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Sample records for agua hirviente bwr

  1. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Energy Technology Data Exchange (ETDEWEB)

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    dans la centrale et aux alentours restent nettement au-dessous des limites fixees par les permis d'exploitation. La simplicite et la facilite d'exploitation des reacteurs a eau bouillante se sont confirmees. La rapidite de reponse du reacteur de Dresden aux variations de la demande est excellente. Aucun des travaux d'entretien et de reparation, quelle que soit leur importance, n'exige de qualification speciale ni ne comporte de risques de radioexposition excessifs. L'inspection generale et la revision de la turbine de la centrale de Dresden n'ont revele aucun probleme d'entretien apres 12 000 h de fonctionnement avec la vapeur en cycle direct. Or, on avait continue l'exploitation apres avoir constate que des cartouches de combustible etaient deteriorees. (author) [Spanish] El autor sefiala que la experiencia adquirida con la explotacion de centrales nucleoeleonicas que utilizan reactores de agua hirviente es ya bastante considerable. En efecto, al finalizar el aflo 1962 se habian generado mas de 2,2.10{sup 9} kWh en tres centrales nucleoelectricas integradas en redes de distribucion: la central nucleoelectrica de Dresden (Commonwealth Edison Company, Moriis, Illinois), la central nucleoelectrica de Vallecitos (Pacific Gas and Electric Company, Pleasanton, California) y la central nucleoelectrica de Kahl (Reinisch-Westfalisches Elektrizitatswerk y Bayernwerk A.G., Kahl-am-Main, Republica Federal de Alemania). El rendimiento de estas centrales explotadas en condiciones normales de produccion de electricidad es excelente. Los factores de disponibilidad y de capacidad de los reactores y de las plantas constituyen una base firme para prever que las centrales nucleoelectricas dotadas de reactores de agua hirviente funcionaran a regimen continuo en condiciones de seguridad. En 1963 entraran en servicio cuatro nuevas centrales equipadas con reactores de agua hirviente: la central nucleoelectrica de Big Rock Point (Consumere Power Company, Charlevoix, Michigan), la central

  2. 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

  3. 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.

  4. BWR 90 and BWR 90+: Two advanced BWR design generations from ABB

    International Nuclear Information System (INIS)

    Haukeland, S.; Ivung, B.; Pedersen, T.

    1999-01-01

    ABB has two evolutionary advanced light water reactors available today - the BWR 90 boiling water reactor and the System 80+ pressurised water reactor. The BWR 90 is based on the design, construction, commissioning and operation of the BWR 75 plants. The operation experience of the six plants of this advanced design has been very good. The average annual energy availability is above 90%, and total power generation costs have been low. When developing the BWR 90 specific changes were introduced to a reference design, to adapt to technological progress, new safety requirements and to achieve cost savings. The thermal power rating of BWR 90 is 3800 MWth (providing a nominal 1374 MWe net), slightly higher than that of the reference plant ABB Atom has taken advantage of margins gained using a new generation of its SVEA fuel to attain this power rating without major design modifications. The BWR 90 design was completed and offered to the TVO utility in Finland in 1991, as one of the contenders for the fifth Finnish nuclear power plant project. Hence, the design is available today for deployment in new plant projects. Utility views were incorporated through co-operation with the Finnish utility TVO, owner and operator of the two Olkiluoto plants of BWR 75 design. A review against the European Utility Requirement (EUR) set of requirements has been performed, since the design, in 1997, was selected by the EUR Steering Committee to be the first BWR to be evaluated against the EUR documents. The review work was completed in 1998. It will be the subject of an 'EUR Volume 3 Subset for BWR 90' document. ABB is continuing its BWR development work with an 'evolutionary' design called BWR 90+, which aims at developing the BWR as a competitive option for the anticipated revival of the market for new nuclear plants beyond the turn of the century, as well as feeding ideas and inputs to the continuous modernisation efforts at operating plants. The development is performed by ABB Atom

  5. BWR 90: The ABB advanced BWR design

    International Nuclear Information System (INIS)

    Haukeland, S.; Ivung, B.; Pedersen, T.

    1999-01-01

    ABB has two evolutionary advanced fight water reactors available today - the BWR 90 boiling water reactor and the System 80+ pressurised water reactor. The BWR 90 is based on the design, construction, commissioning and operation of the BWR 75 plants. The operation experience of the six plants of this advanced design has been very good. The average annual energy availability is above 90%, and the total power generation costs have been low. In the development of BWR 90 specific changes were introduced to the reference design, to adapt to technological progress, new safety requirements and to achieve cost savings. The thermal power rating of BWR 90 is 3800 MWth (providing a nominal 1374 MWe net), slightly higher dim that of the reference plant ABB Atom has taken advantage of margins gained using a new generation of its SVEA fuel to attain this power rating without major design modifications. The BWR 90 design was completed and offered to the TVO utility in Finland in 1991, as one of the contenders for the fifth Finnish nuclear power plant project. Thus, the design is available today for deployment in new plant projects. Utility views were incorporated through co-operation with the Finnish utility TVO, owner and operator of the two Olkiluoto plants of BWR 75 design. A review against the European Utility Requirement (EUR) set of requirements has been performed, since the design, in 1997, was selected by the EUR Steering Committee to be the first BWR to be evaluated against the EUR documents. The work is scheduled for completion in 1998. It will be the subject of an 'EUR Volume 3 Subset for BWR 90' document. ABB is continuing its BWR development work with the 'evolutionary' design BWR 90+. The primary design goal is to develop the BWR as a competitive option for the anticipated revival of the market for new nuclear plants beyond the turn of the century, as well as feeding ideas and inputs to the continuous modernisation efforts at operating plants. The development is

  6. Compact modular BWR (CM-BWR)

    International Nuclear Information System (INIS)

    Fennern, Larry; Boardman, Charles; Carroll, Douglas G.; Hida, Takahiko

    2003-01-01

    A preliminary assessment has shown that a small 350 MWe BWR reactor can be placed within a close fitting steel containment vessel that is 7.1 meters inside diameter. This allows the technology and manufacturing capability currently used to fabricate large ABWR reactor vessels to be used to provide a factory fabricated containment vessel for a 350 MWe BWR. When a close fitted steel containment is combined with a passive closed loop isolation condenser system and a natural circulating reactor system that contains a large water inventory, primary system leaks cannot uncover the core. This eliminates many of the safety systems needed in response to a LOCA that are common to large, conventional plant designs including. Emergency Core Flooding, Automatic Depressurization System, Active Residual Heat Removal, Safety Related Auxiliary Cooling, Safety Related Diesel Generators, Hydrogen Re-Combiners, Ex-vessel Core Retention and Cooling. By fabricating the containment in a factory and eliminating most of the conventional safety systems, the construction schedule is shortened and the capital cost reduced to levels that would not otherwise be possible for a relatively small modular BWR. This makes the CM-BWR a candidate for applications where smaller incremental power additions are desired relative to a large ALWR or where the local infrastructure is not able to accommodate a conventional ALWR plant rated at 1350 MWe or more. This paper presents a preliminary design description of a Compact Modular BWR (CM-BWR) whose design features dramatically reduce the size and cost of the reactor building and associated safety systems. (author)

  7. Development of a BWR core burn-up calculation code COREBN-BWR

    International Nuclear Information System (INIS)

    Morimoto, Yuichi; Okumura, Keisuke

    1992-05-01

    In order to evaluate core performances of BWR type reactors, the three dimensional core burnup calculation code COREBN-BWR and the fuel management code HIST-BWR have been developed. In analyses of BWR type reactors, thermal hydraulics calculations must be coupled with neutronics calculations to evaluate core performances, because steam void distribution changes according to the change of the power distribution. By installing new functions as follows to the three dimensional core burnup code COREBN2 developed in JAERI for PWR type reactor analyses, the code system becomes to be applicable to burnup analyses of BWR type reactors. (1) Macroscopic cross section calculation function taking into account of coolant void distribution. (2) Thermal hydraulics calculation function to evaluate core flow split, coolant void distribution and thermal margin. (3) Burnup calculation function under the Haling strategy. (4) Fuel management function to incorporate the thermal hydraulics information. This report consists of the general description, calculational models, input data requirements and their explanations, detailed information on usage and sample input. (author)

  8. The BWR Stability Issue

    International Nuclear Information System (INIS)

    D'Auria, F.

    2008-01-01

    The purpose of this paper is to supply general information about Boiling Water Reactor (BWR) stability. The main concerned topics are: phenomenological aspects, experimental database, modelling features and capabilities, numerical models, three-dimensional modelling, BWR system performance during stability, stability monitoring and licensing aspects.

  9. 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)

  10. SCORPIO-BWR: status and future plans

    International Nuclear Information System (INIS)

    Porsmyr, Jan; Bodal, Terje; Beere, William H.

    2004-01-01

    Full text: During the years from 2000 to 2003 a joint project has been performed by IFE, Halden and TEPCO Systems Corporation, Japan, to develop a core monitoring system for BWRs based on the their existing core monitoring system TiARA and the SCORPIO framework. It has been emphasised to develop a reliable, flexible, adaptable and user-friendly system, which is easy to maintain. Therefore, a rather general framework (SCORPIO Framework) has been used which facilitates easy software modifications as well as adding/ replacing physics modules. The software modules is integrated in the SCORPIO framework using the Software Bus as the communication tool and with the Picasso UIMS tool for MMI. The SCORPIO-BWR version is developed on a Windows-PC platform. The SCORPIO-BWR version provides all functions, which are necessary for all analyses and operations performed on a BWR plant and comprises functions for on-line core monitoring, predictive analysis and core management with interfaces to plant instrumentation and physics codes. Functions for system initialisation and maintenance are also included. A SCORPIO-BWR version adapted for ABWR was installed in TEPSYS facilities in Tokyo in January 2003, where the final acceptance tests were carried out and accepted. The ABWR version of the system is now in the verification and validation phase. In the period from April 2003 until March 2004 a project for realizing an offline-version of SCORPIO-BWR system, which supports the offline tasks of BWR in-core fuel management for ABWR and BWR-5 type of reactors, was developed. The offline-version of the SCORPIO-BWR system for ABWR and BWR-5 type of reactors was installed at TEPSYS in March 2003, where the final acceptance tests were carried out and accepted. Plans for the next version of this system is to study the possibility of adapting SCORPIO-BWR to work with 'mobile technology'. This means that it should be possible to access and display information from the SCORPIO-BWR system on a

  11. SCORPIO-BWR: status and future plans

    Energy Technology Data Exchange (ETDEWEB)

    Porsmyr, Jan; Bodal, Terje; Beere, William H. (and others)

    2004-07-01

    Full text: During the years from 2000 to 2003 a joint project has been performed by IFE, Halden and TEPCO Systems Corporation, Japan, to develop a core monitoring system for BWRs based on the their existing core monitoring system TiARA and the SCORPIO framework. It has been emphasised to develop a reliable, flexible, adaptable and user-friendly system, which is easy to maintain. Therefore, a rather general framework (SCORPIO Framework) has been used which facilitates easy software modifications as well as adding/ replacing physics modules. The software modules is integrated in the SCORPIO framework using the Software Bus as the communication tool and with the Picasso UIMS tool for MMI. The SCORPIO-BWR version is developed on a Windows-PC platform. The SCORPIO-BWR version provides all functions, which are necessary for all analyses and operations performed on a BWR plant and comprises functions for on-line core monitoring, predictive analysis and core management with interfaces to plant instrumentation and physics codes. Functions for system initialisation and maintenance are also included. A SCORPIO-BWR version adapted for ABWR was installed in TEPSYS facilities in Tokyo in January 2003, where the final acceptance tests were carried out and accepted. The ABWR version of the system is now in the verification and validation phase. In the period from April 2003 until March 2004 a project for realizing an offline-version of SCORPIO-BWR system, which supports the offline tasks of BWR in-core fuel management for ABWR and BWR-5 type of reactors, was developed. The offline-version of the SCORPIO-BWR system for ABWR and BWR-5 type of reactors was installed at TEPSYS in March 2003, where the final acceptance tests were carried out and accepted. Plans for the next version of this system is to study the possibility of adapting SCORPIO-BWR to work with 'mobile technology'. This means that it should be possible to access and display information from the SCORPIO-BWR

  12. High Fidelity BWR Fuel Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Su Jong [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-08-01

    This report describes the Consortium for Advanced Simulation of Light Water Reactors (CASL) work conducted for completion of the Thermal Hydraulics Methods (THM) Level 3 milestone THM.CFD.P13.03: High Fidelity BWR Fuel Simulation. High fidelity computational fluid dynamics (CFD) simulation for Boiling Water Reactor (BWR) was conducted to investigate the applicability and robustness performance of BWR closures. As a preliminary study, a CFD model with simplified Ferrule spacer grid geometry of NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) benchmark has been implemented. Performance of multiphase segregated solver with baseline boiling closures has been evaluated. Although the mean values of void fraction and exit quality of CFD result for BFBT case 4101-61 agreed with experimental data, the local void distribution was not predicted accurately. The mesh quality was one of the critical factors to obtain converged result. The stability and robustness of the simulation was mainly affected by the mesh quality, combination of BWR closure models. In addition, the CFD modeling of fully-detailed spacer grid geometry with mixing vane is necessary for improving the accuracy of CFD simulation.

  13. BWR core melt progression phenomena: Experimental analyses

    International Nuclear Information System (INIS)

    Ott, L.J.

    1992-01-01

    In the BWR Core Melt in Progression Phenomena Program, experimental results concerning severe fuel damage and core melt progression in BWR core geometry are used to evaluate existing models of the governing phenomena. These include control blade eutectic liquefaction and the subsequent relocation and attack on the channel box structure; oxidation heating and hydrogen generation; Zircaloy melting and relocation; and the continuing oxidation of zirconium with metallic blockage formation. Integral data have been obtained from the BWR DF-4 experiment in the ACRR and from BWR tests in the German CORA exreactor fuel-damage test facility. Additional integral data will be obtained from new CORA BWR test, the full-length FLHT-6 BWR test in the NRU test reactor, and the new program of exreactor experiments at Sandia National Laboratories (SNL) on metallic melt relocation and blockage formation. an essential part of this activity is interpretation and use of the results of the BWR tests. The Oak Ridge National Laboratory (ORNL) has developed experiment-specific models for analysis of the BWR experiments; to date, these models have permitted far more precise analyses of the conditions in these experiments than has previously been available. These analyses have provided a basis for more accurate interpretation of the phenomena that the experiments are intended to investigate. The results of posttest analyses of BWR experiments are discussed and significant findings from these analyses are explained. The ORNL control blade/canister models with materials interaction, relocation and blockage models are currently being implemented in SCDAP/RELAP5 as an optional structural component

  14. Development of advanced BWR

    International Nuclear Information System (INIS)

    Toyota, Masatoshi

    1982-01-01

    The Japanese technology and domestic production of BWR type nuclear power plants have been established through the experiences in the construction and operation of BWRs in addition to the technical agreement with the General Electric Co. In early days, the plants experienced some trouble such as stress corrosion cracking and some inconvenience in the operation and maintenance. The government, electric power companies and BWR manufacturers have endeavored to standardize and improve the design of LWRs for the purpose of improving the safety, reliability and the rate of operation and reducing the radiation exposure dose of plant workers. The first and second stages of the standardization and improvement of LWRs have been completed. Five manufacturers of BWRs in the world have continued the conceptual design of a new version of BWR power plants. It was concluded that this is the most desirable version of BWR nuclear power stations, but the technical and economic evaluation must be made before the commercial application. Six electric power companies and three manufacturers of BWRs in Japan set up the organization to develop the technology in cooperation. The internal pump system, the new control rod drive mechanism and others are the main features. (Kako, I.)

  15. BWR Radiation Assessment and Control Program: assessment and control of BWR radiation fields. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    Anstine, L.D.

    1983-05-01

    This report covers work on the BWR Radiation Assessment and Control (BRAC) Program from 1978 to 1982. The major activities during this report period were assessment of the radiation-level trends in BWRs, evaluation of the effects of forward-pumped heater drains on BWR water quality, installation and operation of a corrosion-product deposition loop in an operating BWR, and analyzation of fuel-deposit samples from two BWRs. Radiation fields were found to be controlled by cobalt-60 and to vary from as low as 50 mr/hr to as high as 800 mr/hr on the recirculation-system piping. Detailed information on BWR corrosion films and system deposits is presented in the report. Additionally, the results of an oxygen-injection experiment and recontamination monitoring studies are provided

  16. BWR Full Integral Simulation Test (FIST) Phase II test results and TRAC-BWR model qualification

    International Nuclear Information System (INIS)

    Sutherland, W.A.; Alamgir, M.; Findlay, J.A.; Hwang, W.S.

    1985-10-01

    Eight matrix tests were conducted in the FIST Phase I. These tests investigated the large break, small break and steamline break LOCA's, as well as natural circulation and power transients. There are nine tests in Phase II of the FIST program. They include the following LOCA tests: BWR/6 LPCI line break, BWR/6 intermediate size recirculation break, and a BWR/4 large break. Steady state natural circulation tests with feedwater makeup performed at high and low pressure, and at high pressure with HPCS makeup, are included. Simulation of a transient without rod insertion, and with controlled depressurization, was performed. Also included is a simulation of the Peach Bottom turbine trip test. The final two tests simulated a failure to maintain water level during a postulated accident. A FIST program objective is to assess the TRAC code by comparisons with test data. Two post-test predictions made with TRACB04 are compared with Phase II test data in this report. These are for the BWR/6 LPCI line break LOCA, and the Peach Bottom turbine trip test simulation

  17. Best-estimate analysis development for BWR systems

    International Nuclear Information System (INIS)

    Sutherland, W.A.; Alamgir, M.; Kalra, S.P.; Beckner, W.D.

    1986-01-01

    The Full Integral Simulation Test (FIST) Program is a three pronged approach to the development of best-estimate analysis capability for BWR systems. An experimental program in the FIST BWR system simulator facility extends the LOCA data base and adds operational transients data. An analytical method development program with the BWR-TRAC computer program extends the modeling of BWR specific components and major interfacing systems, and improves numerical techniques to reduce computer running time. A method qualification program tests TRAC-B against experiments run in the FIST facility and extends the results to reactor system applications. With the completion and integration of these three activities, the objective of a best-estimate analysis capability has been achieved. (author)

  18. Panorama of the BWR reactors - Evolution of the concept

    Energy Technology Data Exchange (ETDEWEB)

    Novotny, C.; Uhrig, E. [AREVA NP GmbH, Safety Engineering Department - PEPS-G (Germany)

    2012-01-15

    Nowadays, a fleet of more than 50 boiling water reactors (BWR) are in operation in the world. This article gives a short overview on the developments of nuclear power plants of the BWR type, with a focus on the European builds. It describes the technical bases from the early designs in the fifties, sketches the innovations of the sixties and seventies in the types BWR 69 and 72 (Baulinie 69 and 72) and gives an outlook of a possible next generation BWR. A promising approach in recent BWR developments is the the combination of passive safety systems with established design basis

  19. BWR AXIAL PROFILE

    International Nuclear Information System (INIS)

    Huffer, J.

    2004-01-01

    The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips. Thus, accounting for axially varying burnup in criticality analyses is also referred to as accounting for the ''end effect'' reactivity. The magnitude of the reactivity change due to ''end effect'' is dependent on the initial assembly enrichment, the assembly average burnup, and the particular axial profile characterizing the burnup distribution. The set of bounding axial profiles should incorporate multiple BWR core designs and provide statistical confidence (95 percent confidence that 95 percent of the population is bound by the profile) that end nodes are conservatively represented. The profiles should also conserve the overall burnup of the fuel assembly. More background on BWR axial profiles is provided in Attachment I

  20. GPE-BWR and the containment venting and filtering issue

    International Nuclear Information System (INIS)

    Palomo, J.; Santiago, J. de

    1988-01-01

    The Spanish Boiling Water Reactor Owner's Group (GPE-BWR) is formed by three utilities, owning four units: Santa Maria de Garona (46 MWe, BWR3, Mark I containment), Cofrentes (975 MWe, BWR6, Mark III containment) and Valdecaballeros (2x975 MWe, BWR6, Mark III containment) - all of the reactors having been supplied by General Electric. One of the GPE-BWR's several committees is the Safety and Licensing Committee, which follows up the evolution of severe accident topics and particularly the containment venting and filtering issue. In September 1987, the Consejo de Seguridad Nuclear (CSN), the Spanish Regulatory Body, asked the GPE-BWR to define its position on the installation of a containment venting system. The GPE-BWR created a Working Group which presented a Report on Containment Venting to the CSN in January 1987 gathered from: the US Nuclear Regulatory Commission (NRC); some US utilities; and several European countries, especially France, Germany and Sweden. CSN's review of the containment venting Report and the Action Plan proposed by the GPE-BWR finished in April 1988. The conclusion of the Report and the proposed Action Plan take into account the US NRC's identified open items on severe accidents and the R and D programs scheduled to close these items

  1. Administración del agua. - Capítulo VII: Aprovechamiento de las aguas

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  2. Agua y salud humana

    OpenAIRE

    Cordoba, María Alejandra; Del Coco, Valeria; Basualdo Farjat, Juan A.

    2010-01-01

    La protección de la salud pública requiere agua de bebida segura. La realización de frecuentes exámenes para determinar si el agua contiene organismos indicadores sigue siendo el modo más sensible y especifico de estimar la calidad del agua desde el punto de vista de la higiene. En los países donde existe un sistema de vigilancia integrado, la mayoría de los brotes de origen hídrico han sido vinculados a fallas en el tratamiento, inclusión de agua contaminada en la red o a problemas...

  3. BWR stability analysis

    International Nuclear Information System (INIS)

    Valtonen, K.

    1990-01-01

    The objective of this study has been to examine TVO-I oscillation incident, which occured in February 22.1987 and to find out safety implications of oscillations in ATWS incidents. Calculations have been performed with RAMONA-3B and TRAB codes. RAMONA-3B is a BWR transient analysis code with three-dimencional neutron kinetics and nonequilibrium, nonhomogeneous thermal hydraulics. TRAB code is a one-dimencional BWR transient code which uses methods similar to RAMONA-3B. The results have shown that both codes are capable of analyzing of the oscillation incidents. Both out-of-phase and in-phase oscillations are possible. If the reactor scram fails (ATWS) during oscillations the severe fuel failures are always possible and the reactor core may exceed the prompt criticality

  4. Fundamentals of boiling water reactor (BWR)

    International Nuclear Information System (INIS)

    Bozzola, S.

    1982-01-01

    These lectures on fundamentals of BWR reactor physics are a synthesis of known and established concepts. These lectures are intended to be a comprehensive (even though descriptive in nature) presentation, which would give the basis for a fair understanding of power operation, fuel cycle and safety aspects of the boiling water reactor. The fundamentals of BWR reactor physics are oriented to design and operation. In the first lecture general description of BWR is presented, with emphasis on the reactor physics aspects. A survey of methods applied in fuel and core design and operation is presented in the second lecture in order to indicate the main features of the calculational tools. The third and fourth lectures are devoted to review of BWR design bases, reactivity requirements, reactivity and power control, fuel loading patterns. Moreover, operating limits are reviewed, as the actual limits during power operation and constraints for reactor physics analyses (design and operation). The basic elements of core management are also presented. The constraints on control rod movements during the achieving of criticality and low power operation are illustrated in the fifth lecture. Some considerations on plant transient analyses are also presented in the fifth lecture, in order to show the impact between core and fuel performance and plant/system performance. The last (sixth) lecture is devoted to the open vessel testing during the startup of a commercial BWR. A control rod calibration is also illustrated. (author)

  5. 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

  6. BWR Refill-Reflood Program, Task 4.7 - model development: TRAC-BWR component models

    International Nuclear Information System (INIS)

    Cheung, Y.K.; Parameswaran, V.; Shaug, J.C.

    1983-09-01

    TRAC (Transient Reactor Analysis Code) is a computer code for best-estimate analysis for the thermal hydraulic conditions in a reactor system. The development and assessment of the BWR component models developed under the Refill/Reflood Program that are necessary to structure a BWR-version of TRAC are described in this report. These component models are the jet pump, steam separator, steam dryer, two-phase level tracking model, and upper-plenum mixing model. These models have been implemented into TRAC-B02. Also a single-channel option has been developed for individual fuel-channel analysis following a system-response calculation

  7. Boiling water system of nuclear power plants (BWR)

    International Nuclear Information System (INIS)

    Martias Nurdin

    1975-01-01

    About 85% of the world electric generators are light water reactors. It shows that LWR is technologically and economically competitive with other generators. The Boiling Water Reactor (BWR) is one of the two systems in the LWR group. The techniques of BWR operation in several countries, especially low and moderate power BWR, are presented. The discussion is made in relation with the interconnection problems of electric installation in developing countries, including Indonesia, where the total electric energy installation is low. The high reliability and great flexibility of the operation of a boiling water reactor for a sufficiently long period are also presented. Component standardization for BWR system is discussed to get a better technological and economical performance for further development. (author)

  8. Vigilancia sanitaria de cianobacterias en aguas de consumo humano y aguas de baño

    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

  9. Administración del agua. - Capítulo II: Organización administrativa del agua.

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  10. Synergistic failure of BWR internals

    International Nuclear Information System (INIS)

    Ware, A. G.; Chang, T.Y.

    1999-01-01

    Boiling Water Reactor (BWR) core shrouds and other reactor internals important to safety are experiencing intergranular stress corrosion cracking (IGSCC). The United States Nuclear Regulatory Commission has followed the problem, and as part of its investigations, contracted with the Idaho National Engineering and Environmental Laboratory to conduct a risk assessment. The overall project objective is to assess the potential consequences and risks associated with the failure of IGSCC-susceptible BWR vessel internals, with specific consideration given to potential cascading and common mode effects. An initial phase has been completed in which background material was gathered and evaluated, and potential accident sequences were identified. A second phase is underway to perform a simplified, quantitative probabilistic risk assessment on a representative high-power BWR/4. Results of the initial study conducted on the jet pumps show that any cascading failures would not result in a significant increase in the core damage frequency. The methodology is currently being extended to other major reactor internals components

  11. Utility experience with BWR-PSMS

    International Nuclear Information System (INIS)

    Bond, G.R.

    1986-01-01

    The BWR Power Shape Monitoring System (BWR-PSMS) has proven to be an effective and versatile tool for core monitoring. GPU Nuclear Corporation's (GPUN) Oyster Creek plant has been involved in the PSMS development since its inception, having been selected by EPRI as the initial demonstration site. Beginning with Cycle 10, Oyster Creek has been applying the BWR-PSMS as the primary core monitoring tool. Although the system has been in operation at Oyster Creek for the past several cycles, this is the first time the PSMS was used to monitor compliance to the plant technical specifications, to guide adherence to vendore fuel maneuvering recommendations and to develop data for certain performance records such as fuel burnup, isotopic accounting, etc. This paper will discuss the bases for the decision to apply PSMS as the fundamental core monitoring system, the experience in implementing the PSMS in this mode, activities currently underway or planned related to PSMS, and potential future extensions and applications of PSMS at Oyster Creek

  12. 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

  13. EPRI BWR Water Chemistry Guidelines Revision

    International Nuclear Information System (INIS)

    Garcia, Susan E.; Giannelli, Joseph F.

    2014-01-01

    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

  14. Potencial del Agua del suelo

    Directory of Open Access Journals (Sweden)

    Bustamante Heliodoro

    1986-12-01

    Full Text Available 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 importante por sí misma, sino por su relación con la energía en diferentes lugares dentro del suelo. El concepto Potencial de agua del suelo es un criterio para esta energía.

  15. 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).

  16. BWR Services maintenance training program

    International Nuclear Information System (INIS)

    Cox, J.H.; Chittenden, W.F.

    1979-01-01

    BWR Services has implemented a five-phase program to increase plant availability and capacity factor in operating BWR's. One phase of this program is establishing a maintenance training program on NSSS equipment; the scope encompasses maintenance on both mechanical equipment and electrical control and instrumentation equipment. The program utilizes actual product line equipment for practical Hands-on training. A total of 23 formal courses will be in place by the end of 1979. The General Electric Company is making a multimillion dollar investment in facilities to support this training. These facilities are described

  17. Behaviour of the reactivity for BWR fuel cells; Comportamiento de la reactividad para celdas de combustible BWR

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, J. A.; Alonso, G.; Delfin, A.; Vargas, S. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E., E-mail: galonso@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, U. P. Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico)

    2011-11-15

    In this work the behaviour of the reactivity of a fuel assembly type BWR was studied, the objective is to obtain some expressions that consider the average enrichment of U-235 and the gadolinium concentration like a function of the fuel cells burnt. Also, the applicability of the lineal reactivity model was analyzed for fuel cells type BWR. The analysis was carried out with the CASMO-4 code. (Author)

  18. Moderator temperature coefficient in BWR core

    International Nuclear Information System (INIS)

    Naito, Yoshitaka

    1977-01-01

    Temperature dependences of infinite multiplication factor k sub(infinity) and neutron leakage from the core must be examined for estimation of moderator temperature coefficient. Temperature dependence on k sub(infinity) has been investigated by many researchers, however, the dependence on neutron leakage of a BWR with cruciformed control rods has hardly been done. Because there are difficulties and necessity on calculations of three space dimensional and multi-energy groups neutron distribution in a BWR core. In this study, moderator temperature coefficients of JPDR-II (BWR) core were obtained by calculation with DIFFUSION-ACE, which is newly developed three-dimensional multi-group computer code. The results were compared with experimental data measured from 20 to 275 0 C of the moderator temperature and the good agreement was obtained between calculation and measurement. In order to evaluate neutron leakage from the core, the other two calculations were carried out, adjusting criticality by uniform absorption rate and by material buckling. The former underestimated neutron leakage and the latter overestimated it. Discussion on the results shows that in order to estimate the temperature coefficient of BWR, neutron leakage must be evaluated precisely, therefore the calculation at actual pattern of control rods is necessary. (auth.)

  19. BWR stability analysis at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Wulff, W.; Cheng, H.S.; Mallen, A.N.; Rohatgi, U.S.

    1991-01-01

    Following the unexpected, but safely terminated, power and flow oscillations in the LaSalle-2 Boiling Water Reactor (BWR) on March 9, 1988, the Nuclear Regulatory Commission (NRC) Offices of Nuclear Reactor Regulation (NRR) and of Analysis and Evaluation of Operational Data (AEOD) requested that the Office of Nuclear Regulatory Research (RES) carry out BWR stability analyses, centered around fourteen specific questions. Ten of the fourteen questions address BWR stability issues in general and are dealt with in this paper. The other four questions address local, out-of-phase oscillations and matters of instrumentation; they fall outside the scope of the work reported here. It was the purpose of the work documented in this report to answer ten of the fourteen NRC-stipulated questions. Nine questions are answered by analyzing the LaSalle-2 instability and related BWR transients with the BNL Engineering Plant Analyzer (EPA) and by performing an uncertainty assessment of the EPA predictions. The tenth question is answered on the basis of first principles. The ten answers are summarized

  20. 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.

  1. Residual stress analysis in BWR pressure vessel attachments

    International Nuclear Information System (INIS)

    Dexter, R.J.; Leung, C.P.; Pont, D.

    1992-06-01

    Residual stresses from welding processes can be the primary driving force for stress corrosion cracking (SCC) in BWR components. Thus, a better understanding of the causes and nature of these residual stresses can help assess and remedy SCC. Numerical welding simulation software, such as SYSWELD, and material property data have been used to quantify residual stresses for application to SCC assessments in BWR components. Furthermore, parametric studies using SYSWELD have revealed which variables significantly affect predicted residual stress. Overall, numerical modeling techniques can be used to evaluate residual stress for SCC assessments of BWR components and to identify and plan future SCC research

  2. BWR Refill-Reflood Program. Final report

    International Nuclear Information System (INIS)

    Myers, L.L.

    1983-09-01

    The BWR Refill-Reflood Program is part of the continuing Loss of Coolant Accident (LOCA) research in the United States which is jointly sponsored by the Nuclear Regulatory Commission, the Electric Power Research Institute, and the General Electric Company. The current program expanded the focus of this research to include full scale experimental evaluations of multidimensional and multichannel effects during system refill. The program has also made major contributions to the BWR version of the Transient Reactor Analysis Code (TRAC) which has been developed cooperatively with the Idaho National Engineering Laboratory (INEL) for application to BWR transients. A summary description of the complete program is provided including the principal findings and main conclusions of the program. The results of the program have shown that multidimensional and parallel channel effects have the potential to significantly improve the system response over that observed in single channel tests

  3. BWR Steam Dryer Alternating Stress Assessment Procedures

    Energy Technology Data Exchange (ETDEWEB)

    Morante, R. J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Hambric, S. A. [Brookhaven National Lab. (BNL), Upton, NY (United States); Ziada, S. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2016-12-01

    This report presents an overview of Boiling Water Reactor (BWR) steam dryer design; the fatigue cracking failures that occurred at the Quad Cities (QC) plants and their root causes; a history of BWR Extended Power Uprates (EPUs) in the USA; and a discussion of steam dryer modifications/replacements, alternating stress mechanisms on steam dryers, and structural integrity evaluations (static and alternating stress).

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

    International Nuclear Information System (INIS)

    Espinosa-Paredes, Gilberto; Nunez-Carrera, Alejandro; Vazquez-Rodriguez, Alejandro

    2006-01-01

    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

  5. Administración del agua. - Capítulo X: Administración centralizada del agua en Venezuela

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  6. ABB advanced BWR and PWR fuel

    International Nuclear Information System (INIS)

    Junkrans, S.; Helmersson, S.; Andersson, S.

    1999-01-01

    Fuel designed and fabricated by ABB is now operating in 40 PWRs and BWRs in Europe, the United States and Korea. An excellent fuel reliability track record has been established. High burnups are proven for both BWR and PWR. Thermal margin improving features and advanced burnable absorber concepts enable the utilities to adopt demanding duty cycles to meet new economic objectives. In particular we note the excellent reliability record of ABB PWR fuel equipped with Guardian TM debris filter, proven to meet the -6 rod-cycles fuel failure goal, and the out-standing operating record of the SVEA 10x10 BWR fuel, where ABB is the only vendor to date with multi batch experience to high burnup. ABB is dedicated to maintain high fuel reliability as well as continually improve and develop a broad line of BWR and PWR products. ABB's development and fuel follow-up activities are performed in close co-operation with its customers. (orig.)

  7. BWR control blade replacement strategies

    Energy Technology Data Exchange (ETDEWEB)

    Kennard, M W [Stoller Nuclear Fuel, NAC International, Pleasantville, NY (United States); Harbottle, J E [Stoller Nuclear Fuel, NAC International, Thornbury, Bristol (United Kingdom)

    2000-02-01

    The reactivity control elements in a BWR, the control blades, perform three significant functions: provide shutdown margin during normal and accident operating conditions; provide overall core reactivity control; and provide axial power shaping control. As such, the blades are exposed to the core's neutron flux, resulting in irradiation of blade structural and absorber materials. Since the absorber depletes with time (if B{sub 4}C is used, it also swells) and the structural components undergo various degradation mechanisms (e.g., embrittlement, corrosion), the blades have limits on their operational lifetimes. Consequently, BWR utilities have implemented strategies that aim to maximize blade lifetimes while balancing operational costs, such as extending a refuelling outage to shuffle high exposure blades. This paper examines the blade replacement strategies used by BWR utilities operating in US, Europe and Asia by assembling information related to: the utility's specific blade replacement strategy; the impact the newer blade designs and changes in core operating mode were having on those strategies; the mechanical and nuclear limits that determined those strategies; the methods employed to ensure that lifetime limits were not exceeded during operation; and blade designs used (current and replacement blades). (author)

  8. BWR control blade replacement strategies

    International Nuclear Information System (INIS)

    Kennard, M.W.; Harbottle, J.E.

    2000-01-01

    The reactivity control elements in a BWR, the control blades, perform three significant functions: provide shutdown margin during normal and accident operating conditions; provide overall core reactivity control; and provide axial power shaping control. As such, the blades are exposed to the core's neutron flux, resulting in irradiation of blade structural and absorber materials. Since the absorber depletes with time (if B 4 C is used, it also swells) and the structural components undergo various degradation mechanisms (e.g., embrittlement, corrosion), the blades have limits on their operational lifetimes. Consequently, BWR utilities have implemented strategies that aim to maximize blade lifetimes while balancing operational costs, such as extending a refuelling outage to shuffle high exposure blades. This paper examines the blade replacement strategies used by BWR utilities operating in US, Europe and Asia by assembling information related to: the utility's specific blade replacement strategy; the impact the newer blade designs and changes in core operating mode were having on those strategies; the mechanical and nuclear limits that determined those strategies; the methods employed to ensure that lifetime limits were not exceeded during operation; and blade designs used (current and replacement blades). (author)

  9. Burnup credit feasibility for BWR spent fuel shipments

    International Nuclear Information System (INIS)

    Broadhead, B.L.

    1990-01-01

    Considerable interest in the allowance of reactivity credit for the exposure history of power reactor fuel currently exists. This ''burnup credit'' issue has the potential to greatly reduce risk and cost when applied to the design and certification of spent of fuel casks used for transportation and storage. Analyses 1 have shown the feasibility estimated the risk and economic incentives for allowing burnup credit in pressurized water reactor (PWR) spent fuel shipping cask applications. This paper summarizes the extension of the previous PWR feasibility assessments to boiling water reactor (BWR) fuel. As with the PWR analysis, the purpose was not verification of burnup credit (see ref. 2 for ongoing work in this area) but a reasonable assessment of the feasibility and potential gains from its use in BWR applications. This feasibility analysis aims to apply simple methods that adequately characterize the time-dependent isotopic compositions of typical BWR fuel. An initial analysis objective was to identify a simple and reliable method for characterizing BWR spent fuel. The method includes characterization of a typical pin-cell spectrum, using a one-dimensional (1-D) model of a BWR assembly. The calculated spectrum allows burnup-dependent few-group material constants to be generated. Point depletion methods were then used to obtain the time-varying characteristics of the fuel. These simple methods were validated, where practical, with multidimensional methods. 6 refs., 1 tab

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

    International Nuclear Information System (INIS)

    Colby, M.J.; Townsend, D.B.; Kunz, C.L.

    1980-06-01

    A denatured (U-233/Th)O 2 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 UO 2 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)O 2 -fueled BWR will likely have reduced operating flexibility. A (U-235/Th)O 2 -fueled BWR should perform similar to a UO 2 -fueled BWR under all operating conditions. A (Pu/Th)O 2 -fueled BWR may have reduced thermal margins and similar accident response and be less stable than a UO 2 -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

  11. BWR vessel and internals project (BWRVIP)

    International Nuclear Information System (INIS)

    Bilanin, W.J.; Dyle, R.L.

    1996-01-01

    Recent Boiling Water Reactor (BWR) inspections indicate that Intergranular Stress Corrosion Cracking (IGSCC) is a significant technical issue for some BWR internals. IN response, the Boiling Water Reactor Vessel and Internals Project (BWRVIP) was formed by an associated of domestic and international utilities which own and operate BWRs. The project is identifying or developing generic, cost-effective strategies for managing degradation of reactor internals from which each utility can select the alternative most appropriate for their plant. The Electric Power Research Institute manages the technical program, implementing the utility defined programs. The BWRVIP is organized into four technical tasks: Assessment, Inspection, Repair and Mitigation. An Integration task coordinates the work. The goal of the Assessment task is to develop methodologies for evaluation of vessel and internal components in support of decisions for operation, inspection, mitigation or repair. The goal of the Inspection task is to develop and assess effective and predictable inspection techniques which can be used to determine the condition of BWR vessel and internals that are potentially susceptible to service-related SCC degradation. The goal of the Repair task is to assure the availability of cost-effective repair/replacement alternatives. The goal of the Mitigation task is to develop and demonstrate countermeasures for SCC degradation. This paper summarizes the BWRVIP approach for addressing BWR internals SCC degradation and illustrates how utilities are utilizing BWRVIP products to successfully manage the effect of SCC on core shrouds

  12. Strategies of operation cycles in BWR type reactors

    International Nuclear Information System (INIS)

    Molina, D.; Sendino, F.

    1996-01-01

    The article analyzes the operation cycles in BWR type reactors. The cycle size of operation is the consequence on the optimization process of the costs with the technical characteristics of nuclear fuel and the characteristics of demand and production. The authors analyze the cases of Garona NP and Cofrentes NP, both with BWR reactors. (Author)

  13. Review of international solutions to NEACRP benchmark BWR lattice cell problems

    International Nuclear Information System (INIS)

    Halsall, M.J.

    1977-12-01

    This paper summarises international solutions to a set of BWR benchmark problems. The problems, posed as an activity sponsored by the Nuclear Energy Agency Committee on Reactor Physics, were as follows: 9-pin supercell with central burnable poison pin, mini-BWR with 4 pin-cells and water gaps and control rod cruciform, full 7 x 7 pin BWR lattice cell with differential U 235 enrichment, and full 8 x 8 pin BWR lattice cell with water-hole, Pu-loading, burnable poison, and homogenised cruciform control rod. Solutions have been contributed by Denmark, Japan, Sweden, Switzerland and the UK. (author)

  14. Improvement for BWR operator training, 3

    International Nuclear Information System (INIS)

    Noji, Kunio; Toeda, Susumu; Saito, Genhachi; Suzuki, Koichi

    1990-01-01

    BWR Operator Training Center Corporation (BTC) is conducting training for BWR plant operators using Full-scope Simulators. There are several courses for individual operators and one training course for shift crew (Family Training Course) in BTC. Family Training is carried out by all members of the operating shift-crew. BTC has made efforts to improve the Family Training in order to acquire more effective training results and contribute to up-grade team performance of all crews. This paper describes some items of our efforts towards Family Training improvement. (author)

  15. Assessment of two BWR accident management strategies

    International Nuclear Information System (INIS)

    Hodge, S.A.; Petek, M.

    1991-01-01

    Candidate mitigative strategies for management of in-vessel events during the late phase (after core degradation has occurred) of postulated BWR severe accidents were considered at Oak Ridge National Laboratory (ORNL) during 1990. The identification of new strategies was subject to the constraint that they should, to the maximum extent possible, make use of the existing equipment and water resources of the BWR facilities and not require major equipment modifications or additions. As a result of this effort, two of these candidate strategies were recommended for additional assessment. The first is a strategy for containment flooding to maintain the core and structural debris within the reactor vessel in the event that vessel injection cannot be restored to terminate a severe accident sequence. The second strategy pertains to the opposite case, for which vessel injection would be restored after control blade melting had begun; its purpose is to provide an injection source of borated water at the concentration necessary to preclude criticality upon recovering a damaged BWR core. Assessments of these two strategies have been performed during 1991 under the auspices of the Detailed Assessment of BWR In-Vessel Strategies Program. This paper provides a discussion of the motivation for and purpose of these strategies and the potential for their success. 33 refs., 9 figs

  16. Administración del agua. - Capítulo IV: Los usuarios y la gestión del agua

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  17. Kinematics of two-phase mixture level motion in BWR pressure vessels

    International Nuclear Information System (INIS)

    Wulff, W.; Cheng, H.S.; Mallen, A.N.; Stritar, A.

    1985-01-01

    A model is presented for predicting two-phase mixture level elevations in BWR systems. The model accounts for the particular geometry and conditions in a BWR system during Small-Break Loss of Coolant Accidents. The model presented here is particularly suitable for efficient, high-speed simulations on small minicomputers. The model has been implemented and tested. Results are shown from BWR ATWS simulations

  18. Vigilancia sanitaria de cianobacterias en aguas de consumo humano y aguas de baño

    OpenAIRE

    Guadalupe Martínez Juárez; Idoia Merino Azcue

    2008-01-01

    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,...

  19. Improvement for BWR operator training

    International Nuclear Information System (INIS)

    Tsuchiya, Toshio; Masuda, Hisao; Isono, Tomoyuki; Noji, Kunio; Togo, Toshiki

    1989-01-01

    BWR Operator Training Center Corporation (BTC) was established in April 1971 for the purpose of training the operators from all BWR utilities in Japan. Since April 1974, more than 2600 operators and 1000 shift teams have been trained with the full-scope simulators in BTC up to the end of March 1988. To get the satisfactory results of the training, BTC has been making every effort to improve the facilities, the training materials, the instruction methods and the curricula. In this paper, such a series of recent improvements in the instruction methods and the curricula are presented that are effective to expand the knowledge and to improve the skills of middle or senior class operators. (author)

  20. 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 superfi...

  1. Application of gadolinia credit to cask transportation of BWR-STEP3 SFAs

    International Nuclear Information System (INIS)

    Kikuchi, Tsukasa; Mitsuhashi, Ishi; Ito, Dai-ichiro; Nakamura, Yu

    2003-01-01

    Instead of the fresh-fuel assumption, the application of gadolinia credit to cask transportation of BWR SFAs is studied. Its efficacy for BWR-STEP2 SFAs had already been estimated. This paper reports on the application of gadolinia credit to cask transportation of BWR-STEP3 SFAs. (author)

  2. Seismic risk assessment of a BWR: status report

    International Nuclear Information System (INIS)

    Chuang, T.Y.; Bernreuter, D.L.; Wells, J.E.; Johnson, J.J.

    1985-02-01

    The seismic risk methodology developed in the US NRC Seismic Safety Margins Research Program (SSMRP) was demonstrated by its application to the Zion nuclear power plant, a pressurized water reactor (PWR). A detailed model of Zion, including systems analysis models (initiating events, event trees, and fault trees), SSI and structure models, and piping models was developed and analyzed. The SSMRP methodology can equally be applied to a boiling water reactor (BWR). To demonstrate its applicability, to identify fundamental differences in seismic risk between a PWR and a BWR, and to provide a basis of comparison of seismic risk between a PWR and a BWR when analyzed with comparable methodology and assumptions, a seismic risk analysis is being performed on the LaSalle County Station nuclear power plant

  3. Administración del agua. - Conclusiones generales

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  4. BWR plant analyzer development at BNL

    International Nuclear Information System (INIS)

    Cheng, H.S.; Wulff, W.; Mallen, A.N.; Lekach, S.V.; Stritar, A.; Cerbone, R.J.

    1985-01-01

    Advanced technology for high-speed interactive nuclear power plant simulations is of great value for timely resolution of safety issues, for plant monitoring, and for computer-aided emergency responses to an accident. Presented is the methodology employed at BNL to develop a BWR plant analyzer capable of simulating severe plant transients at much faster than real-time process speeds. Five modeling principles are established and a criterion is given for selecting numerical procedures and efficient computers to achieve the very high simulation speeds. Typical results are shown to demonstrate the modeling fidelity of the BWR plant analyzer

  5. Estudio de patentes sobre tecnologías para tratamiento de agua y el agua residual

    Directory of Open Access Journals (Sweden)

    Odonel González-Cabrera

    Full Text Available Se presenta un estudio de patentes sobre la temática tratamiento de agua y agua residual. Se localizan y descargan más de 2.500 documentos de patentes relacionados con la temática. Estos se procesan en software al efecto y herramientas de procesamiento. Se extraen indicadores de patentes para esta tecnología con alto valor para actividades comerciales y de investigación, tales como tecnologías emergentes sobre tratamiento de agua, países, entidades e inventores líderes a nivel mundial según el resultado de la tecnología patentada. Se presenta la evolución de las tecnologías de tratamiento del agua y el agua residual en los últimos veinte años a nivel mundial según el registro de las patentes. La entrega de todo el material se realiza enuna herramienta de visualización que logra hacer más atractivo el servicio, tener un producto más amigable y cómodo para el uso, constituyendo una información de alto nivel de actualización y eficacia para la toma de decisiones de una empresa de proyectos e investigaciones hidráulicas.

  6. Development of new irradiation facility for BWR safety research

    International Nuclear Information System (INIS)

    Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Ohmi, Masao

    2013-01-01

    In JAEA (Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation. (author)

  7. aguas residuales en la guajira (Colombia

    Directory of Open Access Journals (Sweden)

    Camilo Madariaga

    2005-01-01

    Full Text Available Este estudio muestra la descripción de los resultados del componente social y comunicacional del proyecto sobre el desarrollo e implementación de modelos matemáticos para la representación del comportamiento de plantas de tratamiento de aguas residuales en los quince (15 municipios del departamento de La Guajira (Colombia. Con los problemas de escasez de agua se ha empezado a prestar gran atención a un recurso cercano, concentrado y cuya calidad es relativamente constante y conocida: el agua residual. Los resultados mostraron la falta de conocimiento por parte de casi todos los actores sociales con respecto al estado, proceso, planificación y ejecución de trabajo con el sistema de agua. Asimismo, en cuanto a la posibilidad de reutilización de aguas servidas después de un procedimiento de tratamiento adecuado en las lagunas de estabilización, éstas no tienen las condiciones estructurales para el trabajo de tratamiento y la comunidad en general desconoce su existencia.

  8. "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

  9. Interpretation of incore noise measurements in BWR's

    International Nuclear Information System (INIS)

    Dam, H. van

    1982-01-01

    A survey is given of the main incentives for power reactor noise research and the differences and similarities of noise in power and zero power systems are touched on. The basic characteristics of the adjoint method in reactor noise theory are treated. The detector adjoint functions describe the transfer functions between spatially distributed noise sources and a (neutron or gamma) detector. In particular, the spatial dependence of these functions explains the 'local' and 'global' effects in BWR noise measurements. By including thermal hydraulic feedback effects in the adjoint analysis, it is shown that the common idea of a dominant global effect at low frequencies which should result in point kinetic behaviour, is erroneous. The same analysis provides a method for nonperturbing on-line measurement of the reactor transfer function, which is demonstrated by results from measurements on a BWR in the Netherlands. In the final part of the paper some ideas are given for further research in the field of BWR noise. (author)

  10. Interpretation of incore noise measurements in BWR's

    International Nuclear Information System (INIS)

    Dam, H. van

    1983-01-01

    A survey is given of the main incentives for power reactor noise research, and the differences and similarities of noise in power and zero power systems are shown. After a short outline of historical developments the basic characteristics of the adjoint method in reactor noise theory are dealt with. The detector adjoint functions describe the transfer functions between spatially distributed noise sources and a (neutron or gamma) detector. In particular, the spatial dependence of these functions explains the 'local' and 'global' effects in BWR noise measurements. By including thermal hydraulic feedback effects in the adjoint analysis, it is shown that the common idea of a dominant global effect at low frequencies, which should result in point kinetic behaviour, is erroneous. The same analysis provides a method for nonperturbing on-line measurements on a BWR in The Netherlands. In the final part of the paper some ideas are given for further research in the field of BWR noise. (author)

  11. EVALUACIÓN DE LA CALIDAD MICROBIOLÓGICA DEL AGUA PARA CONSUMO Y DEL AGUA RESIDUAL EN UNA POBLACIÓN DE BOGOTÁ (COLOMBIA)

    OpenAIRE

    Venegas B, Camilo; Mercado R, Marcela; Campos, María Claudia

    2014-01-01

    En Colombia el acceso al agua potable y a sistemas de saneamiento no están garantizados para buena parte de la población, por lo que el consumo de agua contaminada genera enfermedades de origen hídrico. La alternativa más utilizada para el acceso al agua potable es su almacenamiento dentro de las viviendas y la improvisación de sistemas de alcantarillado que generalmente se encuentran a cielo abierto. Objetivo: Evaluar la calidad microbiológica del agua utilizada para consumo y el agua residu...

  12. The HAMBO BWR simulator of HAMMLAB

    International Nuclear Information System (INIS)

    Karlsson, Tommy; Jokstad, Haakon; Meyer, Brita D.; Nihlwing, Christer; Norrman, Sixten; Puska, Eija Karita; Raussi, Pekka; Tiihonen, Olli

    2001-02-01

    Modernisation of control rooms of the nuclear power plants has been a major issue in Sweden and Finland the last few years, and this will continue in the years to come. As an aid in the process of introducing new technology into the control rooms, the benefit of having an experimental simulator where proto typing of solutions can be performed, has been emphasised by many plants. With this as a basis, the BWR plants in Sweden and Finland decided to fund, in co-operation with the Halden Project, an experimental BWR simulator based on the Forsmark 3 plant in Sweden. The BWR simulator development project was initiated in January 1998. VTT Energy in Finland developed the simulator models with the aid of their APROS tool, while the operator interface was developed by the Halden Project. The simulator was thoroughly tested by experienced HRP personnel and professional Forsmark 3 operators, and accepted by the BWR utilities in June 2000. The acceptance tests consisted of 19 well-defined transients, as well as the running of the simulator from full power down to cold shutdown and back up again with the use of plant procedures. This report describes the HAMBO simulator, with its simulator models, the operator interface, and the underlying hardware and software infrastructure. The tools used for developing the simulator, APROS, Picasso-3 and the Integration Platform, are also briefly described. The acceptance tests are described, and examples of the results are presented, to illustrate the level of validation of the simulator. The report concludes with an indication of the short-term usage of the simulator. (Author)

  13. Development of next BWR plant

    International Nuclear Information System (INIS)

    Moriya, Kumiaki; Tanikawa, Naoshi; Kinoshita, Shoichiro; Utena, Shunsuke

    1995-01-01

    It is expected that BWR power generation will be main nuclear power generation for long period hereafter, and in the ABWRs being constructed at present, the safety, reliability, operation performance, economical efficiency and so on are further heightend as compared with conventional BWRs. On the other hand, in order to cope with future social change, the move to develop the next reactor type following ABWRs was begun already by the cooperation of electirc power companies and plant manufacturers. Hitachi Ltd. has advanced eagerly the development of new light water reactors. Also the objective of BWR power generation hereafter is to heighten the safety, reliability, operation performance and economical efficiency, and the development has been advanced, aiming at bearing the main roles of nuclear power generation. At present, ABWRs are under construction as No. 6 and 7 plants in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. In order to let ABWRs take root, the further improvement of economy by the standardization, the rationalization by revising the specification and the improvement of machinery and equipment is necessary. As the needs of the development of next generation BWRs, the increase of power output, the heightening of safety and economical efficiency are discussed. The concept of the next generation BWR plant aiming at the start of operation around 2010 is shown. (K.I.)

  14. Development of next BWR plant

    Energy Technology Data Exchange (ETDEWEB)

    Moriya, Kumiaki; Tanikawa, Naoshi; Kinoshita, Shoichiro; Utena, Shunsuke [Hitachi Ltd., Ibaraki (Japan). Hitachi Works

    1995-04-01

    It is expected that BWR power generation will be main nuclear power generation for long period hereafter, and in the ABWRs being constructed at present, the safety, reliability, operation performance, economical efficiency and so on are further heightend as compared with conventional BWRs. On the other hand, in order to cope with future social change, the move to develop the next reactor type following ABWRs was begun already by the cooperation of electirc power companies and plant manufacturers. Hitachi Ltd. has advanced eagerly the development of new light water reactors. Also the objective of BWR power generation hereafter is to heighten the safety, reliability, operation performance and economical efficiency, and the development has been advanced, aiming at bearing the main roles of nuclear power generation. At present, ABWRs are under construction as No. 6 and 7 plants in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. In order to let ABWRs take root, the further improvement of economy by the standardization, the rationalization by revising the specification and the improvement of machinery and equipment is necessary. As the needs of the development of next generation BWRs, the increase of power output, the heightening of safety and economical efficiency are discussed. The concept of the next generation BWR plant aiming at the start of operation around 2010 is shown. (K.I.).

  15. Transmutation of minor actinide using thorium fueled BWR core

    International Nuclear Information System (INIS)

    Susilo, Jati

    2002-01-01

    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 6 t h 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

  16. Decay ratio studies in BWR and PWR using wavelet

    International Nuclear Information System (INIS)

    Ciftcioglu, Oe.

    1996-10-01

    The on-line stability of BWR and PWR is studied using the neutron noise signals as the fluctuations reflect the dynamic characteristics of the reactor. Using appropriate signal modeling for time domain analysis of noise signals, the stability parameters can be directly obtained from the system impulse response. Here in particular for BWR, an important stability parameter is the decay ratio (DR) of the impulse response. The time series analysis involves the autoregressive modeling of the neutron detector signal. The DR determination is strongly effected by the low frequency behaviour since the transfer function characteristic tends to be a third order system rather than a second order system for a BWR. In a PWR low frequency behaviour is modified by the Boron concentration. As a result of these phenomena there are difficulties in the consistent determination of the DR oscillations. The enhancement of the consistency of this DR estimation is obtained by wavelet transform using actual power plant data from BWR and PWR. A comparative study of the Restimation with and without wavelets are presented. (orig.)

  17. BWR radiation exposure--experience and projection

    International Nuclear Information System (INIS)

    Falk, C.F.; Wilkinson, C.D.; Hollander, W.R.

    1979-01-01

    The BWR/6 Mark III radiation exposures are projected to be about half of those of current average operating experience of 725 man-rem. These projections are said to be realistic and based on current achievements and not on promises of future development. The several BWRs operating with low primary system radiation levels are positive evidence that radiation sources can be reduced. Improvements have been made in reducing the maintenance times for the BWR/6, and further improvements can be made by further attention to cost-effective plant arrangement and layout during detail design to improve accessibility and maintainability of each system and component

  18. The BWR Hybrid 4 control rod

    International Nuclear Information System (INIS)

    Gross, H.; Fuchs, H.P.; Lippert, H.J.; Dambietz, W.

    1988-01-01

    The service life of BWR control rods designed in the past has been unsatisfactory. The main reason was irradiation assisted stress corrosion cracking of B 4 C rods caused by external swelling of the B 4 C powder. By this reason KWU developed an improved BWR control rod (Hybrid 4 control rod) with extended service life and increased control rod worth. It also allows the procedure for replacing and rearranging fuel assemblies to be considerably simplified. A complete set of Hydbrid 4 control rods is expected to last throughout the service life of a plant (assumption: ca. 40 years) if an appropriate control rod reshuffling management program is used. (orig.)

  19. An overview of the BWR ECCS strainer blockage issues

    International Nuclear Information System (INIS)

    Serkiz, A.W.; Marshall, M.L. Jr.; Elliott, R.

    1996-01-01

    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

  20. BWR type nuclear reactors

    International Nuclear Information System (INIS)

    Yamamoto, Toru.

    1987-01-01

    Purpose: To obtain reactor core characteristics with less changes in the excess reactivity due to fuel burnup even when the operation period varies. Constitution: In a BWR type reactor where fuel assemblies containing fuel rods incorporated with burnable poisons are arranged, the fuel assemblies are grouped into first fuel assemblies and second fuel assemblies. Then, the number of fuel rods incorporated with burnable poisons within the first fuel assemblies is made greater than that of the second fuel rods, while the concentration of the burnable poisons in the fuel rods incorporated with the burnable poisons in the first fuel assemblies is made lower than that of the fuel rods incorporated with the burnable poisons in the second fuel assemblies. In the BWR type reactor constituted in this way, the reactor core characteristics can be improved by changing the ratio between the first fuel assemblies and the second fuel assemblies charged to the reactor core, thereby decreasing the changes in the burnup of the excess reactivity. (Kamimura, M.)

  1. Operator training simulator for BWR nuclear power plant

    International Nuclear Information System (INIS)

    Watanabe, Tadasu

    1988-01-01

    For the operation management of nuclear power stations with high reliability and safety, the role played by operators is very important. The effort of improving the man-machine interface in the central control rooms of nuclear power stations is energetically advanced, but the importance of the role of operators does not change. For the training of the operators of nuclear power stations, simulators have been used from the early stage. As the simulator facilities for operator training, there are the full scope simulator simulating faithfully the central control room of an actual plant and the small simulator mainly aiming at learning the plant functions. For BWR nuclear power stations, two full scope simulators are installed in the BWR Operator Training Center, and the training has been carried out since 1974. The plant function learning simulators have been installed in respective electric power companies as the education and training facilities in the companies. The role of simulators in operator training, the BTC No.1 simulator of a BWR-4 of 780 MWe and the BTC No.2 simulator of a BWR-5 of 1,100 MWe, plant function learning simulators, and the design of the BTC No.2 simulator and plant function learning simulators are reported. (K.I.)

  2. Estudio de la calidad del agua en cisternas de captación de agua de lluvia en escuelas rurales de Alagoas (Brasil)

    OpenAIRE

    Gonzalez Abelleira, Mafalda

    2014-01-01

    El presente trabajo se centra en el estudio de la calidad del agua de Sistemas de Recogida de agua de lluvia en escuelas del Semiárido Alagoano de Brasil. Aspectos de la obra civil también son incluidos. Los Sistemas principalmente están formados por un área de captación de agua de lluvia, cisternas de placas de cemento, canalizaciones que las unen y una bomba manual para la retirada del agua de la cisterna. Se analizaron 206 muestras de parámetros básicos de la calidad del agua – conducti...

  3. FIST small break accident analysis with BWR TRACBO2-pretest predictions

    International Nuclear Information System (INIS)

    Alamgir, M.; Sutherland, W.A.

    1984-01-01

    The BWR Full Integral Simulation Test (FIST) program includes experimental simulation and analytical evaluation of BWR thermal-hydraulic phenomena during transient events. One such event is a small size break in the suction line of one of the recirculation pumps. The results from a test simulating this transient in the FIST facility are compared with a system analysis using the Transient Reactor Analysis Code (TRACB02). This comparison demonstrates BWR-TRAC capability for small break analyses and provides detailed understanding of the phenomena

  4. Administración del agua. - Introducción

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  5. Administración del agua. - Créditos

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

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

    International Nuclear Information System (INIS)

    Kohsaka, Atsuo; Akimoto, Masayuki; Asahi, Yoshiro; Abe, Kiyoharu; Muramatsu, Ken; Araya, Fumimasa; Sato, Kazuo

    1982-12-01

    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)

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

    International Nuclear Information System (INIS)

    Aldrich, L.R.

    1995-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Aldrich, L.R. [Commonwealth Edison Co., Downers Grove, IL (United States)

    1995-03-01

    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 Class{close_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.

  9. 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)

  10. Administración del agua. - Capítulo I: Marco jurídico conceptual de la gestión del agua.

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  11. El agua en América Latina

    Directory of Open Access Journals (Sweden)

    Ángel Wilfrido Yánez-Yánez

    2016-11-01

    Full Text Available El uso racional del agua en la actualidad constituye en uno de los mayores retos de la humanidad. En este sentido, el agua en América Latina llega a ser uno de los recursos esenciales para toda forma de vida. Según cálculos del Programa Ambiental de Naciones Unidas, la región cuenta con el 65% de agua dulce del mundo. Sin embargo, la relación entre la oferta y demanda de agua da lugar a situaciones muy complejas y distintas, dependiendo de cada país. La frecuente escasez del agua en la Región Andina, ocasionada por el cambio climático, las sequías prolongadas y, el aumento constante de la población humana, ocasionan, conflictos entre regiones, por el control y uso del agua. Por otra parte el 97.5 % del agua existente en el planeta es salada, mientras que un 2.5 % del recurso hídrico es apto para el consumo de los seres humanos y para el desarrollo de las actividades agropecuarias, sugiriendo el mejor aprovechamiento, para reducir los conflictos sociales derivados de los monopolios que controlan el recurso hídrico. Este hecho tendrá repercusiones económicas y geopolíticas en todo el mundo, aunque en América se verá involucrada por el contraste manifiesto que existe entre la zona septentrional, cada vez más sedienta y esquilmada de sus recursos hídricos, y el área meridional, donde el agua es abundante y todavía no ha sido debidamente aprovechada. En cualquier caso, se puede hablar con absoluta propiedad de la existencia de una disputa del agua entre el centro y la periferia, entre grupos antagónicos con intereses contrapuestos donde una vez más se generan desequilibrios y exclusiones socioeconómicas, culturales, políticas y ambientales. Se establece de hecho una pugna entre quienes piensan que el agua debe ser considerada un bien comercial y quienes sostienen que se trata de un bien social relacionado con el derecho a la vida. Ante ésta realidad se hace indispensable seguir trabajando en la conservación de los p

  12. 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)

  13. Advanced methods for BWR transient and stability analysis

    International Nuclear Information System (INIS)

    Schmidt, A.; Wehle, F.; Opel, S.; Velten, R.

    2008-01-01

    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)

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

    International Nuclear Information System (INIS)

    Yanagisawa, Kazuaki

    1992-03-01

    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)

  15. 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.

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

    International Nuclear Information System (INIS)

    Ortiz-Villafuerte, Javier; Castillo-Duran, Rogelio; Palacios-Hernandez, Javier C.

    2011-01-01

    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

  17. Estudio sanitario de los recursos hídricos: aguas residuales y aguas de consumo de la zona de Linares

    OpenAIRE

    Román Martínez, Isidoro

    2011-01-01

    Se ha realizado durante el periodo marzo-1987 a abril-1988 un estudio desde el punto de vista sanitario de 45 puntos de muestreo correspondientes a los municipios de Linares (20), Vilches (16), Jabalquinto (6), la Carolina (1), Santa Elena (1) y bailen (1). Las aguas fueron agrupadas por naturalezas. Resultando la distribuci??n siguiente: residuales (12), fluviales (16), aguas tratadas (10) y aguas profundas (7). De estas, se utilizaban para el consumo las correspondientes a 16 puntos. entre ...

  18. Analysis of multidimensional and countercurrent effects in a BWR loss-of-coolant accident

    International Nuclear Information System (INIS)

    Shiralkar, B.S.; Dix, G.E.; Alamgir, M.

    1991-01-01

    The presence of parallel enclosed channels in a boiling water reactor (BWR) provides opportunities for multiple flow regimes in cocurrent and countercurrent flow under loss-of-coolant accident (LOCA) conditions. To address and understand these phenomena, an integrated experimental and analytical study has been conducted. The primary experimental facility was the steam sector test facility (SSFT), which simulated a full scale 30deg sector of a BWR/6 reactor vessel. Both steady-state separate effects tests an integral transients with vessel vlowdown and refill were performed. The presence of multidimensional and parallel-channel effects was found to be very beneficial to BWR LOCA performance. The best estimate TRAC-BWR computer code was extended as part of this study by incorporation of a phenomenological upper plenum mixing model. TRAC-BWR was applied to the analysis of these full scale experiments. Excellent predictions of phenomena and experimental trends were achieved. (orig.)

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

    International Nuclear Information System (INIS)

    Powers, J.; Yonezawa, H.; Aoyagi, Y.; Kataoka, K.

    2015-09-01

    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)

  20. 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)

  1. Power oscillations in BWR reactors

    International Nuclear Information System (INIS)

    Espinosa P, G.

    2002-01-01

    One of the main problems in the operation of BWR type reactors is the instability in power that these could present. One type of oscillations and that is the objective of this work is the named density wave, which is attributed to the thermohydraulic processes that take place in the reactor core. From the beginnings of the development of BWR reactors, the stability of these has been an important aspect in their design, due to its possible consequences on the fuel integrity. The reactor core operates in two phase flow conditions and it is observed that under certain power and flow conditions, power instabilities appear. Studying this type of phenomena is complex, due to that a reactor core is constituted approximately by 27,000 fuel bars with different distributions of power and flow. The phenomena that cause the instability in BWR reactors continue being matter of scientific study. In the literature mainly in nuclear subject, it can be observed that exist different methods and approximations for studying this type of phenomena, nevertheless, their results are focused to establish safety limits in the reactor operation, instead of studying in depth of the knowledge about. Also in this line sense of the reactor data analysis, the oscillations characteristic frequencies are obtained for trying to establish if the power is growing or decreasing. In addition to that before mentioned in this paper it is presented a rigorous study applying the volumetric average method, for obtaining the vacuum waves propagation velocities and its possible connection with the power oscillations. (Author)

  2. Scaling and uncertainty in BWR instability problems

    International Nuclear Information System (INIS)

    Di Auria, F.; Pellicoro, V.

    1995-01-01

    This paper deals with a critical review of activities, performed at the DCMN of Pisa University, in relation to the thermo-hydraulic oscillations in two-phase systems. Stability analyses, including model development and achievement of experimental data, are generally performed for BWRs in order to achieve the following objectives: to reach a common understanding in relation to the predictive capabilities of system codes and to the influence of various parameters on the instability; to establish a data base for the qualification of the analytical tools already or becoming available; to set-up qualified tools (code/models + nodalization + user assumption) suitable for predicting the unstable behaviour of the nuclear plants of interest (current BWR, SBWR, ABWR and RBMK). These considerations have been the basis for the following researches: 1) proposal of the Boiling Instability Program (BIP) (1) 2) evaluation of stability tests in PIPER-ONE apparatus (2) 3) coupled thermal-hydraulic and neutronic instabilities in the LaSalle-2 BWR plant (3) 4) participation to the NEA-OECD BWR Benchmark (4) The RELAP/MOD2 and RELAP5/MOD3 codes have been used. (author)

  3. 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)

  4. Material operating behaviour of ABB BWR control rods

    International Nuclear Information System (INIS)

    Rebensdorff, B.; Bart, G.

    2000-01-01

    The BWR control rods made by ABB use boron carbide (B 4 C 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 B 4 C 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)

  5. General Electric's training program for BWR chemists

    International Nuclear Information System (INIS)

    Osborn, R.N.; Lim, W.

    1981-01-01

    This paper describes the development and implementation of the General Electric boiling water reactor chemistry training program from 1959 to the present. The original intention of this program was to provide practical hands on type training in radiochemistry to BWR chemistry supervisors with fossil station experience. This emphasis on radiochemistry has not changed through the years, but the training has expanded to include the high purity water chemistry of the BWR and has been modified to include new commission requirements, engineering developments and advanced instrumentation. Student and instructor qualifications are discussed and a description of the spin off courses for chemistry technicians and refresher training is presented

  6. BWR SFAT, gross-defect verification of spent BWR fuel. Final report on Task FIN A563 on the Finnish Support Programme to IAEA Safeguards including BWR SFAT User Manual

    International Nuclear Information System (INIS)

    Tarvainen, M.; Paakkunainen, M.; Tiitta, A.; Sarparanta, K.

    1994-04-01

    A measurement instrument called Spent Fuel Attribute Tester, SFAT, has been designed, fabricated and taken into use by the IAEA in gross defect verification of spent BWR fuel assemblies. The equipment consists of an underwater measurement head connected with cables to a control unit on the bridge of the fuel handling machine as well as to a PMCA for measurement of the gamma spectra. The BWR SFAT is optimized for the AFR interim storage, TVO KPA-STORE, of the TVO Power Company in Olkiluoto, Finland. It has a shape and it is moved like a fuel assembly using the fuel handling machine. No fuel movements are needed. Spent fuel specific radiation from the fission product 137 Cs at the gamma-ray energy of 662 keV is detected above the assemblies in the storage rack using a NaI(Tl) detector. In the design and in licensing the requirements of the IAEA, operator and the safety authority have been taken into account. The BWR SFAT allows modifications for other LWR fuel types with minor changes. The work has been carried out under the task FIN A 563 of the Finnish Support Programme to IAEA Safeguards. (orig.) (9 refs., 22 figs.)

  7. agua potable

    Directory of Open Access Journals (Sweden)

    John Fredy Rios

    2008-01-01

    Full Text Available Los sistemas de distribución pueden afectar la calidad del agua potable debido a las condiciones de la tubería y a la operación del sistema. Algunos parámetros son sensibles a la variación durante la distribución como: el cloro residual, pH, color y turbiedad, debido a que el material de la tubería puede presentar deterioro en estos sistemas a causa de la corrosividad del agua. Los diversos estudios realizados sobre el tema han empleado tanto sistemas reales como dispositivos de laboratorio para la realización de los ensayos. Entre los dispositivos más empleados actualmente, se reporta el uso del sistema piloto de distribución por las ventajas que ofrece y su flexibilidad en el diseño. Para definir las características de diseño de un sistema piloto de distribución se hizo una revisión de la literatura. El sistema se empleará en el estudio de la interacción entre el líquido y la pared de tubería. Se utilizarán materiales metálicos usados en sistemas de distribución secundarios, con el fin de determinar el ataque a la superficie interna de las tuberías y las causas de formación de depósitos sobre ellas, así como identificar los efectos de esta interacción en la calidad del agua.

  8. Reducing BWR O and M costs through on-line performance monitoring

    International Nuclear Information System (INIS)

    Jonas, T.; Gross, R.; Logback, F.; Josyula, R.

    1995-01-01

    Competition in the electric power industry has placed significant emphasis on reducing operating and maintenance (O and M) costs at nuclear facilities. Therefore, on-line performance monitoring to locate power losses for boiling water reactor (BWR) plants is creating tremendous interest. In addition, the ability to automate activities such as data collection, analysis, and reporting increases the efficiency of plant engineers and gives them more time to concentrate on solving plant efficiency problems. This capability is now available with a unique software product called GEBOPS. GE Nuclear Energy, in conjunction with Joint Venture partner Black and Veatch, has undertaken development of the General Electric/Black and Veatch On-line Performance System (GEBOPS), an on-line performance monitoring system for BWR plants. The experience and expertise of GE Nuclear Energy with BWR plants, coupled with the proven on-line monitoring software development experience and capability of Black and Veatch, provide the foundation for a unique product which addresses the needs of today's BWR plants

  9. Química recreativa con agua oxigenada

    Directory of Open Access Journals (Sweden)

    Mª Luisa Aguilar Muñoz

    2011-01-01

    Full Text Available Con el objeto de despertar el interés por la química así como de tratar diversos conceptos químicos y biológicos, presentamos la reacción de descomposición catalítica del agua oxigenada (H2O2 en tres experiencias diferentes y con distintos catalizadores. Esta reacción es muy exotérmica, produciendo agua y oxígeno. En la primera experiencia, se mezclan en una probeta la disolución de agua oxigenada y un poco de lavavajillas. Al añadir yoduro de potasio, éste actúa como catalizador y aparece gran cantidad de espuma debido al oxígeno desprendido en la reacción. En la segunda, se utiliza como catalizador un óxido de manganeso finamente dividido, que al dejarlo caer en el recipiente que contiene agua oxigenada, produce un espectacular chorro de vapor de agua. En la última, se produce una llamativa reacción luminiscente entre el peróxido de hidrógeno y el luminol utilizando como catalizador el ión hierro contenido en el hexacianoferrato (III de potasio (ferricianuro de potasio.

  10. Peach Bottom transient analysis with BWR TRACB02

    International Nuclear Information System (INIS)

    Alamgir, M.; Sutherland, W.A.

    1984-01-01

    TRAC calculations have been performed for a Turbine Trip transient (TT1) in the Peach Bottom BWR power plant. This study is a part of the qualification of the BWR-TRAC code. The simulation is aimed at reproducing the observed thermal hydraulic behavior in a pressurization transient. Measured core power is an input to the calculation. Comparison with data show the code reasonably well predicts the generation and propagation of the pressure waves in the main steam line and associated pressurization of the reactor vessel following the closure of the turbine stop valve

  11. Methyl Iodide Decomposition at BWR Conditions

    International Nuclear Information System (INIS)

    Pop, Mike; Bell, Merl

    2012-09-01

    Based on favourable results from short-term testing of methanol addition to an operating BWR plant, AREVA has performed numerous studies in support of necessary Engineering and Plant Safety Evaluations prior to extended injection of methanol. The current paper presents data from a study intended to provide further understanding of the decomposition of methyl iodide as it affects the assessment of methyl iodide formation with the application of methanol at BWR Plants. This paper describes the results of the decomposition testing under UV-C light at laboratory conditions and its effect on the subject methyl iodide production evaluation. The study as to the formation and decomposition of methyl iodide as it is effected by methanol addition is one phase of a larger AREVA effort to provide a generic plant Safety Evaluation prior to long-term methanol injection to an operating BWR. Other testing phases have investigated the compatibility of methanol with fuel construction materials, plant structural materials, plant consumable materials (i.e. elastomers and coatings), and ion exchange resins. Methyl iodide is known to be very unstable, typically preserved with copper metal or other stabilizing materials when produced and stored. It is even more unstable when exposed to light, heat, radiation, and water. Additionally, it is known that methyl iodide will decompose radiolytically, and that this effect may be simulated using ultra-violet radiation (UV-C) [2]. In the tests described in this paper, the use of a UV-C light source provides activation energy for the formation of methyl iodide. Thus is similar to the effect expected from Cherenkov radiation present in a reactor core after shutdown. Based on the testing described in this paper, it is concluded that injection of methanol at concentrations below 2.5 ppm in BWR applications to mitigate IGSCC of internals is inconsequential to the accident conditions postulated in the FSAR as they are related to methyl iodide formation

  12. TRAC-BWR development

    International Nuclear Information System (INIS)

    Weaver, W.L.; Rouhani, S.Z.

    1983-01-01

    The TRAC-BD1/MOD1 code containing many new or improved models has been assembled and is undergoing developmental assessment and testing and should be available shortly. The preparation of the manual for this code version is underway and should be available to the USNRC and their designated contractors by April of 1984. Finally work is currently underway on a fast running version of TRAC-BWR which will contain a one-dimensional neutron kinetics model

  13. Tratamiento del agua para consumo humano en el hogar

    OpenAIRE

    Instituto Nacional de Salud

    2008-01-01

    El agua es esencial para la vida y la accesibilidad del ser humano a ella le ha permitido asentarse, desarrollarse, recrearse y asegurar su supervivencia y salud. El uso cotidiano donde hombres, mujeres, niños y ancianos hacen uso de ésta, se relaciona con el acceso del agua para satisfacer necesidades básicas como el agua para bebida, higiene personal y alimentación. La privación del acceso del agua dulce ya sea en cantidades o calidades adecuadas pone en riesgo su salud y calidad de vida...

  14. BWR mechanics and materials technology update

    International Nuclear Information System (INIS)

    Kiss, E.

    1983-01-01

    This paper discusses technical results obtained from a variety of important programs underway at General Electric's Nuclear Engineering Division. The principal objective of these programs is to qualify and improve BWR product related technologies that fall broadly under the disciplines of Applied Mechanics and Materials Engineering. The paper identifies and deals with current technical issues that are of general importance to the LWR industry albeit the specific focus is directed to the development and qualification of analytical predictive methods and criteria, and improved materials for use in the design of the BWR. In this paper, specific results and accomplishments are summarized to provide a braod perspective of technology advances. Results are presented in sections which discuss: dynamic analysis and modeling; fatigue and fracture evaluation; materials engineering advances; and flow induced vibration. (orig.)

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

    Directory of Open Access Journals (Sweden)

    LY. Orozco

    2001-07-01

    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.

  16. Water chemistry control practices and data of the European BWR fleet

    International Nuclear Information System (INIS)

    Stellwag, B.; Laendner, A.; Weiss, S.; Huettner, F.

    2010-01-01

    Nineteen BWR plants are in operation in Europe, nine built by ASEA Atom, six by Siemens KWU and four by General Electric. This paper gives an overview of water chemistry operation practices and parameters of the European BWR plants. General design characteristics of the plants are described. Chemistry control strategies and underlying water chemistry guidelines are summarized. Chemistry data are presented and discussed with regard to plant design characteristics. The paper is based on a contract of the European BWR Forum with AREVA on a chemistry sourcebook for member plants. The survey of chemistry data was conducted for the years 2002 to 2008. (author)

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

    International Nuclear Information System (INIS)

    Smith, S.K.; Lehnert, D.F.; Locke, R.K.

    1991-01-01

    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)

  18. Simulation of decreasing reactor power level with BWR simulator

    International Nuclear Information System (INIS)

    Suwoto; Zuhair; Rivai, Abu Khalid

    2002-01-01

    Study on characteristic of BWR using Desktop PC Based Simulator Program was analysed. This simulator is more efficient and cheaper for analyzing of characteristic and dynamic respond than full scope simulator for decreasing power level of BW. Dynamic responses of BWR reactor was investigated during the power level reduction from 100% FP (Full Power) which is 3926 MWth to 0% FP with 25% steps and 1 % FP/sec rate. The overall results for core flow rate, reactor steam flow, feed-water flow and turbine-generator power show tendency proportional to reduction of reactor power. This results show that reactor power control in BWR could be done by control of re-circulation flow that alter the density of water used as coolant and moderator. Decreasing the re-circulation flow rate will decrease void density which has negative reactivity and also affect the position of control rods

  19. Metallurgical factors that contribute to cracking in BWR piping

    International Nuclear Information System (INIS)

    Weeks, J.R.

    1975-01-01

    During the fall of 1974 and early winter of 1975, cracks have been discovered in the 4 in. bypass lines of several Boiling Water Reactors (BWR's) in the United States. Further, similar cracks were discovered at two BWR's in Japan during the same period. More recently, cracks have been discovered in the core spray piping and in a furnace-sensitized ''safe end'' and adjacent ''dutchman'' at the Dresden Nuclear Power Station, Unit No. 2. Although inspections at all other U.S. BWR's have not disclosed further instances of cracking in core spray piping, leaking cracks have been found in the core spray piping of two BWR's overseas. Metallurgical examinations of these cracks are not yet complete. The following observations have been made to date. All cracks (except those in the furnace-sensitized safe end and dutchman) occurred in seamless type 304 stainless steel piping or in elbows fabricated from such piping, in the outer heat affected zone of either field or shop welds, in lines isolated from the main primary coolant flow during full power operation, except for the not yet examined cracks in the Monticello bypass lines. The cracks are exclusively intergranular, and occur in metal that has been lightly sensitized by the welding process, with only intermittent grain boundary carbides. They developed in the areas of peak axial residual stresses from welding rather than in the most heavily sensitized areas. No fatigue striations have been found on the fracture surfaces. The evidence received to date strongly indicates that these cracks were caused by intergranular stress corrosion of weld-sensitized stainless steel by BWR water containing greater than 0.2 ppM oxygen. The possible role of fatigue or alternating stresses in this corrosion is not clear. Further, not all the cracks detected to date necessarily have occurred by the same mechanism

  20. 22 de marzo: Día Internacional del Agua

    OpenAIRE

    Facultad de Ciencias Agrarias y Forestales

    2013-01-01

    Con la excusa del día internacional del agua, nos parece importante compartir con ustedes algunos conceptos importantes. ¿A qué se denomina agua potable? Agua potable es aquella que, bien en su estado natural o después de un tratamiento adecuado, es apta para el consumo humano y no produce ningún efecto perjudicial para la salud. Es limpia, transparente, sin olores o sabores desagradables y está libre de contaminantes.

  1. BWR chemistry control status: a summary of industry chemistry status relative to the BWR water chemistry guidelines

    International Nuclear Information System (INIS)

    Garcia, S.E.; Giannelli, J.F.; Jarvis, M.L.

    2010-01-01

    The EPRI Boiling Water Reactor (BWR) Water Chemistry Guidelines were revised and issued in October 2008. The 2008 Revision of the Guidelines continues to focus on intergranular stress corrosion cracking (IGSCC), which can limit the service life of susceptible materials and components exposed to water chemistry environments. The 2008 Revision also places increased emphasis on fuel performance and meeting the industry goal of zero fuel failures by 2010. As an industry consensus document, the Guidelines were created to provide proactive water chemistry control strategies for mitigating IGSCC, maintaining fuel integrity and controlling radiation fields. The Guidelines provide a technically-based framework for an effective BWR water chemistry program. This paper provides an overview of industry experience relative to the Guidelines. Over the past few years, many BWR units have implemented noble metal chemical application technologies either during plant hot or cold shutdown or at normal power operating conditions. This paper explores plant experience with optimized water chemistry, implementation of various additive chemistries such as noble metal application and zinc addition, and compliance with the Guidelines recommendations. Depleted zinc oxide addition has been broadly applied across the BWR fleet since the 1980s. The guidance for zinc addition has been revised in the Guidelines to reflect concerns with fuel performance. While zinc addition is a successful method for shutdown dose rate control, concerns still exist for high zinc deposition on fuel surfaces, especially when feedwater iron is elevated and as fuel cores are being driven to provide maximum power output over longer fuel cycles. Recent plant experience has shown that the utilization of online noble metal application and continued zinc addition may provide additional benefits for radiation control. Dose rate experiences at plants utilizing the online noble metal application technology and zinc addition

  2. BWR chemistry control status: a summary of industry chemistry status relative to the BWR water chemistry guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, S.E., E-mail: sgarcia@epri.com [Electric Power Research Inst. (EPRI), Palo Alto, California (United States); Giannelli, J.F.; Jarvis, M.L., E-mail: jgiannelli@finetech.com [Finetech, Inc., Parsippany, NJ (United States)

    2010-07-01

    The EPRI Boiling Water Reactor (BWR) Water Chemistry Guidelines were revised and issued in October 2008. The 2008 Revision of the Guidelines continues to focus on intergranular stress corrosion cracking (IGSCC), which can limit the service life of susceptible materials and components exposed to water chemistry environments. The 2008 Revision also places increased emphasis on fuel performance and meeting the industry goal of zero fuel failures by 2010. As an industry consensus document, the Guidelines were created to provide proactive water chemistry control strategies for mitigating IGSCC, maintaining fuel integrity and controlling radiation fields. The Guidelines provide a technically-based framework for an effective BWR water chemistry program. This paper provides an overview of industry experience relative to the Guidelines. Over the past few years, many BWR units have implemented noble metal chemical application technologies either during plant hot or cold shutdown or at normal power operating conditions. This paper explores plant experience with optimized water chemistry, implementation of various additive chemistries such as noble metal application and zinc addition, and compliance with the Guidelines recommendations. Depleted zinc oxide addition has been broadly applied across the BWR fleet since the 1980s. The guidance for zinc addition has been revised in the Guidelines to reflect concerns with fuel performance. While zinc addition is a successful method for shutdown dose rate control, concerns still exist for high zinc deposition on fuel surfaces, especially when feedwater iron is elevated and as fuel cores are being driven to provide maximum power output over longer fuel cycles. Recent plant experience has shown that the utilization of online noble metal application and continued zinc addition may provide additional benefits for radiation control. Dose rate experiences at plants utilizing the online noble metal application technology and zinc addition

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

    International Nuclear Information System (INIS)

    Ott, L.J.

    1997-01-01

    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 B 4 C-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

  4. sobre la calidad del agua de la ciénaga

    Directory of Open Access Journals (Sweden)

    Diego Alejandro Chalarca Rodríguez

    2007-01-01

    Full Text Available En el municipio de Ayapel, departamento de Córdoba, se realizaron cuatro muestreos de campo con el fin de obtener información representativa de las variaciones horarias del agua residual del municipio como también de la calidad del agua en la zona de influencia de éstas en la ciénaga de Ayapel. En el sector donde se presentan las principales descargas del alcantarillado se determinaron las variables fisicoquímicas y microbiológicas del agua residual doméstica y de la ciénaga. Ello con el fin de determinar el posible impacto de las aguas residuales domésticas sobre la calidad del agua de un sector de la ciénaga de Ayapel.Los resultados del estudio permiten afirmar que existe un impacto de las aguas residuales sobre el complejo cenagoso, sin embargo estas descargas afectan principalmente la calidad ambiental de los sitios aledaños al casco urbano del municipio de Ayapel, principalmente en las épocas de aguas bajas incluyendo la zona pelágica del sector E0.

  5. Analysis of multi-dimensional and countercurrent effects in a BWR loss-of-coolant accident

    International Nuclear Information System (INIS)

    Shiralkar, B.S.; Dix, G.E.; Alamgir, M.

    1989-01-01

    The presence of parallel enclosed channels in a BWR provides opportunities for multiple flow regimes in co-current and countercurrent flow under Loss-of-Coolant Accident (LOCA) conditions. To address and understand these phenomena, an integrated experimental and analytical study has been conducted. The primary experimental facility was the Steam Sector Test Facility (SSTF) which simulated a full scale 30deg sector of a BWR/6 reactor vessel. Both steady-state separate effects tests and integral transients with vessel blowdown and refill were performed. The present of multi-dimensional and parallel channel effects was found to be very beneficial to BWR LOCA performance. The best estimate TRAC-BWR computer code was extended as part of this study by incorporation of a phenomenological upper plenum mixing model. TRAC-BWR was applied to the analysis of these full scale experiments. Excellent predictions of phenomena and experimental trends were achieved. (orig.)

  6. 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.

  7. Assessment of two BWR accident management strategies

    International Nuclear Information System (INIS)

    Hodge, S.A.; Petek, M.

    1994-01-01

    Candidate mitigative strategies for the management of in-vessel events during the late phase (after-core degradation has occurred) of postulated boiling water reactor (BWR) severe accidents were considered at Oak Ridge National Laboratory (ORNL) during 1990. The identification of new strategies was subject to the constraint that they should, to the maximum extent possible, make use of the existing equipment and water resources of the BWR facilities, and not require major equipment modifications or additions. As a result of this effort, two of these candidate strategies were recommended for further assessment. The first was a strategy for containment flooding to maintain the core and structural debris within the reactor vessel in the event that vessel injection cannot be restored to terminate a severe accident sequence. The second strategy pertained to the opposite case, for which vessel injection would be restored after control blade melting had begun; its purpose was to provide an injection source of borated water at the concentration necessary to preclude criticality upon recovering a damaged BWR core. Assessments of these two strategies were performed during 1991 and this paper provides a discussion of the motivation for and purpose of these strategies, and the potential for their success. ((orig.))

  8. Aguas diversas. Derechos de agua y pluralidad legal en las comunidades andinas

    Directory of Open Access Journals (Sweden)

    Boelens, Rutgerd

    2009-12-01

    Full Text Available Water rights and property relations have become pivotal issues in water debates, reforms and intervention programs. Governments, development agencies and expert centers tend to consider ‘water rights’ as merely standard black boxes that juxtapose the frameworks of positivist technical and economist water science. But far beyond universal manuals and irrigation regulations, there is another water world, entrenched in the everyday lives of real people, male and female water users. The paper makes clear how Andean user collectives practice an enormous variety of water rights and management forms, as localnational- international hybrids that are created and affirmed in local water territories, embedded in historical and cultural-political contexts.

    Por el aumento generalizado de los conflictos por el agua, los derechos a este recurso se han vuelto ejes en los debates, reformas y programas de intervención hídrica. Los gobiernos, las agencias de desarrollo y los centros expertos tienden a considerar los ‘derechos de agua’ como meras cajas negras estándar que se yuxtaponen a los marcos de las ciencias técnicas y económicas positivistas. Pero mucho más allá de los manuales y las regulaciones de riego, hay otro mundo del agua íntimamente ligado a la vida diaria de gente real, hombres y mujeres que usan ese agua. Este artículo estudia cómo los colectivos de usuarios en la región andina practican una enorme variedad de derechos de agua y formas de gestión, como híbridos locales-nacionales-internacionales que se crean y afirman en los territorios hídricos locales, embebidos en contextos históricos y cultural-políticos.

  9. BWR plant dynamic analysis code BWRDYN user's manual

    International Nuclear Information System (INIS)

    Yokobayashi, Masao; Yoshida, Kazuo; Fujiki, Kazuo

    1989-06-01

    Computer code BWRDYN has been developed for thermal-hydraulic analysis of a BWR plant. It can analyze the various types of transient caused by not only small but also large disturbances such as operating mode changes and/or system malfunctions. The verification of main analytical models of the BWRDYN code has been performed with measured data of actual BWR plant. Furthermore, the installation of BOP (Balance of Plant) model has made it possible to analyze the effect of BOP on reactor system. This report describes on analytical models and instructions for user of the BWRDYN code. (author)

  10. Modern technology applied in the advanced BWR (ABWR)

    International Nuclear Information System (INIS)

    Hucik, S.A.

    1988-01-01

    The advanced boiling water reactor (ABWR) represents the next generation of light water reactors (LWR) to be introduced into commercial operation in the 1990's. The ABWR is the result of the continuing evolution of the BWR, incorporating state-of-the-art technology and improvements based on worldwide experience, and extensive design and test and development programs. This paper discusses how the ABWR development objective focused on an optimized selection of advanced technologies and proven BWR technologies. A technical evaluation of the ABWR shows its superiority in terms of performance characteristics and economics relative to current LWR designs

  11. BWR recirculation pump diagnostic expert system

    International Nuclear Information System (INIS)

    Chiang, S.C.; Morimoto, C.N.; Torres, M.R.

    2004-01-01

    At General Electric (GE), an on-line expert system to support maintenance decisions for BWR recirculation pumps for nuclear power plants has been developed. This diagnostic expert system is an interactive on-line system that furnishes diagnostic information concerning BWR recirculation pump operational problems. It effectively provides the recirculation pump diagnostic expertise in the plant control room continuously 24 hours a day. The expert system is interfaced to an on-line monitoring system, which uses existing plant sensors to acquire non-safety related data in real time. The expert system correlates and evaluates process data and vibration data by applying expert rules to determine the condition of a BWR recirculation pump system by applying knowledge based rules. Any diagnosis will be automatically displayed, indicating which pump may have a problem, the category of the problem, and the degree of concern expressed by the validity index and color hierarchy. The rules incorporate the expert knowledge from various technical sources such as plant experience, engineering principles, and published reports. These rules are installed in IF-THEN formats and the resulting truth values are also expressed in fuzzy terms and a certainty factor called a validity index. This GE Recirculation Pump Expert System uses industry-standard software, hardware, and network access to provide flexible interfaces with other possible data acquisition systems. Gensym G2 Real-Time Expert System is used for the expert shell and provides the graphical user interface, knowledge base, and inference engine capabilities. (author)

  12. Economic analysis of hydride fueled BWR

    International Nuclear Information System (INIS)

    Ganda, F.; Shuffler, C.; Greenspan, E.; Todreas, N.

    2009-01-01

    The economic implications of designing BWR cores with hydride fuels instead of conventional oxide fuels are analyzed. The economic analysis methodology adopted is based on the lifetime levelized cost of electricity (COE). Bracketing values (1970 and 3010 $/kWe) are used for the overnight construction costs and for the power scaling factors (0.4 and 0.8) that correlate between a change in the capital cost to a change in the power level. It is concluded that a newly constructed BWR reactor could substantially benefit from the use of 10 x 10 hydride fuel bundles instead of 10 x 10 oxide fuel bundles design presently in use. The cost saving would depend on the core pressure drop constraint that can be implemented in newly constructed BWRs - it is between 2% and 3% for a core pressure drop constraint as of the reference BWR, between 9% and 15% for a 50% higher core pressure drop, and between 12% and 21% higher for close to 100% core pressure. The attainable cost reduction was found insensitive to the specific construction cost but strongly dependent on the power scaling factor. The cost advantage of hydride fuelled cores as compared to that of the oxide reference core depends only weakly on the uranium and SWU prices, on the 'per volume base' fabrication cost of hydride fuels, and on the discount rate used. To be economically competitive, the uranium enrichment required for the hydride fuelled core needs to be around 10%.

  13. Analysis of a BWR direct cycle forced circulation power plants operation

    International Nuclear Information System (INIS)

    Andrade, G.G. de.

    1973-01-01

    First, it is established a general view over the operational problems of the BWR direct cycle forced circulation power plants, and then it is analysed the possibility of the utilization of the energy purged from the turbine as an additional energy for the electrical generation. To simulate the BWR power plant and to obtain the solution of the mathematical model it was developed a computer code named ATOR which shows the feasibility of the proposed method. In this way it is shown the possibility to get a better maneuvering allowance for the BWR power plant whenever it is permitted a convenient use of the vapor extracted from the turbine for the feedwater pre-heaters of the reactor. (author)

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

    International Nuclear Information System (INIS)

    Karlberg, G.; Goddard, C.; Fitzpatrick, S.

    1994-02-01

    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

  15. 22 de marzo: Día Internacional del Agua

    OpenAIRE

    Facultad de Ciencias Agrarias y Forestales

    2013-01-01

    Con la excusa del día internacional del agua, nos parece importante compartir con ustedes algunos conceptos importantes. ¿A qué se denomina agua potable? Agua potable es aquella que, bien en su estado natural o después de un tratamiento adecuado, es apta para el consumo humano y no produce ningún efecto perjudicial para la salud. Es limpia, transparente, sin olores o sabores desagradables y está libre de contaminantes. Facultad de Ciencias Agrarias y Forestales

  16. Development of the BWR Dry Core Initial and Boundary Conditions for the SNL XR2 Experiments; TOPICAL

    International Nuclear Information System (INIS)

    Ott, L.J.

    1994-01-01

    The objectives of the Boiling Water Reactor Experimental Analysis and Model Development for Severe Accidents (BEAMD) Program at the Oak Ridge National Laboratory (ORNL) are: (1) the development of a sound quantitative understanding of boiling water reactor (BWR) core melt progression; this includes control blade and channel box effects, metallic melt relocation and possible blockage formation under severe accident conditions, and (2) provision of BWR melt progression modeling capabilities in SCDAP/RELAP5 (consistent with the BWR experimental data base). This requires the assessment of current modeling of BWR core melt progression against the expanding BWR data base. Emphasis is placed upon data from the BWR tests in the German CORA test facility and from the ex-reactor experiments[Sandia National Laboratories (SNL)] on metallic melt relocation and blockage formation in BWRs, as well as upon in-reactor data from the Annular Core Research Reactor (ACRR) DF-4 BWR test (conducted in 1986 at SNL). The BEAMD Program is a derivative of the BWR Severe Accident Technology Programs at ORNL. The ORNL BWR programs have studied postulated severe accidents in BWRs and have developed a set of models specific to boiling water reactor response under severe accident conditions. These models, in an experiment-specific format, have been successfully applied to both pretest and posttest analyses of the DF-4 experiment, and the BWR severe fuel damage (SFD) experiments performed in the CORA facility at the Kernforschungszentrum Karlsruhe (KfK) in Germany, resulting in excellent agreement between model prediction and experiment. The ORNL BWR models have provided for more precise predictions of the conditions in the BWR experiments than were previously available. This has provided a basis for more accurate interpretation of the phenomena for which the experiments are performed. The experiment-specific models, as used in the ORNL DF-4 and CORA BWR experimental analyses, also provide a basis

  17. 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

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

    International Nuclear Information System (INIS)

    Powers, J.; Aoyagi, Y.; Kataoka, K.; Thomas, S.; Mookhoek, B.

    2015-09-01

    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

  19. 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

  20. 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.

  1. Maximum thermal loading test of BWR fuel assembly

    International Nuclear Information System (INIS)

    Nakajima, Yoshitaka; Yoshimura, Kunihiro; Nakamura, Satoshi; Ishizuka, Takao.

    1987-01-01

    Various proving tests on the reliability of nuclear power plants have been conducted at the Nuclear Power Engineering Test Center and at the Japan Power Plant Engineering and Inspection Corporation. The tests were initiated at the request of the Ministry of International Trade and Industry (MITI). Toshiba undertook one of the proving tests on the reliability of nuclear fuel assembly; the maximum thermal loading test of BWR fuel assembly from the Nuclear Power Engineering Test Center. These tests are part of the proving tests mentioned above, and their purpose is to confirm the reliability of the thermal hydraulic engineering techniques. Toshiba has been engaged for the past nine years in the design, fabrication and testing of the equipment. For the project, a test model fuel assembly was used to measure the critical power of the BWR fuel assembly and the void and fluidity of the coolant. From the test results, it has been confirmed that the heat is transferred safely from the fuel assembly to the coolant in the BWR nuclear power plant. In addition, the propriety and reliability of the thermal hydraulic engineering techniques for the fuel assembly have been proved. (author)

  2. Large bundle BWR test CORA-18: Test results

    International Nuclear Information System (INIS)

    Hagen, S.; Hofmann, P.; Noack, V.; Sepold, L.; Schanz, G.; Schumacher, G.

    1998-04-01

    The CORA out-of-pile experiments are part of the international Severe Fuel Damage (SFD) Program. They were performed to provide information on the damage progression of Light Water Reactor (LWR) fuel elements in Loss-of-coolant Accidents in the temperature range 1200 C to 2400 C. CORA-18 was the large BWR bundle test corresponding to the PWR test CORA-7. It should investigate if there exists an influence of the BWR bundle size on the fuel damage behaviour. Therefore, the standard-type BWR CORA bundle with 18 fuel rod simulators was replaced by a large bundle with two additional surrounding rows of 30 rods (48 rods total). Power input and steam flow were increased proportionally to the number of fuel rod simulators to give the same initial heat-up rate of about 1 K/s as in the smaller bundles. Emphasis was put on the initial phase of the damage progression. More information on the chemical composition of initial and intermediate interaction products and their relocation behaviour should be obtained. Therefore, power and steam input were terminated after the onset of the temperature escalation. (orig.) [de

  3. BWR shutdown analyzer using artificial intelligence (AI) techniques

    International Nuclear Information System (INIS)

    Cain, D.G.

    1986-01-01

    A prototype alarm system for detecting abnormal reactor shutdowns based on artificial intelligence technology is described. The system incorporates knowledge about Boiling Water Reactor (BWR) plant design and component behavior, as well as knowledge required to distinguish normal, abnormal, and ATWS accident conditions. The system was developed using a software tool environment for creating knowledge-based applications on a LISP machine. To facilitate prototype implementation and evaluation, a casual simulation of BWR shutdown sequences was developed and interfaced with the alarm system. An intelligent graphics interface for execution and control is described. System performance considerations and general observations relating to artificial intelligence application to nuclear power plant problems are provided

  4. TRATAMIENTO DE AGUAS RESIDUALES MEDIANTE IRRADIACIÓN GAMMA

    OpenAIRE

    Eduardo Campos Medina

    2009-01-01

    Esta investigación tiene por objetivo principal mostrar el efecto que tiene la aplicación de radiación gamma sobre los contaminantes orgánicos disueltos en aguas residuales industriales. En el proceso de investigación se emplearon porciones de agua residual de la empresa tratadora Reciclagua, estas muestras de agua mostraron elevados valores en cuanto a la Demanda Química de Oxígeno (DQO), posteriormente se aplicaron diferentes dosis de radiación gamma, buscando con ello la fragmentación de l...

  5. BWR condensate filtration studies

    International Nuclear Information System (INIS)

    Wilson, J.A.; Pasricha, A.; Rekart, T.E.

    1993-09-01

    Poor removal of particulate corrosion products (especially iron) from condensate is one of the major problems in BWR systems. The presence of activated corrosion products creates ''hot spots'' and increases piping dose rates. Also, fuel efficiency is reduced and the risk of fuel failure is increased by the deposit of corrosion products on the fuel. Because of these concerns, current EPRI guidelines call for a maximum of 2 ppb of iron in the reactor feedwater with a level of 0.5 ppb being especially desirable. It has become clear that conventional deep bed resins are incapable of meeting these levels. While installation of prefilter systems is an option, it would be more economical for plants with naked deep beds to find an improved bead resin for use in existing systems. BWR condensate filtration technologies are being tested on a condensate side stream at Hope Creek Nuclear Generating Station. After two years of testing, hollow fiber filters (HFF) and fiber matrix filters (FMF), and low crosslink cation resin, all provide acceptable results. The results are presented for pressure drop, filtration efficiency, and water quality measurements. The costs are compared for backwashable non-precoat HFF and FMF. Results are also presented for full deep bed vessel tests of the low crosslink cation resin

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

    International Nuclear Information System (INIS)

    Takahashi, Shiro; Okuyama, Keita; Tamura, Akinori

    2009-01-01

    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)

  7. Los microbios en el agua de las unidades dentales

    Directory of Open Access Journals (Sweden)

    Chris H. Milleri

    1996-12-01

    Full Text Available Los microbios están presentes en el agua de las unidades dentales y existen en la biocapa que cubre las paredes de las tuberías de agua. El mejoramiento de la calidad microbiana del agua en las unidades dentales según estén disponibles los medios es una parte natural del mantenimiento de la calidad para la atención al paciente y al equipo de trabajo.

  8. Agua potable y saneamiento en la Argentina

    OpenAIRE

    Auge, Miguel

    2007-01-01

    Este trabajo fue presentado originalmente en el Foro Regional del Agua, con el título “Problemática del Acceso al Agua Potable y al Saneamiento en Argentina”. Dicho foro, organizado por la Defensoría del Pueblo de la Nación Argentina, se desarrolló en Córdoba, en mayo del 2007.

  9. The BWR vessel and internals project - 2001 and beyond

    International Nuclear Information System (INIS)

    Wagoner, V.; Mulford, T.

    2001-01-01

    The BWR Vessel and Internals Project (BWRVIP) is an international association of utilities owning boiling water reactors (BWRs). Figure 1 contains a list of current BWRVIP member utilities. The association was formed in 1994 with the following objectives: to lead the BWR industry toward generic resolution of reactor pressure vessel and internals material condition issues; to identify or develop generic, cost-effective strategies from which each operating plant will select the most appropriate alternative; to serve as the focal point for the regulatory interface with the industry on BWR vessel and internals issues; and to share information and promote communication and cooperation among participating utilities. The initial issue faced by the BWRVIP was core shroud cracking that had been observed in a number of BWRs. The BWRVIP reacted by quickly developing a set of industry guidelines to assist utilities in inspecting, evaluating, and, if necessary, repairing cracked shrouds. Subsequently, the BWRVIP pro-actively developed a comprehensive set of guidelines for managing degradation in other reactor internal components, including the reactor pressure vessel itself. The major components addressed by the BWRVIP are included. (author)

  10. The BWR vessel and internals project - 2001 and beyond

    Energy Technology Data Exchange (ETDEWEB)

    Wagoner, V. [Carolina Power and Light, Progress Energy Building, NC (United States); Mulford, T. [Electric Power Research Institute, Palo Alto, CA (United States)

    2001-07-01

    The BWR Vessel and Internals Project (BWRVIP) is an international association of utilities owning boiling water reactors (BWRs). Figure 1 contains a list of current BWRVIP member utilities. The association was formed in 1994 with the following objectives: to lead the BWR industry toward generic resolution of reactor pressure vessel and internals material condition issues; to identify or develop generic, cost-effective strategies from which each operating plant will select the most appropriate alternative; to serve as the focal point for the regulatory interface with the industry on BWR vessel and internals issues; and to share information and promote communication and cooperation among participating utilities. The initial issue faced by the BWRVIP was core shroud cracking that had been observed in a number of BWRs. The BWRVIP reacted by quickly developing a set of industry guidelines to assist utilities in inspecting, evaluating, and, if necessary, repairing cracked shrouds. Subsequently, the BWRVIP pro-actively developed a comprehensive set of guidelines for managing degradation in other reactor internal components, including the reactor pressure vessel itself. The major components addressed by the BWRVIP are included. (author)

  11. Advanced chemistry management system to optimize BWR chemistry control

    International Nuclear Information System (INIS)

    Maeda, K.; Nagasawa, K.

    2002-01-01

    BWR plant chemistry control has close relationships among nuclear safety, component reliability, radiation field management and fuel integrity. Advanced technology is required to improve chemistry control [1,3,6,7,10,11]. Toshiba has developed TACMAN (Toshiba Advanced Chemistry Management system) to support BWR chemistry control. The TACMAN has been developed as response to utilities' years of requirements to keep plant operation safety, reliability and cost benefit. The advanced technology built into the TACMAN allows utilities to make efficient chemistry control and to keep cost benefit. TACMAN is currently being used in response to the needs for tools those plant chemists and engineers could use to optimize and identify plant chemistry conditions continuously. If an incipient condition or anomaly is detected at early stage, root causes evaluation and immediate countermeasures can be provided. Especially, the expert system brings numerous and competitive advantages not only to improve plant chemistry reliability but also to standardize and systematize know-how, empirical knowledge and technologies in BWR chemistry This paper shows detail functions of TACMAN and practical results to evaluate actual plant. (authors)

  12. Crud deposition modeling on BWR fuel rods

    International Nuclear Information System (INIS)

    Kucuk, Aylin; Cheng, Bo; Potts, Gerald A.; Shiralkar, Bharat; Morgan, Dave; Epperson, Kenny; Gose, Garry

    2014-01-01

    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)

  13. 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...

  14. Aguas contemporáneas

    Directory of Open Access Journals (Sweden)

    Underlea Bruscato Portella

    2007-10-01

    Full Text Available El agua parece un material esquivo para la arquitectura. Propio del mundo natural, fluido y cambiante, distante de la estabilidad perenne de los edificios, que la eluden con sus gruesos muros y amplias techumbres. Sin embargo, algunas construcciones han logrado una emotiva amalgama con el devenir del agua, como los jardines de la Alhambra en Granada. Quizás por provenir de una cultura que apreciaba la escasez del recurso líquido y su frescor en la vida diaria. Estanques, fuentes, canales, regaderas, se combinan con el aroma de los naranjos, el delicado aderezado de las columnas y arcos, la sombra de los salones, la vista enmarcada de las sierras, el lujo de la corte, el placer de los sentidos.

  15. ¿Agua dividida, agua compartida? Acuiferos transfronterizos en Sudamérica, una aproximación

    Directory of Open Access Journals (Sweden)

    Carmen Maganda

    2008-01-01

    Full Text Available Este artículo aborda la política fronteriza del agua en Sudamérica, con una discusión específica sobre la frontera Colombia-Venezuela. Con una perspectiva comparativa, la autora aborda el impacto de los procesos políticos en la distribución y acceso al agua en regiones fronterizas. La autora señala que la internacionalización del manejo del agua en zonas fronterizas debilita la participación pública debido al limitado conocimiento de la agenda ambiental de los macro esfuerzos regionales como la Comunidad Andina y sus instituciones. Los ríos o acuíferos compartidos son recursos «invisibles» para el común de los ciudadanos en Sudamérica, que pueden convertirse en fuente potencial de conflictos o de cooperación e integración regional. La cooperación es definitivamente necesaria en estos casos. Pocos esfuerzos se han registrado recientemente en Latinoamérica. Entre estos, destaca el programa Acuíferos Transfronterizos de las Américas (ISARM en Inglés, creado en 2002 por la UNESCO. Es particularmente importante poner atención en la falta de acuerdos trasnacionales sobre acuíferos transfronterizos en Sudamérica para compartir responsabilidades y toma de decisiones sobre el manejo de estas aguas. La autora señala el caso particular del acuífero transfronterizo Cúcuta-San Antonio sin un aparente manejo binacional entre Colombia y Venezuela.

  16. ¿Agua dividida, agua compartida? Acuiferos transfronterizos en Sudamérica, una aproximación

    Directory of Open Access Journals (Sweden)

    Carmen Maganda

    Full Text Available Este artículo aborda la política fronteriza del agua en Sudamérica, con una discusión específica sobre la frontera Colombia-Venezuela. Con una perspectiva comparativa, la autora aborda el impacto de los procesos políticos en la distribución y acceso al agua en regiones fronterizas. La autora señala que la internacionalización del manejo del agua en zonas fronterizas debilita la participación pública debido al limitado conocimiento de la agenda ambiental de los macro esfuerzos regionales como la Comunidad Andina y sus instituciones. Los ríos o acuíferos compartidos son recursos ''invisibles'' para el común de los ciudadanos en Sudamérica, que pueden convertirse en fuente potencial de conflictos o de cooperación e integración regional. La cooperación es definitivamente necesaria en estos casos. Pocos esfuerzos se han registrado recientemente en Latinoamérica. Entre estos, destaca el programa Acuíferos Transfronterizos de las Américas (ISARM en Inglés, creado en 2002 por la UNESCO. Es particularmente importante poner atención en la falta de acuerdos trasnacionales sobre acuíferos transfronterizos en Sudamérica para compartir responsabilidades y toma de decisiones sobre el manejo de estas aguas. La autora señala el caso particular del acuífero transfronterizo Cúcuta-San Antonio sin un aparente manejo binacional entre Colombia y Venezuela.

  17. Administración del agua. - Capítulo IX: Protección del dominio público hidráulico y de la calidad de las aguas

    OpenAIRE

    Fernández Morales, Juan Carlos

    2008-01-01

    ÍNDICE Créditos Dedicatoria Agradecimiento Notas del autor Introducción Capítulo I: Marco jurídico conceptual de la gestión del agua. Capítulo II: Organización administrativa del agua. Capítulo III: Las confederaciones hidrográficas en la legislación española. Capítulo IV: Los usuarios y la gestión del agua. Capítulo V: Administración del agua y competencias sectoriales en las comunidades autonómas españolas. Capítulo VI: Abastecimien...

  18. Secondary systems of PWR and BWR

    International Nuclear Information System (INIS)

    Schindler, N.

    1981-01-01

    The secondary systems of a nuclear power plant comprises the steam, condensate and feedwater cycle, the steam plant auxiliary or ancillary systems and the cooling water systems. The presentation gives a general review about the main systems which show a high similarity of PWR and BWR plants. (orig./RW)

  19. Development and recent trend of design of BWR nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kani, J [Tokyo Shibaura Electric Co. Ltd., Kawasaki, Kanagawa (Japan)

    1977-11-01

    Many improvements have been carried out in BWR nuclear power plants from BWR-1, represented by Dresden No. 1 plant, to the present BWR-6 as the capacity has increased. In Japan, the plants up to BWR-5 have been constructed. In addition, further fine design improvements are being performed in the complete domestic manufacturing of BRWs based on the operational experiences to date. A variety of investigations on the standardization of nuclear power facilities have been progressing under the leadership of Japanese Ministry of International Trade and Industry since 1975. In this standardization, it is intended to forward the plant design taking eight concrete items into consideration, mainly aiming at carrying cut unerringly the maintenance and inspection, reduction of exposure of employees to radiation, and improvements of the rate of operation of plants and equipment reliability. The containment vessel has been developed in three forms, from Mark 1 through 3, adopting the pressure control system consistently since BWR-2. Mark 1 and 2 were constructed in Japan. However, these designs sacrificed the workability and increased radiation exposure during maintenance as a result of placing emphasis on the safety facilities, therefore Toshiba Electric has investigated the advanced Mark 1 type. Its features are the design for improving the work efficiency in a containment vessel, reducing the radiation exposure of workers, shortening plant construction period, and considering the aseismatic capability. In addition, the following themes are being planned as future standardization: (1) electrically driven control rod driving system, (2) improved design of reactor core, and (3) internal pump system as compared with external re-circulation.

  20. Development and recent trend of disign of BWR nuclear power plants

    International Nuclear Information System (INIS)

    Kani, Jiro

    1977-01-01

    Many improvements have been carried out in BWR nuclear power plants from BWR-1, represented by Dresden No. 1 plant, to the present BWR-6 as the capacity has increased. In Japan, the plants up to BWR-5 have been constructed. In addition, further fine design improvements are being performed in the complete domestic manufacturing of BRWs based on the operational experiences to date. A variety of investigations on the standardization of nuclear power facilities have been progressing under the leadership of Japanese Ministry of International Trade and Industry since 1975. In this standardization, it is intended to forward the plant design taking eight concrete items into consideration, mainly aiming at carrying cut unerringly the maintenance and inspection, reduction of exposure of employees to radiation, and improvements of the rate of operation of plants and equipment reliability. The containment vessel has been developed in three forms, from Mark 1 through 3, adopting the pressure control system consistently since BWR-2. Mark 1 and 2 were constructed in Japan. However, these designs sacrificed the workability and increased radiation exposure during maintenance as a result of placing emphasis on the safety facilities, therefore Toshiba Electric has investigated the advanced Mark 1 type. Its features are the design for improving the work efficiency in a containment vessel, reducing the radiation exposure of workers, shortening plant construction period, and considering the aseismatic capability. In addition, the following themes are being planned as future standardization: (1) electrically driven control rod driving system, (2) improved design of reactor core, and (3) internal pump system as compared with external re-circulation. (Wakatsuki, Y.)

  1. 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.

  2. Identification and assessment of BWR in-vessel severe accident mitigation strategies

    International Nuclear Information System (INIS)

    Hodge, S.A.; Kress, T.S.; Cleveland, J.C.; Petek, M.

    1992-01-01

    This paper briefly describes the results of work carried out in support of the US Nuclear Regulatory Commission Accident Management Research Program to evaluate the effectiveness and feasibility of current and proposed strategies for BWR severe accident management. These results are described in detail in the just-released report Identification and Assessment of BWR In-Vessel Severe Accident Mitigation Strategies, NUREG/CR-5869, which comprises three categories of findings. First, an assessment of the current status of accident management strategies for the mitigation of in-vessel events for BWR severe accident sequences is combined with a review of the BWR Owners' Group Emergency Procedure Guidelines (EPGs) to determine the extent to which they currently address the characteristic events of an unmitigated severe accident. Second, where considered necessary, new candidate accident management strategies are proposed for mitigation of the late-phase (after core damage has occurred) events. Finally, two of the four candidate strategies identified by this effort are assessed in detail. These are (1) preparation of a boron solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and (2) containment flooding to maintain the core debris within the reactor vessel if the injection systems cannot be restored

  3. BWR level estimation using Kalman Filtering approach

    International Nuclear Information System (INIS)

    Garner, G.; Divakaruni, S.M.; Meyer, J.E.

    1986-01-01

    Work is in progress on development of a system for Boiling Water Reactor (BWR) vessel level validation and failure detection. The levels validated include the liquid level both inside and outside the core shroud. This work is a major part of a larger effort to develop a complete system for BWR signal validation. The demonstration plant is the Oyster Creek BWR. Liquid level inside the core shroud is not directly measured during full power operation. This level must be validated using measurements of other quantities and analytic models. Given the available sensors, analytic models for level that are based on mass and energy balances can contain open integrators. When such a model is driven by noisy measurements, the model predicted level will deviate from the true level over time. To validate the level properly and to avoid false alarms, the open integrator must be stabilized. In addition, plant parameters will change slowly with time. The respective model must either account for these plant changes or be insensitive to them to avoid false alarms and maintain sensitivity to true failures of level instrumentation. Problems are addressed here by combining the extended Kalman Filter and Parity Space Decision/Estimator. The open integrator is stabilized by integrating from the validated estimate at the beginning of each sampling interval, rather than from the model predicted value. The model is adapted to slow plant/sensor changes by updating model parameters on-line

  4. Investigation of BWR stability in Forsmark 2

    International Nuclear Information System (INIS)

    Oguma, R.; Reisch, F.; Bergdahl, B.G.; Lorenzen, J.; Aakerhielm, F.; Kellner, S.

    1988-01-01

    A series of noise measurements have been conducted at the Forsmark-2 reactor during its start-up operation after the revision in 1987. The main purpose was to investigate the BWR stability problem based on noise analysis, i.e. the problem of resonant power oscillation with frequency of about 0.5 Hz, which tends to arise at high power and low core flow condition. The noise analysis was performed to estimate the noise source which gives rise to the power oscillation, to evaluate the stability condition of the Forsmark-2 reactor in terms of the decay ratio (DR), as well as to investigate a safety related problem in connection with the BWR stability. The results indicate that the power oscillation is due to dynamic coupling between the neutron kinetics and thermal-hydraulics via void reactivity feedback. The DR reached as high as ≅ 0.7 at 63% of the rated power and 4100 kg/s of the total core flow. An investigation was made for the noise recording which represents a strong pressure oscillation with a peak frequency at 0.33 Hz. The result suggests that such pressure oscillation, if the peak frequency coincided with that of the resonant power oscillation, might become a cause of scram. The present noise analysis indicates the importance of a BWR on-line surveillance system with functions like stability condition monitoring and control system diagnosis. (orig.)

  5. 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.

  6. 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.

  7. Corrosion issues in the BWR and their mitigation for plant life extension

    International Nuclear Information System (INIS)

    Gordon, B.M.

    1988-01-01

    Corrosion is a major service life limiting mechanism for both pressurized water reactors (PWRs) and boiling water reactors (BWRs). For the BWR, stress corrosion cracking of piping has been the major source of concern where extensive research has led to a number of qualified remedies and currently > 90% of susceptible welds have been mitigated or replaced. Stress corrosion cracking of reactor internals due to the interaction of irradiation, as discussed elsewhere in this conference, is also a possible life limiting phenomenon. This paper focusses on two corrosion phenomena in the BWR which have only recently been identified as impacting the universal goal of BWR life extension: the general corrosion of containment structures and the erosion-corrosion of carbon steel piping

  8. 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).

  9. LAPUR5 BWR stability analysis in Kuosheng nuclear power plant

    International Nuclear Information System (INIS)

    Kunlung Wu; Chunkuan Shih; Wang, J.R.; Kao, L.S.

    2005-01-01

    Full text of publication follows: Unstable oscillation of a nuclear power reactor core is one of the main reasons that causes minor core damage. Stability analysis needs to be performed to predict the potential problem as early as possible and to prevent core instability events from happening. Nuclear Regulatory Commission (NRC) requests all BWR licensees to examine each core reload and to impose operating limitations, as appropriate, to ensure compliance with GDC 10 and 12. GDC 10 requires that the reactor core be designed with appropriate margin to assure that specified acceptable fuel design limits will not be exceeded during any condition of normal operation, including anticipated operational occurrences. GDC 12 requires assurance that power oscillations which can result in conditions exceeding specified acceptable fuel design limits are either not possible or can be reliably and readily detected and suppressed. Therefore, the core instability is directly related to the fuel design limits. The core and channel DR (decay ratio) calculation are commonly performed to determine system's stability when new fuel designs are introduced in the core. In order to establish the independent analysis technology for BWR licensees and verifications, the Institute of Nuclear Energy Research (INER) has obtained agreement from NRC and implemented the 'Methodology and Procedure for Calculation of Core and Channel Decay Ratios with LAPUR', which was developed by the IBERINCO in 2001. LAPUR5 uses a multi-nodal description of the neutron dynamics, together with a distributed parameter model of the core thermal hydrodynamics to produce a space-dependent representation of the dynamics of a BWR in the frequency domain for small perturbations around a steady state condition. From the output of LAPUR5, the following results are obtained: global core decay ratio, out-of phase core decay ratio, and channel decay ratio. They are key parameters in the determination of BWR core stability

  10. Sistema de agua entubada de Cambugán

    OpenAIRE

    Mayorga, O.H.

    2004-01-01

    Los usos principales del agua de Cambugán son lavar ropa y actividades domésticas. Quienes acceden a otro sistema de mejor calidad usan el agua para beber. Hay problemas de sedimentos, mal sabor y olor. Da recomendaciones para educación y otros estudios específicos.

  11. 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...

  12. Eliminación del arsénico en diferentes clases de aguas con zeolitas naturales

    OpenAIRE

    Lazo Camposano, Roberto

    2013-01-01

    Para el desarrollo del presente trabajo de Investigación se ha tenido Ia referencia sobre todo de las contaminaciones de las diferentes aguas sea este de origen natural, aguas subterráneas, aguas de rio, aguas procedentes de Iluvias, aguas de filtraciones, aguas de minas, etc, es decir toda clase de agua que contenga el arsénico que es perjudicial a la salud humana. En el presente trabajo se utilizará un medio adsorbente que consiste de zeolita natural (clinoptilolita) recubierta con óxido...

  13. Minería del agua

    OpenAIRE

    Reynolds Vargas, Jenny

    2016-01-01

    En Costa Rica el recurso hídrico se ve amenazado ante una explotación sin control en actividades que implican la extracción o minería del agua, es decir, la fuente es empleada hasta que se agota, cuando ya es inútil para consumo, irrigación o recreación. Se señala en este artículo el agravamiento del problema por la falta de mecanismos de protección que promuevan un uso sotenible del agua y se brindan algunas recomendaciones en pro de mejorar la calidad del recurso.

  14. Advances in BWR water chemistry

    International Nuclear Information System (INIS)

    Garcia, Susan E.; Giannelli, Joseph F.; Jarvis, Mary L.

    2012-09-01

    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

  15. Derecho humano al agua y principio de unidad de gestión

    Directory of Open Access Journals (Sweden)

    Alma Patricia Domínguez Alonso

    2014-04-01

    Full Text Available El trabajo analiza el reciente reconocimiento a nivel internacional delDerecho humano al agua, que ha abierto una nueva perspectiva desdela que abordar el uso y gestión de este decisivo recurso para la vidaen el planeta. Un agua potable limpia y el saneamiento son esencialespara la realización de todos los derechos humanos. En este sentido,revista mucha importancia el principio de unidad de gestión de lasaguas, que supone que las aguas de una misma cuenca -en cuantoforman un conjunto integrado- sean gestionadas de forma homogénea.El objetivo de un buen estado de las aguas debe perseguirse en cadacuenca hidrográfica, de modo que se coordinen las medidas relativasa las aguas superficiales y las aguas subterráneas pertenecientes almismo sistema ecológico, hidrológico e hidrogeológico.

  16. Seismic proving test of BWR primary loop recirculation system

    International Nuclear Information System (INIS)

    Sato, H.; Shigeta, M.; Karasawa, Y.

    1987-01-01

    The seismic proving test of BWR Primary Loop Recirculation system is the second test to use the large-scale, high-performance vibration table of Tadotsu Engineering Laboratory. The purpose of this test is to prove the seismic reliability of the primary loop recirculation system (PLR), one of the most important safety components in the BWR nuclear plants, and also to confirm the adequacy of seismic analysis method used in the current seismic design. To achieve the purpose, the test was conducted under conditions and scale as near as possible to actual systems. The strength proving test was carried out with the test model mounted on the vibration table in consideration of basic design earthquake ground motions and other conditions to confirm the soundness of structure and the strength against earthquakes. Detailed analysis and analytic evaluation of the data obtained from the test was conducted to confirm the adequacy of the seismic analysis method and earthquake response analysis method used in the current seismic design. Then, on the basis of the results obtained, the seismic safety and reliability of BWR primary loop recirculation of the actual plants was fully evaluated

  17. Complete BWR--EM LOCA analysis using the WRAP--EM system

    International Nuclear Information System (INIS)

    Beckmeyer, R.R.; Gregory, M.V.; Buckner, M.R.

    1979-01-01

    The Water Reactor Analysis Package, Evaluation Model (WRAP--EM), provides a complete analysis of postulated loss-of-coolant accidents (LOCA's) in light--water nuclear power reactors. The system is being developed at the Savannah River Laboratory (SRL) for use by the Nuclear Regulatory Commission (NRC) to interpret and evaluate reactor vendor, evaluation model (EM) analyses. The initial version of the WRAP--EM system for analysis of boiling water reactors (BWR's) is operational. To demonstrate the complete capability of the WRAP--BWR--EM system, a LOCA analysis has been performed for the Hope Creek Plant

  18. Computational fluid dynamics modeling of two-phase flow in a BWR fuel assembly

    International Nuclear Information System (INIS)

    Andrey Ioilev; Maskhud Samigulin; Vasily Ustinenko; Simon Lo; Adrian Tentner

    2005-01-01

    Full text of publication follows: The goal of this project is to develop an advanced Computational Fluid Dynamics (CFD) computer code (CFD-BWR) that allows the detailed analysis of the two-phase flow and heat transfer phenomena in a Boiling Water Reactor (BWR) fuel bundle under various operating conditions. This code will include more fundamental physical models than the current generation of sub-channel codes and advanced numerical algorithms for improved computational accuracy, robustness, and speed. It is highly desirable to understand the detailed two-phase flow phenomena inside a BWR fuel bundle. These phenomena include coolant phase changes and multiple flow regimes which directly influence the coolant interaction with fuel assembly and, ultimately, the reactor performance. Traditionally, the best analysis tools for the analysis of two-phase flow phenomena inside the BWR fuel assembly have been the sub-channel codes. However, the resolution of these codes is still too coarse for analyzing the detailed intra-assembly flow patterns, such as flow around a spacer element. Recent progress in Computational Fluid Dynamics (CFD), coupled with the rapidly increasing computational power of massively parallel computers, shows promising potential for the fine-mesh, detailed simulation of fuel assembly two-phase flow phenomena. However, the phenomenological models available in the commercial CFD programs are not as advanced as those currently being used in the sub-channel codes used in the nuclear industry. In particular, there are no models currently available which are able to reliably predict the nature of the flow regimes, and use the appropriate sub-models for those flow regimes. The CFD-BWR code is being developed as a customized module built on the foundation of the commercial CFD Code STAR-CD which provides general two-phase flow modeling capabilities. The paper describes the model development strategy which has been adopted by the development team for the

  19. IMPACTO AMBIENTAL DE LOS CONTAMINANTES PROVENIENTES DE AGUAS RESIDUALES DE FEED-LOT SOBRE AGUAS SUBTERRÁNEAS

    Directory of Open Access Journals (Sweden)

    Walter M. Glessi

    2012-01-01

    Full Text Available En este trabajo se investigó el impacto de los contaminantes de efluentes líquidos generados por doce feedlot del sudeste de la Provincia de Buenos Aires, Argentina, con el objeto de determinar los aspectos significativos sobre la vulnerabilidad de las aguas subterráneas. Se utilizó la Guía metodológica de Evaluación de Impacto Ambiental propuesta por Conesa (2010 partiendo de do ce Estudios de Impacto Ambiental y analizando como influye la actividad sobre el agua subterránea. Se analizó la dimensión de los establecimientos partiendo del número de animales, el tipo de suelo, profundidad freática y tipo de práctica (estacional o continua, así como las doce matrices de impacto en la emisión de contaminantes sobre el medio físico agua. Se obtuvo que los parámetros de mayor incidencia son: el grado de Destrucción, el área de influencia, el momento de manifestación del efecto y la regularidad de la manifestación.

  20. Limerick BWR turbine control and protection system upgrade success

    International Nuclear Information System (INIS)

    Tang, C.K.; Pietryka, T.S.; Federico, P.A.; Williams, J.C.

    2015-01-01

    Westinghouse and Exelon have successfully implemented a digital electro-hydraulic control (DEHC) at Limerick BWR Unit 1 Station to perform the turbine control, protection and reactor pressure functions. The DEHC replaces analog controls and addressed system performance, obsolescence and reliability. This was a first-of-a-kind application for control and protection of the main turbine and BWR pressure control for the distributed control system utilized. The demolition of analog equipment, main control room and front standard modifications, and acceptance testing were completed on schedule during the normal 2014 outage. Key aspects of the project that facilitated this success will be discussed and presented. (author)

  1. Limerick BWR turbine control and protection system upgrade success

    Energy Technology Data Exchange (ETDEWEB)

    Tang, C.K.; Pietryka, T.S.; Federico, P.A., E-mail: tangck@westinghouse.com, E-mail: pietryt@westinghouse, E-mail: federipa@westinghouse.com [Westinghouse Electric Company, LLC, Cranberry Township, PA (United States); Williams, J.C., E-mail: Jonathan.Williams@exeloncorp.com [Exelon Nuclear, Warrenville, IL (United States)

    2015-07-01

    Westinghouse and Exelon have successfully implemented a digital electro-hydraulic control (DEHC) at Limerick BWR Unit 1 Station to perform the turbine control, protection and reactor pressure functions. The DEHC replaces analog controls and addressed system performance, obsolescence and reliability. This was a first-of-a-kind application for control and protection of the main turbine and BWR pressure control for the distributed control system utilized. The demolition of analog equipment, main control room and front standard modifications, and acceptance testing were completed on schedule during the normal 2014 outage. Key aspects of the project that facilitated this success will be discussed and presented. (author)

  2. 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.

  3. Tritium in liquid phase in a BWR-5 like Laguna Verde

    International Nuclear Information System (INIS)

    Tijerina S, F.; Vargas A, A.; Cardenas J, J.

    2011-11-01

    In boiling water reactors (BWR), the tritium (H 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)

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

    International Nuclear Information System (INIS)

    Yanagisawa, Kazuaki; Fujishiro, Toshio; Horiki, Oichiro; Chen Dianshan; Takeuchi, Kiyoshi.

    1992-01-01

    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.)

  5. Aplicación de microondas en el tratamiento de emulsiones del tipo agua en aceite (w/o) y aceite en agua (o/w).

    OpenAIRE

    PÉREZ PÁEZ, ROCIO

    2011-01-01

    Las emulsiones del tipo agua en aceite (w/o) y aceite en agua (o/w) están compuestas por una mezcla de aceite, agua, lodo y otros agentes. Se pueden encontrar en el proceso y/o en los vertidos de diferentes tipos de industrias, tales como refinerías de petróleo, plantas procesadoras de aceite de consumo, industrias farmacéuticas, industrias de alimentos, etc. El calentamiento de un material a una frecuencia de microondas depende de la frecuencia de la onda electromagnética y de las propie...

  6. BWR stability: history and state-of-the-art

    International Nuclear Information System (INIS)

    Yadigaroglu, George

    2014-01-01

    The paper briefly recalls the historical developments, reviews the important phenomena, the analytical and simulation tools that are used for the analysis of BWR stability focussing on the linear, frequency domain methods

  7. Declaración y financiación de obras hidráulicas de interés general, mercado del agua, aguas subterráneas, planificación hidrológica

    OpenAIRE

    Llamas, M. R.

    1997-01-01

    En mayo de 1997 el Ministerio de Medio Ambiente difundió un borrador de Reforma de la Ley de Aguas española de 1985. Esta actuación se enmarcó dentro de la política de transparencia informativa y búsqueda de consenso social en los temas conflictivos de la política del agua en España. El autor propone que esa propuesta de Reforma sea retirada pues, aunque trata algunos temas interesantes como la reutilización de agua, la desalación de aguas de mar y el mercado del agua, no aborda los temas rea...

  8. Riego subsuperficial con aguas residuales tratadas

    OpenAIRE

    Crespi, Raúl; Camacho, Emilio; Polo, María José

    2009-01-01

    La reutilización de aguas residuales tratadas para riego por goteo subsuperficial (RGS) de cultivos extensivos, es una práctica reconocida mundialmente, siendo la obturación de emisores un serio problema en la operación de estos sistemas. Durante el ciclo agrícola 2002/03, se realizó un ensayo experimental usando dos tipos de agua: limpia (AL) y residual tratada (AR) en un sistema mixto combinando un reactor biológico con laguna de maduración y tres tipos de protectores del emisor: micro dosi...

  9. Trihalometanos en aguas de consumo humano

    OpenAIRE

    C Hernández Sánchez; Luis González G; Rubio Armendáriz C; JM Caballero Mesa; N Ben-Charki El-Mousati; A Hardisson de la Torre

    2011-01-01

    Los trihalometanos (THMs) son subproductos de desinfección que resultan de la cloración de las aguas. Los THMs engloban a sustancias como el cloroformo (CHCl ), el 3 bromodiclorometano (CHBrCl ), el clorodibromometano (CHBr Cl) 2 2 y el tribromometano (CHBr ). La Agencia Internacional para la 3 Investigación del Cáncer ha clasificado al cloroformo y al bromodiclorometano en el grupo 2B que incluye a las sustancias posiblemente carcinogénicas en humanos. Debido a su toxicidad y a que el agua d...

  10. Parallel channel effects under BWR LOCA conditions

    International Nuclear Information System (INIS)

    Suzuki, H.; Hatamiya, S.; Murase, M.

    1988-01-01

    Due to parallel channel effects, different flow patterns such as liquid down-flow and gas up-flow appear simultaneously in fuel bundles of a BWR core during postulated LOCAs. Applying the parallel channel effects to the fuel bundle, water drain tubes with a restricted bottom end have been developed in order to mitigate counter-current flow limiting and to increase the falling water flow rate at the upper tie plate. The upper tie plate with water drain tubes is an especially effective means of increasing the safety margin of a reactor with narrow gaps between fuel rods and high steam velocity at the upper tie plate. The characteristics of the water drain tubes have been experimentally investigated using a small-scaled steam-water system simulating a BWR core. Then, their effect on the fuel cladding temperature was evaluated using the LOCA analysis program SAFER. (orig.)

  11. 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.

  12. Sustancias húmicas en aguas para abastecimiento

    Directory of Open Access Journals (Sweden)

    Miller Camargo Valero

    1999-09-01

    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.

  13. 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.

  14. LBB application in Swedish BWR design

    International Nuclear Information System (INIS)

    Kornfeldt, H.; Bjoerk, K.O.; Ekstroem, P.

    1997-01-01

    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

  15. Evaluation on transmutation performance of minor actinides with high-flux BWR

    International Nuclear Information System (INIS)

    Setiawan, M.B.; Kitamoto, A.; Taniguchi, A.

    2001-01-01

    The performance of high-flux BWR (HFBWR) for burning and/or transmutation (B/T) treatment of minor actinides (MA) and long-lived fission products (LLFP) was discussed herein for estimating an advanced waste disposal with partitioning and transmutation (P and T). The concept of high-flux B/T reactor was based on a current 33 GWt-BWR, to transmute the mass of long-lived transuranium (TRU) to short-lived fission products (SLFP). The nuclide selected for B/T treatment was MA (Np-237, Am-241, and Am-243) included in the discharged fuel of LWR. The performance of B/T treatment of MA was evaluated by a new function, i.e. [F/T ratio], defined by the ratio of the fission rate to the transmutation rate in the core, at an arbitrary burn-up, due to all MA nuclides. According to the results, HFBWR could burn and/or transmute MA nuclides with higher fission rate than BWR, but the fission rate did not increase proportionally to the flux increment, due to the higher rate of neutron adsorption. The higher B/T fraction of MA would result in the higher B/T capacity, and will reduce the units of HFBWR needed for the treatment of a constant mass of MA. In addition, HFBWR had a merit of higher mass transmutation compared to the reference BWR, under the same mass loading of MA

  16. Verification of a BWR code package by gamma scan measurements

    International Nuclear Information System (INIS)

    Nakajima, Tsuyoshi; Iwamoto, Tatsuya; Kumanomido, Hironori

    1996-01-01

    High-burnup 8 x 8 fuel with a large central water rod (called step 2 fuel) has been recently introduced to the latest Japanese boiling water reactor (BWR) plants. Lanthanum-140 gamma intensity is almost directly related to nodal powers. By gamma scan measurement, the axial distribution of 140 La in the exposed fuel was measured at the end of cycle (EOC) 1 and was compared with the calculation by a BWR code package TGBLA/LOGOS. The multienrichment fuel-type core (MEC) design was adopted for the initial cycle core of the plants. The MEC design contains three different enrichment types of fuels to simulate the equilibrium cycles, achieve much higher discharge exposure, and save fuel cycle cost, and the low-enrichment fuels are loaded in periphery and in control cells. Such MEC design could be a challenge to the BWR design methods because of the large spectrum mismatch among the fuel assemblies of the different enrichments. The aforementioned comparison has shown that the accuracy of the TGBLA/LOGOS code package is satisfactory

  17. Comparative analysis of mechanical characteristics of solidified concentrates from BWR system using Yugoslav and Italian cements

    International Nuclear Information System (INIS)

    Plecas, I.; Peric, A.; Drljaca, J.; Kostadinovic, A.

    1987-01-01

    In this paper, properties of Italian and Yugoslav cement mixture with BWR evaporation concentrates were compared, research was held upon fifteen samples, according to the adequate formulations. Samples were made in standard cube form, side 10 cm. Functional relationship between decreasing the compressive strength and amount of incorporated BWR concentrate cement mixture was developed. The results of research showed nearly the same mechanical properties of solidified BWR concentrate with Italian and Yugoslav cements. (author)

  18. Predictive uncertainty reduction in coupled neutron-kinetics/thermal hydraulics modeling of the BWR-TT2 benchmark

    Energy Technology Data Exchange (ETDEWEB)

    Badea, Aurelian F., E-mail: aurelian.badea@kit.edu [Karlsruhe Institute of Technology, Vincenz-Prießnitz-Str. 3, 76131 Karlsruhe (Germany); Cacuci, Dan G. [Center for Nuclear Science and Energy/Dept. of ME, University of South Carolina, 300 Main Street, Columbia, SC 29208 (United States)

    2017-03-15

    Highlights: • BWR Turbine Trip 2 (BWR-TT2) benchmark. • Substantial (up to 50%) reduction of uncertainties in the predicted transient power. • 6660 uncertain model parameters were calibrated. - Abstract: By applying a comprehensive predictive modeling methodology, this work demonstrates a substantial (up to 50%) reduction of uncertainties in the predicted total transient power in the BWR Turbine Trip 2 (BWR-TT2) benchmark while calibrating the numerical simulation of this benchmark, comprising 6090 macroscopic cross sections, and 570 thermal-hydraulics parameters involved in modeling the phase-slip correlation, transient outlet pressure, and total mass flow. The BWR-TT2 benchmark is based on an experiment that was carried out in 1977 in the NPP Peach Bottom 2, involving the closure of the turbine stop valve which caused a pressure wave that propagated with attenuation into the reactor core. The condensation of the steam in the reactor core caused by the pressure increase led to a positive reactivity insertion. The subsequent rise of power was limited by the feedback and the insertion of the control rods. The BWR-TT2 benchmark was modeled with the three-dimensional reactor physics code system DYN3D, by coupling neutron kinetics with two-phase thermal-hydraulics. All 6660 DYN3D model parameters were calibrated by applying a predictive modeling methodology that combines experimental and computational information to produce optimally predicted best-estimate results with reduced predicted uncertainties. Simultaneously, the predictive modeling methodology yields optimally predicted values for the BWR total transient power while reducing significantly the accompanying predicted standard deviations.

  19. Predictive uncertainty reduction in coupled neutron-kinetics/thermal hydraulics modeling of the BWR-TT2 benchmark

    International Nuclear Information System (INIS)

    Badea, Aurelian F.; Cacuci, Dan G.

    2017-01-01

    Highlights: • BWR Turbine Trip 2 (BWR-TT2) benchmark. • Substantial (up to 50%) reduction of uncertainties in the predicted transient power. • 6660 uncertain model parameters were calibrated. - Abstract: By applying a comprehensive predictive modeling methodology, this work demonstrates a substantial (up to 50%) reduction of uncertainties in the predicted total transient power in the BWR Turbine Trip 2 (BWR-TT2) benchmark while calibrating the numerical simulation of this benchmark, comprising 6090 macroscopic cross sections, and 570 thermal-hydraulics parameters involved in modeling the phase-slip correlation, transient outlet pressure, and total mass flow. The BWR-TT2 benchmark is based on an experiment that was carried out in 1977 in the NPP Peach Bottom 2, involving the closure of the turbine stop valve which caused a pressure wave that propagated with attenuation into the reactor core. The condensation of the steam in the reactor core caused by the pressure increase led to a positive reactivity insertion. The subsequent rise of power was limited by the feedback and the insertion of the control rods. The BWR-TT2 benchmark was modeled with the three-dimensional reactor physics code system DYN3D, by coupling neutron kinetics with two-phase thermal-hydraulics. All 6660 DYN3D model parameters were calibrated by applying a predictive modeling methodology that combines experimental and computational information to produce optimally predicted best-estimate results with reduced predicted uncertainties. Simultaneously, the predictive modeling methodology yields optimally predicted values for the BWR total transient power while reducing significantly the accompanying predicted standard deviations.

  20. 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.

  1. Tratamiento Híbrido de agua residual gris doméstica

    Directory of Open Access Journals (Sweden)

    Pablo Paredes

    2013-07-01

    Full Text Available El reúso del agua residual gris doméstica es una práctica que también puede aplicarse en nuestro país. Este reúso ayudaria a reducir los costos de consumo de agua potable que actualmente poseen las personas de estratos medio y bajo en el país. Este estudio aplica un concepto nuevo de sistema de tratamiento híbrido para descontaminar el agua y poderla reusar para riego de jardines o para llenar el tanque de los inodoros en una vivienda. Un tratamiento de agua residual gris doméstica híbrido plantea la consecución de remociones totales de materia orgánica, sólidos suspendidos totales, coliformes fecales del 93 %, 92 % y 99,2 %, respectivamente. Este tipo de tratamiento puede tener un valor agregado al disminuir las descargas de aguas servidas a través del sistema de alcantarillado sanitario, con el abaratamiento de la infraestructura para los organismos seccionales del país.

  2. Specifications of the BWR simulator for HAMMLAB 2000

    International Nuclear Information System (INIS)

    Grini, Rolf-Einar; Miettinen, Jaakko; Nurmilaukas, Pekka; Raussi; Pekka; Saarni, Ray; Stokke; Egil; Soerensen, Aimar; Tiihonen, Olli

    1998-02-01

    The Boiling Water Reactor (BWR) simulator for HAMMLAB 2000 will be a model of the Swedish plant Forsmark-3. This report gives the specifications of the BWR simulator. The bulk of the report is a copy of the relevant addendum to the contract with the developer, and to the contract with the group of utilities and with ABB Atom. After a general overview, each plant system is described one after the other (using the reference plant system coding), and the simulation of each system is specified. Even the systems that shall not be simulated are included; in those cases the specification is: It is not required that ... is simulated. A list of malfunctions is given, as well as a list of validation transients. Finally the operator interface is specified. (author)

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

    International Nuclear Information System (INIS)

    1992-09-01

    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 specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

  4. BWR zinc addition Sourcebook

    International Nuclear Information System (INIS)

    Garcia, Susan E.; Giannelli, Joseph F.; Jarvis, Alfred J.

    2014-01-01

    Boiling Water Reactors (BWRs) have been injecting zinc into the primary coolant via the reactor feedwater system for over 25 years for the purpose of controlling primary system radiation fields. The BWR zinc injection process has evolved since the initial application at the Hope Creek Nuclear Station in 1986. Key transitions were from the original natural zinc oxide (NZO) to depleted zinc oxide (DZO), and from active zinc injection of a powdered zinc oxide slurry (pumped systems) to passive injection systems (zinc pellet beds). Zinc addition has continued through various chemistry regimes changes, from normal water chemistry (NWC) to hydrogen water chemistry (HWC) and HWC with noble metals (NobleChem™) for mitigation of intergranular stress corrosion cracking (IGSCC) of reactor internals and primary system piping. While past reports published by the Electric Power Research Institute (EPRI) document specific industry experience related to these topics, the Zinc Sourcebook was prepared to consolidate all of the experience gained over the past 25 years. The Zinc Sourcebook will benefit experienced BWR Chemistry, Operations, Radiation Protection and Engineering personnel as well as new people entering the nuclear power industry. While all North American BWRs implement feedwater zinc injection, a number of other BWRs do not inject zinc. This Sourcebook will also be a valuable resource to plants considering the benefits of zinc addition process implementation, and to gain insights on industry experience related to zinc process control and best practices. This paper presents some of the highlights from the Sourcebook. (author)

  5. BWR full integral simulation test (FIST) pretest predictions with TRACBO2

    International Nuclear Information System (INIS)

    Sutherland, W.A.; Alamgir, M.

    1984-01-01

    The Full Integral Simulation Test program is a three pronged approach to the development of best-estimate analysis capability for BWR systems. An analytical method development program is underway to extend the BWR-TRAC computer code to model reactor kinetics and major interfacing systems, including balance-of-plant, to improve application modeling flexibility, and to reduce computer running time. An experimental program is underway in a new single bundle system test facility to extend the large break loss-of-coolant accident LOCA data base to small breaks and operational transients. And a method qualification program is underway to test TRACBO2 against experiments in the FIST facility. The recently completed Phase 1 period included a series of LOCA and power transient tests, and successful pretest analysis of the large and small break LOCA tests with TRACBO2. These comparisons demonstrate BWR-TRAC capability for small and large break analysis, and provide detailed understanding of the phenomena

  6. BWR water chemistry impurity studies

    International Nuclear Information System (INIS)

    Ljungberg, L.G.; Korhonen, S.; Renstroem, K.; Hofling, C.G.; Rebensdorff, B.

    1990-03-01

    Laboratory studies were made on the effect of water impurities on environmental cracking in simulated BWR water of stainless steel, low alloy steel and nickel-base alloys. Constant elongation rate tensile (CERT) tests were run in simulated normal water chemistry (NWC), hydrogen water chemistry (HWC), or start-up environment. Sulfate, chloride and copper with chloride added to the water at levels of a fraction of a ppM were found to be extremely deleterious to all kinds of materials except Type 316 NG. Other detrimental impurities were fluoride, silica and some organic acids, although acetic acid was beneficial. Nitrate and carbon dioxide were fairly inoccuous. Corrosion fatigue and constant load tests on compact tension specimens were run in simulated normal BWR water chemistry (NWC) or hydrogen water chemistry (HWC), without impurities or with added sulfate or carbon dioxide. For sensitized Type 304 SS in NWC, 0.1 ppM sulfate increased crack propagation rates in constant load tests by up to a factor of 100, and in fatigue tests up to a factor of 10. Also, cracking in Type 316 nuclear grade SS and Alloy 600 was enhanced, but to a smaller degree. Carbon dioxide was less detrimental than sulfate. 3 figs., 4 tabs

  7. 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.

  8. Coretran/Vipre assembly critical power assessment against Nupec BWR experiments

    International Nuclear Information System (INIS)

    Aounallah, Y.

    2001-01-01

    This study has been performed, in the framework of the STARS project, to assess CORETRAN-01/VIPRE-02 code capability to predict critical heat flux conditions for BWR fuel assemblies. The assessment is based on comparisons of the code results with the NUPEC steady-state critical power measurements on full-scale assemblies tested under a range of flow conditions. Two assembly types were considered, the standard BWR 8 x 8 and the so-called ''high-burnup'' assembly, similar to GE-10. Code modelling options that have a significant impact on the results have been identified, along with code limitations. (author)

  9. Evaluación del postratamiento de aguas residuales municipales mediante la utilización de macrofitas como las lentejas de agua (lemma minor en lagunas de estabilización.

    Directory of Open Access Journals (Sweden)

    Juan Pablo Rodriguez Miranda

    2018-04-01

    Full Text Available El presente artículo, tiene el propósito de determinar la utilidad de la lenteja de agua (lemna minor como postratamiento en lagunas de estabilización que tratan aguas residuales domésticas, fue analizada una muestra de agua residual proveniente del efluente de la laguna anaerobia del sistema de tratamiento de aguas residuales el Salguero de Valledupar-Cesar; la muestra fue inoculada con las lentejas de agua, las cuales fueron tomadas de reservorios ubicados en las afueras del Municipio en mención. Se realizó el montaje empleando un sistema tipo batch a escala laboratorio con tres replicas y dos controles los parámetros analizados fueron nutrientes (nitrógeno y fósforo. La remoción de nutrientes fue: 72% P y 95% N. Se pudo establecer que las lentejas de agua presentan una buena eficiencia en relación a la remoción de nutrientes.

  10. 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

  11. El Agua Salina y los Métodos de Riego

    Directory of Open Access Journals (Sweden)

    Bustamante Betancur Fabio

    1985-12-01

    Full Text Available La selección del método más adecuado de riego está notoriamente influenciado por las condiciones de salinidad que pueda haber en el suelo o en el agua que se usará para el riego. El objetivo principal del riego es el de abastecer el suelo con agua para que ella sea fácilmente disponible a los cultivos que en él se desarrollan o crecen. Bajo condiciones normales el método de riego que mejor se adapta, depende del cultivo, la topografía, las características del suelo y la disponibilidad del agua. Las condiciones de salinidad y sodicidad presentes en el suelo, están influenciadas por la concentración local de sales; la aplicación del riego, es una de las causas de la migración de sales y puede influenciar notoriamente el efecto salino del agua que con una determinada calidad sea aplicada.

  12. Remoción de Metales de Aguas Residuales Industriales

    Directory of Open Access Journals (Sweden)

    Carlos Alberto Guerrero Fajardo

    2009-10-01

    Full Text Available En este trabajo se evalúa la tasa de remoción de cuatro metales pesados, comúnmente encontrado en Aguas Residuales Industriales (A,R,I,: Cobre, Cromo, Mercurio y Plata, mediante el empleo de plantas acuáticas vasculares "Jacintos de Agua". Las investigaciones para cada metal se realizaron, acondicionando aguas con cinco concentraciones diferentes que oscilaran por encima y por debajo del valor promedio encontrado en A,R,1,Se adoptó un modelo de comportamiento del sistema debido a la similitud que muestra la remoción de metales por el Jacinto de Agua, con el estudio de cultivos puros de MONOD, Esto permite realizar los ajustes estadísticos a los datosexperimentales encontrados en el presente proyecto. La ecuación establecida para el estudio de remoción de metales por un método biológico es el siguiente: % Remoción = A x t / B + t A= Porcentaje de remoción máxima B= Tiempo mínimo para alcanzar la mitad de la remoción máxima, t =Tiempo de remoción Las constantes A y B, indican la tendencia a la remoción y el tiempo mínimo de recolección, respectivamente. El Jacinto de Agua presenta limitación en su capacidad de remoción de metales, esto determina concentraciones máximas permisibles de metales en el agua para poder utilizar estas plantas acuáticas. El estudio de selectividad en la remoción de metales, indica que la presencia de Cromo, Mercurio y Plata disminuyen el porcentaje de remoción de Cobre, Se observa disminución en el porcentaje de remoción de Cromo, cuando están presentes Cobre, Mercurio y Plata en el agua residual. El caso del Mercurio es diferente a los dos anteriores, observándose más bien un efecto sinergético.

  13. Recent BWR fuel management reactor physics advances

    International Nuclear Information System (INIS)

    Crowther, R.L.; Congdon, S.P.; Crawford, B.W.; Kang, C.M.; Martin, C.L.; Reese, A.P.; Savoia, P.J.; Specker, S.R.; Welchly, R.

    1982-01-01

    Improvements in BWR fuel management have been under development to reduce uranium and separative work (SWU) requirements and reduce fuel cycle costs, while also maintaining maximal capacity factors and high fuel reliability. Improved reactor physics methods are playing an increasingly important role in making such advances feasible. The improved design, process computer and analysis methods both increase knowledge of the thermal margins which are available to implement fuel management advance, and improve the capability to reliably and efficiently analyze and design for fuel management advances. Gamma scan measurements of the power distributions of advanced fuel assembly and advanced reactor core designs, and improved in-core instruments also are important contributors to improving 3-d predictive methods and to increasing thermal margins. This paper is an overview of the recent advances in BWR reactor physics fuel management methods, coupled with fuel management and core design advances. The reactor physics measurements which are required to confirm the predictions of performance fo fuel management advances also are summarized

  14. BWR normal water chemistry guidelines: 1986 revision

    International Nuclear Information System (INIS)

    1988-09-01

    Boiling water reactors (BWRs) have experienced stress corrosion cracking in the reactor cooling system piping resulting in adverse impacts on plant availability and personnel radiation exposure. The BWR Owners Group and EPRI have sponsored a major research and development program to provide remedies for this stress corrosion cracking problem. This work shows that the likelihood of cracking depends on the plant's water chemistry performance (environment) as well as on material condition and stress level. Plant experience and other research demonstrate that water quality also affects fuel performance and radiation field buildup in BWRs. This report,''BWR Normal Water Chemistry Guidelines: 1986 Revision,'' presents suggested generic water chemistry specifications, justifies the proposed water chemistry limits, suggests responses to out-of-specification water chemistry, discusses available chemical analysis methods as well as data management and surveillance schemes, and details the management philosophy required to successfully implement a water chemistry control program. An appendix contains recommendations for water quality of auxiliary systems. 73 refs., 20 figs., 9 tabs

  15. Hydrogen injection device in BWR type reactor

    International Nuclear Information System (INIS)

    Takagi, Jun-ichi; Kubo, Koji.

    1988-01-01

    Purpose: To reduce the increasing ratio of main steam system dose rate due to N-16 activity due to excess hydrogen injection in the hydrogen injection operation of BWR type reactors. Constitution: There are provided a hydrogen injection mechanism for injecting hydrogen into primary coolants of a BWR type reactor, and a chemical injection device for injecting chemicals such as methanol, which makes nitrogen radioisotopes resulted in the reactor water upon hydrogen injection non-volatile, into the pressure vessel separately from hydrogen. Injected hydrogen and the chemicals are not reacted in the feedwater system, but the reaction proceeds due to the presence of radioactive rays after the injection into the pressure vessel. Then, hydrogen causes re-combination in the downcomer portion to reduce the dissolved oxygen concentration. Meanwhile, about 70 % of the chemicals is supplied by means of a jet pump directly to the reactor core, thereby converting the chemical form of N-16 in the reactor core more oxidative (non-volatile). (Kawakami, Y.)

  16. BWR radiation buildup control with ionic zinc

    International Nuclear Information System (INIS)

    Marble, W.J.; Wood, C.J.; Leighty, C.E.; Green, T.A.

    1986-01-01

    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

  17. 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)

  18. DE AGUA. ESTUDIO PRELIMINAR

    Directory of Open Access Journals (Sweden)

    Esther E. Pellizzari

    2015-01-01

    Full Text Available El objetivo del presente estudio fue investigar la resistencia al arsénico en cultivos puros de Pseudomonas aeruginosa , aislada de aguas subterráneas de Presidencia Roque Sáenz Peña, provincia de Chaco y evaluar la posibilidad de su uso para la remoción de este contaminante presente en las aguas subterráneas. Las cepas fueron inmovilizadas en piedra natural y se cu ltivaron en caldo de sales y 1 mgAs/L . Se observó la resistencia al arsénico y la formación de biofilm , logrando la interacción entre la s células, roca y arsénico . L a remoción de arsénico se evaluó durante 3 meses y el porcentaje de eliminación de arsénico al final del experimento fue 60%.

  19. Delivering high performance BWR fuel reliably

    International Nuclear Information System (INIS)

    Schardt, J.F.

    1998-01-01

    Utilities are under intense pressure to reduce their production costs in order to compete in the increasingly deregulated marketplace. They need fuel, which can deliver high performance to meet demanding operating strategies. GE's latest BWR fuel design, GE14, provides that high performance capability. GE's product introduction process assures that this performance will be delivered reliably, with little risk to the utility. (author)

  20. Que es lo que queda cuando el agua se va

    Directory of Open Access Journals (Sweden)

    Hernán Ascui Fernández

    2007-10-01

    Full Text Available El agua siempre deja huellas de su paso. Las aguas del Nilo, después de inundar las llanuras del río, se retiraban dejando el suelo colmado de los nutrientes que habían traído desde el corazón de África. Las costas de Chile han sido modeladas por el ir y venir de las aguas marinas, el río Ibáñez ha esculpido un profundo canal en la roca para abrirse paso, dando nacimiento a un magnífico lugar conocido como Garganta del río Ibáñez. Las cascadas horadan montañas para poder deslizarse como blancas lágrimas, la sobrecogedora belleza de los glaciares ha dejado potentes huellas de sus trayectorias. La lluvia también deposita marcas en los lugares y superficies que moja. A veces son apenas sutiles señales como el musgo que crece en las piedras húmedas o en el perfume de los bosques de Valdivia, con su tierra negra y empapada de lluvia y rocío. Otras veces las huellas del agua están presentes en la arquitectura como ocurre con los palafitos de Castro o Caleta Tortel, donde las casas se levantan para tomar distancia del agua que se mueve al ritmo de las mareas. En otras ocasiones, las huellas del descorren el velo de un drama urbano; es lo que ocurrió con la inundación del invierno pasado. Las huellas del agua aún son visibles en las paredes manchadas, en los muebles, en los pisos. El agua se fue pero dejando tras de sí un desalentador recuerdo de su paso por las ciudades, los pueblos y las casas.

  1. Health surveys of cyanobacteria in drinking and recreational waters Vigilancia sanitaria de cianobacterias en aguas de consumo humano y aguas de baño

    Directory of Open Access Journals (Sweden)

    Guadalupe Martínez Juárez

    2008-06-01

    Full Text Available Environmental surveys of drinking and recreational waters with the objective of related health risk control are a common component in public health policy. Based in updated scientific knowledge proliferation of Cyanobacteria constitutes a new risk, and it should be considered in public health programs. The principal objective of this work is to assess the presence of cyanobacteria and microcystins in drinking and recreational waters. Results of a four year survey in the sanitary department of Talavera de la Reina are presented. A descriptive study of the presence of cyanobacteria and microcystins, in non treated water from two reservoirs at the pick up point and after treatment in the exit point from two treatment plants. The same approach has been used in two recreational summer natural water reservoirs. Every fifteen days samples were analysed for cyanobateria recount and free microcystin level determination by ELISA essay. From the results of the analysis in drinking water we concluded that microcystines levels in non treated water from reservoirs are not high, less than 6 per cent of samples showed a positive results for microcystins. Treatment was effective as no sample after treatment showed a positive result for microcystins. 48 per cent of recreational water samples showed levels above 100,000 cells per ml, which corresponds to the WHO moderate adverse effect risk guide level. Public health policy should include systematic level survey of cyanobaterias from drinking and recreational water. Exposure related health adverse effects surveys should be conducted.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

  2. Condensate polishing guidelines for PWR and BWR plants

    International Nuclear Information System (INIS)

    Robbins, P.; Crinigan, P.; Graham, B.; Kohlmann, R.; Crosby, C.; Seager, J.; Bosold, R.; Gillen, J.; Kristensen, J.; McKeen, A.; Jones, V.; Sawochka, S.; Siegwarth, D.; Keeling, D.; Polidoroff, T.; Morgan, D.; Rickertsen, D.; Dyson, A.; Mills, W.; Coleman, L.

    1993-03-01

    Under EPRI sponsorship, an industry committee, similar in form and operation to other guideline committees, was created to develop Condensate Polishing Guidelines for both PWR and BWR systems. The committee reviewed the available utility and water treatment industry experience on system design and performance and incorporated operational and state-of-the-art information into document. These guidelines help utilities to optimize present condensate polisher designs as well as be a resource for retrofits or new construction. These guidelines present information that has not previously been presented in any consensus industry document. The committee generated guidelines that cover both deep bed and powdered resin systems as an integral part of the chemistry of PWR and BWR plants. The guidelines are separated into sections that deal with the basis for condensate polishing, system design, resin design and application, data management and performance and management responsibilities

  3. Role of BWR MK I secondary containments in severe accident mitigation

    International Nuclear Information System (INIS)

    Greene, S.R.

    1986-01-01

    The recent advent of detailed containment analysis codes such as CONTAIN and MELCOR has facilitated the development of the first large-scale, architectural-based BWR secondary containment models. During the past year ORNL has developed detailed, plant-specific models of the Browns Ferry and Peach Bottom secondary containments, and applied these models in a variety of studies designed to evaluate the role and effectiveness of BWR secondary containments in severe accident mitigation. The topology and basis for these models is discussed, together with some of the emerging insights from these studies

  4. Automatic refueling platform and CRD remote handling device for BWR plant

    International Nuclear Information System (INIS)

    Kato, Hiroaki; Takagi, Kaoru

    1978-01-01

    In BWR plants, machines for replacing fuel assemblies and control rod drives are usually operated directly by personnel. An automatic refueling platform and a CRD remote handling device aiming at radiation exposure reduction and handling perfectness are described, which are already used in BWR plants. Automation of the former is achieved in transporting fuel assemblies between a reactor pressure vessel and a fuel storage pool, shuffling fuel assemblies in a reactor core and moving fuel assemblies in a fuel storage pool. In the latter, replacement of CRDs is nearly all performed remotely. (Mori, K.)

  5. BWR fuel performance

    International Nuclear Information System (INIS)

    Baily, W.E.; Armijo, J.S.; Jacobson, J.; Proebstle, R.A.

    1979-01-01

    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

  6. Economía de agua, economía de instalaciones

    OpenAIRE

    Salas Serrano, Julián; Fernández Rodríguez, Luis

    1988-01-01

    [ES]El agua es un recurso escaso y por lo tanto se considera cada vez más importante optimizar su uso. En este artículo se exponen algunas técnicas y estrategias desarrolladas, en diversos países, para minimizar las pérdidas y el consumo inútil de agua en usos domésticos y evitar los gastos que supone, a la colectividad, la depuración de agua innecesariamente contaminada, así como el sobredimensionamiento de equipos e instalaciones. También se presenta, de un modo gene...

  7. Sensitivity of BWR shutdown margin tests to local reactivity anomalies

    International Nuclear Information System (INIS)

    Cokinos, D.M.; Carew, J.F.

    1987-01-01

    Successful shutdown margin (SDM) demonstration is a required procedure in the startup of a newly configured boiling water reactor (BWR) core. In its most reactive condition throughout a cycle, a BWR core must be capable of being made subcritical by a specified margin with the highest worth control rod fully withdrawn and all other rods at their fully inserted positions. Two different methods are used to demonstrate SDM: (a) the adjacent-rod test and (b) the in-sequence test. In the adjacent-rod test, the strongest rod is fully withdrawn and an adjacent rod is withdrawn to reach criticality. In the in-sequence test, control rods spread throughout the core are withdrawn in a predetermined sequence of withdrawals. Larger than expected core k/sub eff/ values have been observed during the performance of BWR SDM tests. The purpose of the work summarized in this paper has been to investigated and quantify the sensitivity of both the adjacent-rod and in-sequence SDM tests to local reactivity anomalies. This was accomplished by introducing reactivity perturbations at selected four-bundle cell locations and by evaluating their effect on core reactivity in each of the two tests

  8. Reduction of radiation exposure in Japanese BWR Nuclear Power Plants

    International Nuclear Information System (INIS)

    Morikawa, Yoshitake

    1995-01-01

    The reduction of occupational exposure to radiation during the annual inspection and maintenance outages of Japanese boiling water reactors (BWR) is one of the most important objectives for stable and reliable operation. It was shown that this radiation exposure is caused by radionuclides, such as Co-60, Co-58 and Mn-54 which are produced from the metal elements Co, Ni, and Fe present in the corrosion products of structural materials that had been irradiated by neutrons. Therefore, to reduce radiation sources and exposures in Japanese BWRs, attempts have been reinforced to remove corrosion products and activated corrosion products from the primary coolant system. This paper describes the progress of the application of these measures to Japanese BWRs. Most Japanese BWR-4 and BWR-5 type nuclear power plants started their commercial operations during the 1970s. With the elapse of time during operations, a problem came to the forefront, namely that occupational radiation exposure during plant outages gradually increased, which obstructed the smooth running of inspections and maintenance work. To overcome this problem, extensive studies to derive effective countermeasures for radiation exposure reduction were undertaken, based on the evaluation of the plants operation data

  9. Reduction of radiation exposure in Japanese BWR Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Morikawa, Yoshitake [ISOGO Nuclear Engineering Center, Yokohama (Japan)

    1995-03-01

    The reduction of occupational exposure to radiation during the annual inspection and maintenance outages of Japanese boiling water reactors (BWR) is one of the most important objectives for stable and reliable operation. It was shown that this radiation exposure is caused by radionuclides, such as Co-60, Co-58 and Mn-54 which are produced from the metal elements Co, Ni, and Fe present in the corrosion products of structural materials that had been irradiated by neutrons. Therefore, to reduce radiation sources and exposures in Japanese BWRs, attempts have been reinforced to remove corrosion products and activated corrosion products from the primary coolant system. This paper describes the progress of the application of these measures to Japanese BWRs. Most Japanese BWR-4 and BWR-5 type nuclear power plants started their commercial operations during the 1970s. With the elapse of time during operations, a problem came to the forefront, namely that occupational radiation exposure during plant outages gradually increased, which obstructed the smooth running of inspections and maintenance work. To overcome this problem, extensive studies to derive effective countermeasures for radiation exposure reduction were undertaken, based on the evaluation of the plants operation data.

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

    International Nuclear Information System (INIS)

    Itjeu Karliana; Sumijanto; Dhandhang Purwadi, M.

    2008-01-01

    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 m 3 /hour with cost US$ 0.58/m 3 . The coupling VK-300 reactor power type BWR with MED desalination plant is competitive economically. (author)

  11. Design guideline to prevent the pipe rupture by radiolysis gases in BWR steam piping

    International Nuclear Information System (INIS)

    Inagaki, T.; Miyagawa, M.; Ota, T.; Sato, T.; Sakata, K.

    2009-01-01

    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. Afterwards, the experimental study about combustion/detonation of radiolysis gas have been continued. And in March 2007, TENPES published a revised edition of the guideline. This is the report of the revised edition of that guideline. According to this guideline, it became possible to design BWR's steam piping to prevent accumulation of radiolysis gas. (author)

  12. Estudio de comparación del tratamiento de aguas residuales domésticas utilizando lentejas y buchón de agua en humedales artificiales

    OpenAIRE

    Rodríguez-Miranda, Juan Pablo; Gómez, Esteban; Garavito, Laura; López, Francy

    2010-01-01

    El estudio de comparación del tratamiento de aguas residuales domésticas utilizando sistemas naturales como los humedales artificiales presenta resultados de remoción de materia orgánica (DBO5) de entre 70 y 86% al utilizar el buchón de agua, y de 58% cuando se utiliza lenteja de agua. El sistema de humedales artificiales se comporta hidráulicamente como un modelo de flujo pistón, sin distinción del tipo de planta acuática que se use. Durante la experimentación se observó que cuando se utiliz...

  13. Neutron noise analysis of BWR using time series analysis

    International Nuclear Information System (INIS)

    Fukunishi, Kohyu

    1976-01-01

    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) [de

  14. A BWR 24-month cycle analysis using multicycle techniques

    International Nuclear Information System (INIS)

    Hartley, K.D.

    1993-01-01

    Boiling water reactor (BWR) fuel cycle design analyses have become increasingly challenging in the past several years. As utilities continue to seek improved capacity factors, reduced power generation costs, and reduced outage costs, longer cycle lengths and fuel design optimization become important considerations. Accurate multicycle analysis techniques are necessary to determine the viability of fuel designs and cycle operating strategies to meet reactor operating requirements, e.g., meet thermal and reactivity margin constraints, while minimizing overall fuel cycle costs. Siemens Power Corporation (SPC), Nuclear Division, has successfully employed multi-cycle analysis techniques with realistic rodded cycle depletions to demonstrate equilibrium fuel cycle performance in 24-month cycles. Analyses have been performed by a BWR/5 reactor, at both rated and uprated power conditions

  15. Coretran/Vipre assembly critical power assessment against Nupec BWR experiments

    Energy Technology Data Exchange (ETDEWEB)

    Aounallah, Y. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    2001-07-01

    This study has been performed, in the framework of the STARS project, to assess CORETRAN-01/VIPRE-02 code capability to predict critical heat flux conditions for BWR fuel assemblies. The assessment is based on comparisons of the code results with the NUPEC steady-state critical power measurements on full-scale assemblies tested under a range of flow conditions. Two assembly types were considered, the standard BWR 8 x 8 and the so-called ''high-burnup'' assembly, similar to GE-10. Code modelling options that have a significant impact on the results have been identified, along with code limitations. (author)

  16. Development of RBWR (Resource-renewable BWR) for environmental burden reduction of radioactive wastes

    International Nuclear Information System (INIS)

    Hino, Tetsushi; Ohtsuka, Masaya; Moriya, Kumiaki; Matsuura, Masayoshi

    2014-01-01

    Accumulation of long-life transuranium elements produced as by-products with uranium fuel burning became an issue of nuclear power. Hitachi had been developing the reactor with transuranium elements burning as fuels based on BWR type reactors successfully used as commercial reactors: RBWR (Resource-renewable BWR). Efficient transmutation and fissioning of transuranium elements needed adjustment of in-core neutron energy spectra distribution better for nuclear reaction of transuranium elements. Taking advantage of characteristics of BWR type reactors with neutron spectra hardening more easily adjustable than other type of reactors, multiple recycling and fissioning transuranium elements as fuels could make environmental burden reduction of radioactive wastes and efficient use of resources compatible. This article described the concept and history of RBWR and showed its specifications and reactor core characteristics. (T. Tanaka)

  17. Corrosion resistance improvement of ferritic steels through hydrogen additions to the BWR coolant

    International Nuclear Information System (INIS)

    Gordon, B.M.; Jewett, C.W.; Pickett, A.E.; Indig, M.E.

    1984-01-01

    Motivated by the success of oxygen suppression for mitigation of intergranular stress corrosion cracking (IGSCC) in weld sensitized austenitic materials used in Boiling Water Reactors (BWRs), oxygen suppression, through hydrogen additions to the feedwater was investigated to determine its affect on the corrosion resistance of ferritic and martensitic BWR structural materials. The results of these investigations are presented in this paper, where particular emphasis is placed on the corrosion performance of BWR pressure vessel low alloy steels, carbon steel piping materials and martensitic pump materials. It is important to note that the corrosion resistance of these materials in the BWR environment is excellent. Consequently this investigation was also motivated to determine whether there were any detrimental effects of hydrogen additions, as well as to identify any additional margin in ferritic/martensitic materials corrosion performance

  18. Phenomenology of BWR fuel assembly degradation

    Science.gov (United States)

    Kurata, Masaki; Barrachin, Marc; Haste, Tim; Steinbrueck, Martin

    2018-03-01

    Severe accidents occurred at the Fukushima-Daiichi Nuclear Power Station (FDNPS) which required an immediate re-examination of fuel degradation phenomenology. The present paper reviews the updated knowledge on the phenomenology of the fuel degradation, focusing mainly on the BWR fuel assembly degradation at the macroscopic scale and that of the individual interactions at the meso-scale. Oxidation of boron carbide (B4C) control rods potentially generates far larger amounts of heat and hydrogen under BWR accident conditions. All integral tests with B4C control rods or control blades have shown early failure, liquefaction, relocation and oxidation of B4C starting at temperatures around 1250 °C, well below the significant interaction temperatures of UO2-Zry. These interactions or reactions potentially influence the progress of fuel degradation in the early phase. The steam-starved conditions, which are being discussed as a likely scenario at the FDNPS accident, highly influence the individual interactions and potentially lead the fuel degradation in non-prototypical directions. The detailed phenomenology of individual interactions and their influence on the transient and on the late phase of the severe accidents are also discussed.

  19. 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.

  20. CALIDAD DEL AGUA EN POZOS DE ISLA COZUMEL, MÉXICO

    Directory of Open Access Journals (Sweden)

    Luz de Lourdes Aurora Coronado Alvarez

    2011-04-01

    Full Text Available Se analizaron in situ y en el laboratorio, variables físicas y químicas informativas de la calidad de agua subterránea de 14 pozos ubicados en el área de mayor uso de agua dulce de la isla Cozumel, Quintana Roo, México durante un ciclo anual (noviembre 2007 a octubre 2008. Se contrastaron los valores obtenidos con la normatividad nacional e internacional de calidad de agua para uso potable; contribuyendo con información que por un lado permitió determinar áreas con mejor calidad de agua y por otro, evaluar el comportamiento de las variables a escala temporal. Con una prueba de Kruskal-Wallis (p

  1. 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.

  2. Analysis of BWR out-of-phase instabilities in the frequency domain

    International Nuclear Information System (INIS)

    Farawila, Y.M.; Pruitt, D.W.; Kreuter, D.

    1992-01-01

    During startup or because of an inadvertent recirculation pump trip, a boiling water reactor (BWR) may operate at relatively low flow and high power conditions. At these conditions, a BWR is susceptible to coupled flow and power oscillations that could result in undesirable reactor scram unless appropriate countermeasures are taken. This contribution to analytical methods has been developed to address in part a general industrywide and regulatory concern about BWR stability initiated by the LaSalle 2 instability event in March 1988. This work is designed to extend the capability of the one-dimensional parallel channel frequency domain code STAIF to predict the regional oscillation decay ratio. The basic theory follows that developed by March-Leuba and Blakeman, where the oscillation mechanism is identified as the excitation of a subcritical neutronic mode with a constant core pressure drop boundary condition. The improvements to the basic theory include applying the theory to one-dimensional neutronics instead of point kinetics and taking account of the actual three-dimensional harmonic flux distribution

  3. 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.

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

    International Nuclear Information System (INIS)

    Kostic, Lj.

    1983-01-01

    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)

  5. Delivering high performance BWR fuel reliably

    Energy Technology Data Exchange (ETDEWEB)

    Schardt, J.F. [GE Nuclear Energy, Wilmington, NC (United States)

    1998-07-01

    Utilities are under intense pressure to reduce their production costs in order to compete in the increasingly deregulated marketplace. They need fuel, which can deliver high performance to meet demanding operating strategies. GE's latest BWR fuel design, GE14, provides that high performance capability. GE's product introduction process assures that this performance will be delivered reliably, with little risk to the utility. (author)

  6. Novel modular natural circulation BWR design and safety evaluation

    International Nuclear Information System (INIS)

    Ishii, Mamoru; Shi, Shanbin; Yang, Won Sik; Wu, Zeyun; Rassame, Somboon; Liu, Yang

    2015-01-01

    Highlights: • Introduction of BWR-type natural circulation small modular reactor preliminary design (NMR-50). • Design of long fuel cycle length for the NMR-50. • Design of double passive safety systems for the NMR-50. • RELAP5 analyses of design basis accidents for the NMR-50. - Abstract: The Purdue NMR (Novel Modular Reactor) represents a BWR-type small modular reactor with a significantly reduced reactor pressure vessel (RPV) height. Specifically, it has one third the height of a conventional BWR RPV with an electrical output of 50 MWe. The preliminary design of the NMR-50 including reactor, fuel cycle, and safety systems is described and discussed. The improved neutronics design of the NMR-50 extends the fuel cycle length up to 10 years. The NMR-50 is designed with double passive engineering safety system, which is intended to withstand a prolonged station black out with loss of ultimate heat sink accident such as experienced at Fukushima. In order to evaluate the safety features of the NMR-50, two representative design basis accidents, i.e. main steam line break (MSLB) and bottom drain line break (BDLB), are simulated by using the best-estimate thermal–hydraulic code RELAP5. The RPV water inventory, containment pressure, and the performance of engineering safety systems are investigated for about 33 h after the initiation of the accidents

  7. Application of TRAC-BD1/MOD1 to a BWR/4 feedwater control failure ATWS

    International Nuclear Information System (INIS)

    Rouhani, S.Z.; Giles, M.M.; Mohr, C.M. Jr.; Weaver, W.L. III.

    1984-01-01

    This paper begins with a short description of the Transient Reactor Analysis Code for Boiling Water Reactors (TRAC-BWR), briefly mentioning some of its main features such as specific BWR models and input structure. Next, an input model of a BWR/4 is described, and, the assumptions used in performing an analysis of the loss of a feedwater controller without scram are listed. The important features of the calculated trends in flows, pressure, reactivity, and power are shown graphically and commented in the text. A comparison of some of the main predicted trends with the calculated results from a similar study by General Electric is also presented

  8. Construction techniques and management methods for BWR plants

    International Nuclear Information System (INIS)

    Shimizu, Yohji; Tateishi, Mizuo; Hayashi, Yoshishige

    1989-01-01

    Toshiba is constantly striving for safer and more efficient plant construction to realize high-quality BWR plants within a short construction period. To achieve these aims, Toshiba has developed and improved a large number of construction techniques and construction management methods. In the area of installation, various techniques have been applied such as the modularization of piping and equipment, shop installation of reactor internals, etc. Further, installation management has been upgraded by the use of pre-installation review programs, the development of installation control systems, etc. For commissioning, improvements in commissioning management have been achieved through the use of computer systems, and testing methods have also been upgraded by the development of computer systems for the recording and analysis of test data and the automatic adjustment of controllers in the main control system of the BWR. This paper outlines these construction techniques and management methods. (author)

  9. Paired replacement fuel assemblies for BWR-type reactor

    International Nuclear Information System (INIS)

    Oguchi, Kazushige.

    1997-01-01

    There are disposed a large-diameter water rod constituting a non-boiling region at a central portion and paired replacement fuel assemblies for two streams having the same average enrichment degree and different amount of burnable poisons. The paired replacement fuel assemblies comprise a first fuel assembly having a less amount of burnable poisons and a second fuel assembly having a larger amount of burnable poisons. A number of burnable poison-containing fuel rods in adjacent with the large diameter water rod is increased in the second fuel assembly than the first fuel assembly. Then, the poison of the paired replacement fuel assemblies for the BWR type reactor can be annihilated simultaneously at the final stage of the cycle. Accordingly, fuels for a BWR type reactor excellent in economical property and safety and facilitating the design of the replacement reactor core can be obtained. (N.H.)

  10. Potencial y plan exportador agua mineral BE

    OpenAIRE

    López Rodríguez, Diana Carolina; Rojas Isaza, Alejandro

    2012-01-01

    Agua Mineral BE Ltda es una empresa dedicada a la extracción, embotellado y comercialización de agua mineral colombiana, originada en las cordilleras de los Andes. Se caracteriza por ser de alta pureza y ser una bebida funcional, que trae beneficios adicionales a la salud por su composición de minerales, oligoelementos y electrolitos. Las condiciones de la empresa resultaron ser muy atractivas para desarrollar una investigación, por otro lado, el dueño y gerente general mostro gran interés en...

  11. TLTA/6431, Two-Loop-Test-Apparatus, BWR/6 Simulator, Small-Break LOCA

    International Nuclear Information System (INIS)

    1992-01-01

    1 - Description of test facility: The Two-Loop-Test-Apparatus (TLTA) is a 1:624 volume scaled BWR/6 simulator. It was the predecessor of the better-scaled FIST facility. The facility is capable of full BWR system pressure and has a simulated core with a full size 8 x 8, full power single bundle of indirect electrically heated rods. All major BWR systems are simulated including lower plenum, guide tube, core region (bundle and bypass), upper plenum, steam separator, steam dome, annular downcomer, recirculation loops and ECC injection systems. The fundamental scaling consideration was to achieve real-time response. A number of the scaling compromises present in TLTA were corrected in the FIST configuration. These compromises include a number of regional volumes and component elevations. 2 - Description of test: 64.45 sqcm small break LOCA with activation of the full emergency core cooling system, but without activation of the automatic decompression system

  12. Thermohydraulic stability coupled to the neutronic in a BWR

    International Nuclear Information System (INIS)

    Calleros M, G.; Zapata Y, M.; Gomez H, R.A.; Mendez M, A.; Castlllo D, R.

    2006-01-01

    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 Laguna Verde

  13. BWR and PWR chemistry operating experience and perspectives

    International Nuclear Information System (INIS)

    Fruzzetti, K.; Garcia, S.; Lynch, N.; Reid, R.

    2014-01-01

    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)

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

    International Nuclear Information System (INIS)

    1981-08-01

    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

  15. Repair and preventive maintenance technology for BWR reactor internals and piping

    International Nuclear Information System (INIS)

    Ootsubo, Tooru; Itou, Takashi; Sakashita, Akihiro

    2009-01-01

    Stress corrosion cracking of welding portion has found in many domestic and foreign BWR reactor internals and Primary Loop Recirculation piping. Also, repair and preventive maintenance technologies for SCC has been developed and/or adopted to BWRs in recent years. This paper introduces the sample of these technologies, such as seal-welding for SCC on BWR reactor internals, preventive maintenance technology for PLR piping such as Corrosion Resistant Cladding, Internal Polishing and Induction Heating Stress Improvement. These technologies are introduced on 'E-Journal of Advanced Maintenance', which is an international journal on a exclusive website of Japan Society of Maintenology. (author)

  16. 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.

  17. BWR type reactors

    International Nuclear Information System (INIS)

    Yano, Ryoichi; Sato, Takashi; Osaki, Masahiko; Hirayama, Fumio; Watabe, Atsushi.

    1980-01-01

    Purpose: To effectively eliminate radioactive substances released upon loss of coolant accidents in BWR type reactors. Constitution: A high pressure gas jetting device having a plurality of small aperture nozzles is provided above a spray nozzle, that is, at the top of a dry well. The jetting device is connected to a vacuum breaker provided in a pressure suppression chamber. Upon loss of coolant accident, coolants are sprayed from the spray nozzle and air or nitrogen is jetted from the gas jetting device as well. Then, the gases in the dry well are disturbed, whereby radioactive iodine at high concentration liable to be accumulated in the dry well is forced downwardly, dissolved in the spray water and eliminated. (Ikeda, J.)

  18. Initiation model for intergranular stress corrosion cracking in BWR pipes

    International Nuclear Information System (INIS)

    Hishida, Mamoru; Kawakubo, Takashi; Nakagawa, Yuji; Arii, Mitsuru.

    1981-01-01

    Discussions were made on the keys of intergranular stress corrosion cracking of austenitic stainless steel in high-temperature water in laboratories and stress corrosion cracking incidents in operating plants. Based on these discussions, a model was set up of intergranular stress corrosion cracking initiation in BWR pipes. Regarding the model, it was presumed that the intergranular stress corrosion cracking initiates during start up periods whenever heat-affected zones in welded pipes are highly sensitized and suffer dynamic strain in transient water containing dissolved oxygen. A series of BWR start up simulation tests were made by using a flowing autoclave system with slow strain rate test equipment. Validity of the model was confirmed through the test results. (author)

  19. 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

  20. 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.

  1. Agua: la importancia de una ingesta adecuada en pediatría

    OpenAIRE

    JL Arredondo-García; A Méndez-Herrera; H Medina-Cortina; C Pimentel- Hernández

    2017-01-01

    El agua es el componente más abundante del cuerpo humano, que por sí mismo es incapaz de producirla en cantidades suficientes para satisfacer sus necesidades; por eso es vital consumir una cantidad adecuada para mantener la homeostasis. A pesar de que el agua es indispensable para la vida hay gran desconocimiento de los profesionales de la salud sobre el metabolismo de agua y las recomendaciones sobre la ingesta adecuada para una alimentación saludable. Se ha comprobado que los niños consumen...

  2. Validation and application of the system code ATHLET-CD for BWR severe accident analyses

    Energy Technology Data Exchange (ETDEWEB)

    Di Marcello, Valentino, E-mail: valentino.marcello@kit.edu; Imke, Uwe; Sanchez, Victor

    2016-10-15

    Highlights: • We present the application of the system code ATHLET-CD code for BWR safety analyses. • Validation of core in-vessel models is performed based on KIT CORA experiments. • A SB-LOCA scenario is simulated on a generic German BWR plant up to vessel failure. • Different core reflooding possibilities are investigated to mitigate the accident consequences. • ATHLET-CD modelling features reflect the current state of the art of severe accident codes. - Abstract: This paper is aimed at the validation and application of the system code ATHLET-CD for the simulation of severe accident phenomena in Boiling Water Reactors (BWR). The corresponding models for core degradation behaviour e.g., oxidation, melting and relocation of core structural components are validated against experimental data available from the CORA-16 and -17 bundle tests. Model weaknesses are discussed along with needs for further code improvements. With the validated ATHLET-CD code, calculations are performed to assess the code capabilities for the prediction of in-vessel late phase core behaviour and reflooding of damaged fuel rods. For this purpose, a small break LOCA scenario for a generic German BWR with postulated multiple failures of the safety systems was selected. In the analysis, accident management measures represented by cold water injection into the damaged reactor core are addressed to investigate the efficacy in avoiding or delaying the failure of the reactor pressure vessel. Results show that ATHLET-CD is applicable to the description of BWR plant behaviour with reliable physical models and numerical methods adopted for the description of key in-vessel phenomena.

  3. Boiling transition phenomenon in BWR fuel assemblies effect of fuel spacer shape on critical power

    International Nuclear Information System (INIS)

    Yamamoto, Yasushi; Morooka, Shin-ichi; Mitsutake, Toru; Yokobori, Seiichi; Kimura, Jiro.

    1996-01-01

    A thorough understanding of the thermal-hydraulic phenomena near fuel spacer is necessary for the accurate prediction of the critical power of BWR fuel assemblies, and is thus essential for effective developments of a new BWR fuel assembly. The main purpose of this study is to develop an accurate method for predicting the effect of spacer shapes on critical power. Tests have been conducted under actual BWR operating conditions, using an annulus flow channel consisting of a heated rod and circular-tube channel, and BWR simulated 4x4 rod bundles with heater rods unheated just upsteam of spacer. The effect of spacer shapes on critical power was predicted analytically based on the droplet deposition rate estimation. The droplet deposition rate for different spacer shapes was calculated using a single-phase flow model. The prediction results were compared with the test results for the annulus flow channel using ring-type spacers. Analytical results of critical power agreed with measured critical power from point of the effects of changes in the rod-spacer clearance and the spacer thickness on critical power. (author)

  4. Prediction of BWR performance under the influence of Isolation Condenser-using RAMONA-4 code

    International Nuclear Information System (INIS)

    Khan, H.J.; Cheng, H.S.; Rohatgi, U.S.

    1992-01-01

    The purpose of the Boiling Water Reactor (BWR) Isolation Condenser (IC) is to passively control the reactor pressure by removing heat from the system. This type of control is expected to reduce the frequency of opening and closing of the Safety Relief Valves (SRV). A comparative analysis is done for a BWR operating with and without the influence of an IC under Main Steam Isolation Valve (MSIV) closure. A regular BWR, with forced flow and high thermal power, has been considered for analysis. In addition, the effect of ICs on the BWR performance is studied for natural convection flow at lower power and modified riser geometry. The IC is coupled to the steam dome for the steam inlet flow and the Reactor Pressure Vessel (RPV) near the feed water entrance for the condensate return flow. Transient calculations are performed using prescribed pressure set points for the SRVs and given time settings for MSIV closure. The effect of the IC on the forced flow is to reduce the rate of pressure rise and thereby decrease the cycling frequency ofthe SRVS. This is the primary objective of any operating IC in a BWR (e.g. Oyster Creek). The response of the reactor thermal and fission power, steam flow rate, collapsed liquid level, and core average void fraction are found to agree with the trend of pressure. The variations in the case of an active IC can be closely related to the creation of a time lag and changes in the cycling frequency of the SRVS. An analysis for natural convection flow in a BWR indicates that the effect of an IC on its transient performance is similar to that for the forced convection system. In this case, the MSIV closure, has resulted in a lower peak pressure due to the magnitude of reduced power. However, the effect of reduced cycling frequency of the SRV due to the IC, and the time lag between the events, are comparable to that for forced convection

  5. Subchannel analysis of a critical power test, using simulated BWR 8x8 fuel assembly

    International Nuclear Information System (INIS)

    Mitsutake, T.; Terasaka, H.; Yoshimura, K.; Oishi, M.; Inoue, A.; Akiyama, M.

    1990-01-01

    Critical power predictions have been compared with the critical power test data obtained in simulated BWR 8x8 fuel rod assemblies. Two analytical methods for the critical power prediction in rod assemblies are used in the prediction, which are the subchannel analysis using the COBRA/BWR subchannel computer code with empirical critical heat flux (CHF) correlations and the liquid film dryout estimation using the CRIPP-3F 'multi-fluid' computer code. Improvements in both the analytical methods were made for spacer effect modeling, though they were specific for application to the current BWR rod assembly type. In general a reasonable agreement was obtained, though comparisons, between the prediction and the obtained test data. (orig.)

  6. El agua subterránea en la Costa de Hermosillo

    OpenAIRE

    José Luis Moreno Vázquez

    2000-01-01

    En este trabajo se analiza el papel que desempeñó la evolución del conocimiento científico en materia de agua subterránea en el desarrollo de una región agrícola del noroeste del país. En la introducción, se aborda el contexto económico y la visión dominante que existía sobre la disponibilidad y aprovechamiento del agua que hicieron posible el nacimiento de la Costa de Hermosillo a mediados de los años 40. En el primer apartado, se describe el conocimiento que había sobre el agua del subsuelo...

  7. Propuesta de un sistema de aprovechamiento de agua lluvia como alternativa para el ahorro de agua potable, en la institución educativa María Auxiliadora de Caldas, Antioquia

    Directory of Open Access Journals (Sweden)

    Palacio Castañeda Natalia

    2011-11-01

    Full Text Available El aprovechamiento del agua lluvia es una práctica interesante, tanto ambiental como económicamente, si se tiene en cuenta la gran demanda del recurso sobre las cuencas hidrográficas, el alto grado de contaminación de las fuentes superficiales y los elevados costos por el consumo de agua potable en una institución educativa. Este proyecto presenta la ingeniería conceptual de una propuesta de diseño de un si stema de aprovechamiento de agua lluvia como alternativa para el ahorro de agua potable en usos tales como la descarga de sanitarios, el lavado de zonas comunes, entre otros. Se presenta, adicionalmente, un análisis aproximado de la viabilidad técnica y económica de dicho aprovechamiento en una institución educativa del municipio de Caldas, Antioquia. Se desarrollan en este documento tres aspectos principales: el cálculo de los volúmenes disponibles de agua lluvia en la zona, la evaluación del volumen de agua potable ahorrado con el aprovechamiento del agua lluvia, la estimación del presupuesto para la construcción del sistema y la proyección del ahorro generado al utilizarlo. Los resultados sugieren que el aprovechamiento de agua lluvia es una opción técnicamente viable, pero financieramente no, pues la inversión inicial es alta, por lo que es importante buscar financiación externa para desarrollar este tipo de proyectos que representan una solución interesante para contribuir al desarrollo sostenible de la institución educativa.

  8. Cuento: Agua rota

    Directory of Open Access Journals (Sweden)

    José Puben

    1966-04-01

    Full Text Available Ya avanzada la noche la lluvia empezó a caer, clara y sonora, en el empedrado del patio y sobre los amplios techos de la vieja casa. El ruido del aguacero lo despertó de un profundo sueño. La sensación de que la cañada aumentaba, a cada momento, venía del atronador y permanente cauce de las aguas vecinas.

  9. 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...

  10. The impact of BWR MK I primary containment failure dynamics on secondary containment integrity

    International Nuclear Information System (INIS)

    Greene, S.R.

    1987-01-01

    During the past four years, the ORNL BWRSAT Program has developed a series of increasingly sophisticated BWR secondary containment models. These models have been applied in a variety of studies to evaluate the severe accident mitigation capability of BWR secondary containments. This paper describes the results of a recent ORNL study of the impact of BWR MK I primary containment failure dynamics on secondary containment integrity. A 26-cell MELCOR Browns Ferry secondary containment model is described and the predicted thermodynamic response of the secondary containment to a variety of postulated primary containment failure modes is presented. The effects of primary containment failure location, timing, and ultimate hole size on secondary containment response is investigated, and the potential impact of hydrogen deflagrations on secondary containment integrity is explored

  11. SISTEMA DE ELECTROCOAGULACIÓN COMO TRATAMIENTO DE AGUAS RESIDUALES GALVÁNICAS

    OpenAIRE

    Nelly Bibiana Morales Posada; Gema Eunice Acosta Niño

    2010-01-01

    El presente artículo muestra la segunda fase del proyecto "Implementación y evaluación de un sistema piloto de electrocoagulación como tratamiento de aguas residuales con fines de reuso. Estudio de caso: aguas residuales industriales de origen galvánico". Para su desarrollo, se valoró y optimizó un prototipo existente en la Universidad, a partir de ensayos realizados en aguas residuales con contenido de metales, implementando un porcentaje mayor al 47% para la remoción de metales pesados como...

  12. Gestión y Mantenimiento de las Instalaciones Prediales de Aguas

    OpenAIRE

    Moreira, Madalena; Pinheiro-Alves, Teresa; Mourato, Sandra

    2013-01-01

    Terminada la fase de construcción de un edificio se pasa a la fase de exploración y utilización del edificio lo que obliga a cuidados adicionales que se encuadran en un sistema de gestión y mantenimiento de las partes constituyentes del edificio y que debe ser resultado de una planificación bien estructurada en fase de proyecto. La gestión y mantenimiento del edificio dependen de las soluciones de proyecto. Las instalaciones de abastecimiento de agua y de drenaje de aguas residuales y de agua...

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

    Directory of Open Access Journals (Sweden)

    Silva Jorge

    2008-08-01

    Full Text Available

    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 América Latina, en general, generan riesgos en la salud pública, en especial cuando se utilizan para riego de cultivos para consumo directo. Para el reuso de aguas residuales se aconseja realizar siempre un tratamiento preliminar y primario; el tratamiento secundario, además de remover de manera eficiente materia orgánica y sólidos suspendidos, influye directamente sobre la estructura de algunos compuestos, como los de nitrógeno, siendo importante tener en cuenta los requerimientos del cultivo a irrigar y el tipo de suelo. Este artículo propone el uso de aguas residuales domésticas como un recurso alternativo, siempre que se traten y manejen apropiadamente para hacerlo de manera segura en actividades agrícolas, privilegiando el riego de cultivos que sufrirán una transformación industrial posterior.

  14. BWR internals life assurance

    International Nuclear Information System (INIS)

    Herrera, M.L.; Stancavage, P.P.

    1988-01-01

    Boiling water reactor (BWR) internal components play an important role in power plant life extension. Many important internals were not designed for easy removal and changes in material properties and local environmental effects due to high radiation makes stress corrosion cracking more likely and more difficult to correct. Over the past several years, operating experience has shown that inspection, monitoring and refurbishment can be accomplished for internal structures with existing technology. In addition, mitigation techniques which address the causes of degradation are available to assure that life extension targets can be met. This paper describes the many considerations and aspects when evaluating life extension for reactor vessel internals

  15. 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)

  16. Parásitos en aguas del arroyo Naposta, aguas de recreación y de consumo en la ciudad de Bahia Blanca (Provincia de Buenos Aires, Argentina)

    OpenAIRE

    COSTAMAGNA, SIXTO RAÚL; VISCIARELLI, ELENA; LUCCHI, LEANDRO D; BASUALDO, JUAN A

    2005-01-01

    El objetivo del presente trabajo fue detectar la presencia de parásitos de importancia sanitaria para el hombre, en el arroyo Napostá, en aguas recreacionales (piscinas públicas) y de consumo en Bahía Blanca (Provincia de Buenos Aires) Argentina. Se recolectaron 24.000 litros de agua de diferentes sectores del arroyo Napostá, 2.000 litros de cada una de las tres piscinas públicas y 8.000 litros de agua de consumo, mediante filtros de poro de una micra de diámetro (Cuno Micro Wind). El procesa...

  17. Eulerian fluid-structure analysis of BWR

    International Nuclear Information System (INIS)

    McMaster, W.H.

    1979-05-01

    A fluid-structure-interaction algorithm is developed for the analysis of the dynamic response of a BWR pressure-suppression pool and containment structure. The method is incorporated into a two-dimensional semi-implicit Eulerian hydrodynamics code, PELE-IC, for the solution of incompressible flow coupled to flexible structures. The fluid, structure, and coupling algorithms have been verified by calculation of solved problems from the literature and by comparison with air and steam blowdown experiments

  18. ZZ BWRSB-RINGHALS1, Stability Benchmark Data from BWR RINGHALS-1

    International Nuclear Information System (INIS)

    2002-01-01

    Description of program or function: The purpose of this benchmark is to enable code developers to test their codes and also to validate the predictive capability of their respective codes and models for BWR stability analysis. Emphasis is put on the modelling of flow dynamics of the reactor core and in-vessel flow loop wit detailed neutronic and thermodynamic feedback. The secondary systems as well as the control and production systems will be neglected. Data provided comes from measurements in beginning of cycle (BOC) 14, 15, 16 and 17 and middle of cycle (MOC) 16 in the Swedish BWR reactor Ringhals 1. For these measurements complete data sets are given

  19. BWR Fuel Assemblies Physics Analysis Utilizing 3D MCNP Modeling

    International Nuclear Information System (INIS)

    Chiang, Ren-Tai; Williams, John B.; Folk, Ken S.

    2008-01-01

    MCNP is used to model a partially controlled BWR fresh fuel four assemblies (2x2) system for better understanding BWR fuel behavior and for benchmarking production codes. The impact of the GE14 plenum regions on axial power distribution is observed by comparing against the GE13 axial power distribution, in which the GE14 relative power is lower than the GE13 relative power at the 15. node and at the 16. node due to presence of the plenum regions in GE14 fuel in these two nodes. The segmented rod power distribution study indicates that the azimuthally dependent power distribution is very significant for the fuel rods next to the water gap in the uncontrolled portion. (authors)

  20. BWR Fuel Assemblies Physics Analysis Utilizing 3D MCNP Modeling

    Energy Technology Data Exchange (ETDEWEB)

    Chiang, Ren-Tai [University of Florida, Gainesville, Florida 32611 (United States); Williams, John B.; Folk, Ken S. [Southern Nuclear Company, Birmingham, Alabama 35242 (United States)

    2008-07-01

    MCNP is used to model a partially controlled BWR fresh fuel four assemblies (2x2) system for better understanding BWR fuel behavior and for benchmarking production codes. The impact of the GE14 plenum regions on axial power distribution is observed by comparing against the GE13 axial power distribution, in which the GE14 relative power is lower than the GE13 relative power at the 15. node and at the 16. node due to presence of the plenum regions in GE14 fuel in these two nodes. The segmented rod power distribution study indicates that the azimuthally dependent power distribution is very significant for the fuel rods next to the water gap in the uncontrolled portion. (authors)

  1. Product Evaluation Task Force Phase Two report for BWR/PWR dissolver wastes

    International Nuclear Information System (INIS)

    Francis, A.J.

    1990-01-01

    It has been proposed that all Intermediate Level Wastes arising at Sellafield should be encapsulated prior to ultimate disposal. The Product Evaluation Task Force (PETF) was set up to investigate possible encapsulants and to produce an adequate data base to justify the preferred matrices. This report details the work carried out, under Phase 2 of the Product Evaluation Task Force programme, on BWR/PWR Dissolver Wastes. Three possible types of encapsulants for BWR/PWR Dissolver Wastes:- Inorganic cements, Polymer cements and Polymers are evaluated using the Kepner Tregoe decision analysis technique. This technique provides a methodology for scoring and ranking alternative options and evaluating any risks associated with an option. The analysis shows that for all four stages of waste management operations ie Storage, Transport, handling and emplacement, Disposal and Process, cement matrices are considerably superior to other potential matrices. A matrix, consisting of three parts Blast Furnace Slag (BFS) to one part Ordinary Portland Cement (OPC), is recommended for Phase 3 studies on BWR/PWR Dissolver Wastes. (author)

  2. 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.

  3. 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...

  4. 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...

  5. 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)

  6. 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)

  7. Las aguas termominerales de Tabio

    Directory of Open Access Journals (Sweden)

    Antonio María Barriga Villalba

    1933-01-01

    Full Text Available La pintoresca población de Tabio, situada en el vallecito que forman dos repliegues de la gran cordillera montañosa que rodea la sabana de Bogotá, es un pueblecito apacible, famoso desde tiempo inmemorial por las aguas termales que brotan en la falda de los cerros situados al occidente, a unos mil metros de la iglesia de la población, en terrenos de propiedad del doctor Pompilio Martínez. Fue fundada Tabio en el año 1761 (*. Se halla a 4°50'50" de latitud norte y 0° 04'00" de longitud del meridiano de Bogotá. Clima seco en la mayor parte del año, temperatura media 14°.5 C. Presión atmosférica 560 mm.; altura sobre el nivel del mar 2.650 metros; temperatura de. ebullición del agua 91°.62 C.; humedad en vapor de agua, por metro cúbico, en los días secos 127,5 gramos por metro cúbico; en los días húmedos, 251,8 gramos por metro cúbico. En el sitio de las fuentes la humedad relativa media es de 38.38 por 100 y la temperatura de la atmósfera varía de 10° C. hasta 23°C.; en los días de sol, hacia las doce del día, la temperatura de la atmósfera cerca de las fuentes es de 20°-22°C.

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

    OpenAIRE

    Damarys Santana Diaz

    2011-01-01

    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 ...

  9. El agua subterránea en la Costa de Hermosillo

    Directory of Open Access Journals (Sweden)

    José Luis Moreno Vázquez

    2000-01-01

    Full Text Available En este trabajo se analiza el papel que desempeñó la evolución del conocimiento científico en materia de agua subterránea en el desarrollo de una región agrícola del noroeste del país. En la introducción, se aborda el contexto económico y la visión dominante que existía sobre la disponibilidad y aprovechamiento del agua que hicieron posible el nacimiento de la Costa de Hermosillo a mediados de los años 40. En el primer apartado, se describe el conocimiento que había sobre el agua del subsuelo en ciertas zonas del país y del estado de Sonora antes de dicho nacimiento. En el segundo, se muestran las diferentes estimaciones realizadas acerca del potencial de agua subterránea a nivel nacional y estatal, así como los métodos empleados para tal efecto. En el tercer apartado, se discuten las diversas estimaciones efectuadas sobre la recarga natural del acuífero de la Costa a lo largo de la década de los años 60. Por último, en el cuarto se ofrece un resumen de las conclusiones derivadas de este análisis y los riesgos de la falta de conocimiento actualizado sobre este acuífero ante la posible puesta en práctica de nuevos proyectos de aprovechamiento de agua.

  10. Figuras, usos y valores del agua en Bogotá

    Directory of Open Access Journals (Sweden)

    José Manuel Jaramillo Giraldo

    2003-01-01

    Full Text Available El uso del agua representa un factor central del proceso de urbanización de las sociedades. Involucra limitaciones a las nociones dominantes de orden, limpieza, higiene, y organización que operan sobre el espacio, el comportamiento individual, las prácticas sociales y la valoración que construimos sobre estos. En ciudades como Bogotá, cuyo crecimiento urbano espontáneo alcanzó casi a la mitad del total de viviendas levantadas durante la segunda mitad del siglo XX, el agua, como las redes clandestinas de servicios, reflejan as Bogota, una forma de apropiación e integración al espacio social, que revela el conflicto entre la ciudad formal o establecida y la ciudad marginal. Palabras clave: Urbanización v abastecimiento services, reflecrs a wav of appropnation and de agua

  11. Analisis de PPcPs (pharmaceutical and personal care products en aguas residuales y suelos

    Directory of Open Access Journals (Sweden)

    Johana Andrea Velásquez Arias

    2016-12-01

    Full Text Available Los productos farmacéuticos y de higiene personal (PPcPs son conocidos como contaminantes emergentes,  ampliamente usados  por la sociedad  moderna. Las estaciones depuradoras de aguas residuales (EDAR, mitigan la presencia de estos contaminantes emergentes en los efluentes que vierten al medio ambiente. La eficiencia de eliminación de las EDAR, varían en base a la precisión en la detección y en las técnicas utilizadas. Este estudio revisó literatura para estudios que informaron sobre la presencia de PPcPs en aguas, estaciones depuradoras de aguas residuales y suelos, las técnicas biológicas degradadoras utilizadas y la frecuencia de evaluaciones ecotoxicológicas. Tras la búsqueda bibliográfica, se obtuvieron 119 artículos relacionados con la presencia PPcPs en suelos y aguas, de los cuales el 7% son revisiones que incluyen datos de degradación por estrategias de biorremediación, técnicas físico-químicas, acumulación de PPcPs en aguas y plantas y efectos en los organismos, el 40% se centran en aguas superficiales y estaciones depuradoras de aguas residuales, el 28% en suelos irrigados con aguas residuales recuperadas o abonados con lodos de depuradoras y por último, solamente el 22% realizaron ensayos ecotoxicológicos en aguas y el 3% en suelos. A partir de estos resultados se puede concluir que, es necesario hacer énfasis en la realización de estudios sobre comunidades bacterianas con capacidad degradadora de PPcPS, así como la incorporación de ensayos ecotoxicológicos que confirmen la optimización del proceso.

  12. Separación de mezclas agua-propanol usando membranas de preevaporación PDMS

    Directory of Open Access Journals (Sweden)

    Mahacine Amrani

    2008-05-01

    Full Text Available La recuperación y purificación de disolventes orgánicos en la química farmacéutica resulta de gran importancia pa-ra la economía y el medio ambiente. La separación de mezclas de agua/alcohol por el proceso de pervaporación se llevó a cabo a través de membranas hidrofóbicas. En este trabajo se estudia el rendimiento de las membranas de polidimetilsiloxano (PDMS para la deshidratación de mezclas agua/propanol por el proceso de preevaporación. El PDMS es reconocido por su selectividad de permeabilidad al alcohol preferentemente en mezclas de agua/alcohol durante el preevaporación debido a su tamaño molecular, aunque aún se presente penetración de agua a través de la membrana hidrofóbica. Se utilizó una unidad de preevaporación a escala de laboratorio para el estudio de esta membrana de separación evaluando características en términos de pervaporación como el flujo y la selectivi-dad de los canales con un contenido máximo de masa de agua y de 30 °C a 50 °C. El flujo de propanol/agua fue observado al variar la temperatura. A pesar que el PDMS presentó buenas características para la separación de mezclas de agua/propanol, el factor de separación y el flujo de pervaporación disminuyen a medida que el contenido de agua en la carga aumenta. La membrana PDMS resultó ser muy eficiente para concentraciones de a-gua de menos de 0.3, lo que corresponde al total del flujo de transferencia máxima.

  13. Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

    Energy Technology Data Exchange (ETDEWEB)

    Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

    1963-10-15

    . Constituye el primer programa de este genero que se haya llevado a la practica. Para reunir los datos buscados, fue preciso idear muchas tecnicas de instrumentacion nuevas. Se logro el proposito perseguido y se obtuvieron copiosos datos nuevos acerca del rendimiento de un reactor de agua hirviente con circulacion natural. Este programa permitio obtener indicaciones sobre los siguientes puntos: caudales de recirculacion, limites de separacion entre vapor y liquido (arrastre de vapor en el tubo de descenso y arrastre de liquido por el vapor efluente), subenfriamiento, posicion de la interfase real en el reactor y su relacion con el nivel de la columna de agua, coeficientes de condensacion del vapor en el tubo de descenso, coeficientes de cavitacion, antirreactividad del H{sub 3}BO{sub 3}, coeficientes de temperatura, utilizacion de cintas de boro para la regulacion, empleo de elementos combustibles enriquecidos, funciones de transferencia, analisis de los ruidos, algunas mediciones de flujos, estabilidad, etc. Ademas se obtuvieron datos sobre el comportamiento y el estado de ciertas partes y circuitos del reactor, tales como el sistema de control de acido borico, los niveles de radiacion, la distribucion de los productos de corrosion, los defectos funcionales de ciertos equipos, las barras de combustible y de control, etc. Se comprobo que el rendimiento del EBWR depende casi exclusivamente del arrastre de vapor en el tubo de descenso, del arrastre de liquido por el vapor efluente e, indirectamente, de la posicion de la interfase real en el recipiente. En el intervalo de bajas potencias, el factor preponderante es el arrastre de vapor en el tubo de descenso. Al superar los 65 MW, el rendimiento del reactor cambio radicalmente. La velocidad de desprendimiento del vapor alcanzo a 33 cm/s, y la altura de la cupula de vapor se redujo a im. En estas condiciones se registro un arrastre de liquido que se intensifico rapidamente al aumentar la potencia desarrollada. El reactor deja

  14. Organización comunitaria y sustentabilidad del agua

    OpenAIRE

    Sandoval Moreno, Adriana; Universidad Nacional Autonoma de Mexico

    2015-01-01

    Mediante el método cualitativo se analiza cómo las organizaciones comunitarias para el riego y para el consumo humano del agua hacen frente a la problemática de la sustentabilidad de este recurso en la región Lerma-Chapala de Michoacán, México. Los resultados muestran, por un lado, que las organizaciones se basan en arreglos consuetudinarios, buscan la distribución equitativa del agua y tienen una función de control sobre esta en forma de autogestión, con recursos propios, capacidades, sabere...

  15. Prevention of organic iodide formation in BWR's

    International Nuclear Information System (INIS)

    Karjunen, T.; Laitinen, T.; Piippo, J.; Sirkiae, P.

    1996-01-01

    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

  16. 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.

  17. Prony's method application for BWR instabilities characterization

    International Nuclear Information System (INIS)

    Castillo, Rogelio; Ramírez, J. Ramón; Alonso, Gustavo; Ortiz-Villafuerte, Javier

    2015-01-01

    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

  18. 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)

  19. La piedra de agua

    OpenAIRE

    Ricaurte Aguirre, Lina Marcela

    2013-01-01

    En un tiempo en el que los humanos abren su corazón a la enfermedad, Suyana, una adolescente rebelde en una antigua comunidad indígena de la selva, descubre una mágica piedra de agua que la vincula con unos graciosos espíritus, quienes la guiarán para despertar su verdadera identidad y sanar a su pueblo.

  20. Dimensionamiento del sistema de tratamiento de aguas residuales industriales en la industria de la pintura

    OpenAIRE

    Guevara Gavilanes, Silvia; Parrales Baquerizo, Narcisa; Villamar Bajaña, Franklin

    2009-01-01

    Las aguas residuales en la Industria de la pintura son el conjunto de las aguas que son contaminadas durante su empleo en actividades de limpieza realizadas en el proceso de elaboración de las pinturas acuosas. Para reparar esta alteración a la naturaleza aplicaremos sistemas de tratamientos de aguas donde se realiza distintos procesos necesarios para poder llegar al estado inicial del agua sin contaminación, los sistemas de tratamiento no hacen otra cosa que separar todos los contaminante...

  1. BWR-stability investigation at Forsmark 1

    International Nuclear Information System (INIS)

    Bergdahl, B.G.; Reisch, F.; Oguma, R.; Lorenzen, J.; Aakerhielm, F.

    1988-01-01

    A series of noise measurements have been conducted at Forsmark 1 during start-up operation after the revision summer '87. The main purpose was to investigate BWR-stability problems, i.e. resonant power oscillations of 0.5 Hz around 65% power and 4100 kg/s core flow, which tend to arise at high power and low core flow conditions. The analysis was performed to estimate the noise source which gives rise to the oscillation, to evaluate the measure of stability, i.e. the Decay Ratio (Dr) as well as to investigate other safety related problems. The result indicates that the oscillation is due to the dynamic coupling between the neutron kinetics and thermal hydraulics via void reactivity feedback. The Dr ranged between values of 0.7 and > 0.9, instead of expected 0.6 (Dr=1 is defined as instability). These high values imply that the core cannot suppress oscillations fast enough and a small perturbation can cause scram. Further it was found that the entire core is oscillating in phase (LPRM's) with varying strength where any connection to the consequences of different fuel (8x8, 9x9) being present simultaneously cannot be excluded. This report elucidates the importance of an on-line BWR-stability surveillance system with functions like stability condition monitoring and control system diagnosis. (orig.)

  2. Identification and assessment of BWR in-vessel severe accident mitigation strategies

    Energy Technology Data Exchange (ETDEWEB)

    Hodge, S.A.; Cleveland, J.C.; Kress, T.S.; Petek, M. [Oak Ridge National Lab., TN (United States)

    1992-10-01

    This report provides the results of work carried out in support of the US Nuclear Regulatory Commission Accident Management Research Program to develop a technical basis for evaluating the effectiveness and feasibility of current and proposed strategies for boiling water reactor (BWR) severe accident management. First, the findings of an assessment of the current status of accident management strategies for the mitigation of in-vessel events for BWR severe accident sequences are described. This includes a review of the BWR Owners` Group Emergency Procedure Guidelines (EPGSs) to determine the extent to which they currently address the characteristic events of an unmitigated severe accident and to provide the basis for recommendations for enhancement of accident management procedures. Second, where considered necessary, new candidate accident management strategies are proposed for mitigation of the late-phase (after core damage has occurred) events. Finally, recommendations are made for consideration of additional strategies where warranted, and two of the four candidate strategies identified by this effort are assessed in detail: (1) preparation of a boron solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and (2) containment flooding to maintain the core debris within the reactor vessel if the injection systems cannot be restored.

  3. Identification and assessment of BWR in-vessel severe accident mitigation strategies

    International Nuclear Information System (INIS)

    Hodge, S.A.; Cleveland, J.C.; Kress, T.S.; Petek, M.

    1992-10-01

    This report provides the results of work carried out in support of the US Nuclear Regulatory Commission Accident Management Research Program to develop a technical basis for evaluating the effectiveness and feasibility of current and proposed strategies for boiling water reactor (BWR) severe accident management. First, the findings of an assessment of the current status of accident management strategies for the mitigation of in-vessel events for BWR severe accident sequences are described. This includes a review of the BWR Owners' Group Emergency Procedure Guidelines (EPGSs) to determine the extent to which they currently address the characteristic events of an unmitigated severe accident and to provide the basis for recommendations for enhancement of accident management procedures. Second, where considered necessary, new candidate accident management strategies are proposed for mitigation of the late-phase (after core damage has occurred) events. Finally, recommendations are made for consideration of additional strategies where warranted, and two of the four candidate strategies identified by this effort are assessed in detail: (1) preparation of a boron solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and (2) containment flooding to maintain the core debris within the reactor vessel if the injection systems cannot be restored

  4. BWR 9 X 9 Fuel Assembly Thermal-Hydraulic Tests (2): Hydraulic Vibration Test

    International Nuclear Information System (INIS)

    Yoshiaki Tsukuda; Katsuichiro Kamimura; Toshiitsu Hattori; Akira Tanabe; Noboru Saito; Masahiko Warashina; Yuji Nishino

    2002-01-01

    Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8 x 8 and 9 x 9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part of the NUPEC thermal-hydraulic projects, hydraulic vibration tests using full-scale test assemblies simulating 9 x 9 fuel assemblies were carried out to evaluate BWR fuel integrity. The test data were applied to development of a new correlation for the estimation of fuel rod vibration amplitude. (authors)

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

    International Nuclear Information System (INIS)

    1992-09-01

    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

  6. BWR power oscillation evaluation methodologies in core design

    International Nuclear Information System (INIS)

    Hotta, Akitoshi

    1995-01-01

    At the initial stage of BWR development, the power oscillation due to the nuclear-thermal interaction originated in random boiling phenomena and nuclear void feedback was feared. But it was shown that under the high pressure condition in the normal operation of recent commercial BWRs, the core is in very stable state. However, power oscillation events have been observed in actual machines, and it is necessary to do the stability evaluation that sufficiently reflects the detailed operation conditions of actual plants. As the cause of power oscillation events, the instability of control system and nuclear-thermal coupling instability are important, and their mechanisms are explained. As the model for analyzing the stability of BWR core, the nuclear-thermal coupling model in frequency domain is the central existence. As the information for the design, the parameters of fuel assemblies, and the nuclear parameters and the thermohydraulic parameters of cores are enumerated. LAPUR-TSI is a nuclear-thermal coupling model. The analysis system in the software of Tokyo Electric Power Co. is outlined, and the analysis model was verified. (K.I.)

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

    International Nuclear Information System (INIS)

    1992-09-01

    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. Gobernanza del agua residual en Aguascalientes: captura regulatoria y arreglos institucionales complejos

    OpenAIRE

    Raul Pacheco-Vega

    2015-01-01

    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 de...

  9. Representación social del agua y de sus usos

    Directory of Open Access Journals (Sweden)

    Oscar E. Navarro

    2004-01-01

    Full Text Available El agua es actualmente una cuestión política y geoestratégica de gran importancia mundial. Colombia, una de las potencias hídricas del mundo, abastece solamente la mitad de sus habitantes. La degradación del recurso y de los ecosistemas que lo generan, la polución, el despilfarro, el crecimiento de la población y su concentración en los centros urbanos, así como la falta de equidad en el acceso al agua, son algunos de los problemas que atentan contra las posibilidades de un desarrollo sostenible en el país. Con el fin de dar cuenta de los valores acordados al agua, se propuso un estudio que busca identificar la representación social que de ésta tiene un grupo social colombiano. Se entrevistó a 150 estudiantes de ciencias sociales en la ciudad de Bogotá. El análisis prototípico y categorial nos permitió plantear algunas hipótesis con respecto a las características de la representación social del agua elaborada por el grupo participante

  10. El estudio de los paisajes del agua en una cuenca vertiente: Propuesta metodológica

    OpenAIRE

    Marina Frolova

    2008-01-01

    RESUMEN Este trabajo presenta los paisajes del agua como un marco metodológico para el estudio de problemas medioambientales relacionados con el agua. Se propone analizar los paisajes del agua en una escala integradora de una cuenca vertiente, considerándolos desde tres enfoques –sistémico, territorial y paisajístico-. Se bosqueja una primera aproximación al análisis de los paisajes del agua de la cuenca del Guadalquivir, presentándola como un complejo hidrosistema fluvial, como un territori...

  11. MELCOR 1.8.2 assessment: The DF-4 BWR Damaged Fuel experiment

    International Nuclear Information System (INIS)

    Tautges, T.J.

    1993-10-01

    MELCOR is a fully integrated, engineering-level computer code being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As a part of an ongoing assessment, program, MELCOR has been used to model the ACRR in-pile DF-4 Damaged Fuel experiment. DF-4 provided data for early phase melt progression in BWR fuel assemblies, particularly for phenomena associated with eutectic interactions in the BWR control blade and zircaloy oxidation in the canister and cladding. MELCOR provided good agreement with experimental data in the key areas of eutectic material behavior and canister and cladding oxidation. Several shortcomings associated with the MELCOR modeling of BWR geometries were found and corrected. Twenty-five sensitivity studies were performed on COR, HS and CVH parameters. These studies showed that the new MELCOR eutectics model played an important role in predicting control blade behavior. These studies revealed slight time step dependence and no machine dependencies. Comparisons made with the results from four best-estimate codes showed that MELCOR did as well as these codes in matching DF-4 experimental data

  12. BWR ATWS mitigation by Fine Motion Control Rod

    International Nuclear Information System (INIS)

    Rohatgi, U.S.; Cheng, H.S.; Khan, H.; Mallen, A.; Diamond, D.

    1994-01-01

    Two main methods of ATWS mitigation in a SBWR are: fine Motion control Rods (FMCRD) and Boron injection via the Standby Liquid control System (SLCS). This study has demonstrated that the use of FMCRD along with feedwater runback mitigated the conditions due to reactivity insertion and possible ATWS in a BWR which is similar to SBWR

  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)

    Mursid Djokolelono.

    1976-01-01

    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. EVALUACIÓN DE LA PLANTA Lemna minor COMO BIORREMEDIADORA DE AGUAS CONTAMINADAS CON MERCURIO

    OpenAIRE

    Adolfo D. Arenas; Lué-Merú Marcó; Gosmyr Torres

    2011-01-01

    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 L...

  15. 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.

  16. 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)

  17. Hybrid Reactor Simulation and 3-D Information Display of BWR Out-of-Phase Oscillation

    International Nuclear Information System (INIS)

    Edwards, Robert; Huang, Zhengyu

    2001-01-01

    The real-time hybrid reactor simulation (HRS) capability of the Penn State TRIGA reactor has been expanded for boiling water reactor (BWR) out-of-phase behavior. During BWR out-of-phase oscillation half of the core can significantly oscillate out of phase with the other half, while the average power reported by the neutronic instrumentation may show a much lower amplitude for the oscillations. A description of the new HRS is given; three computers are employed to handle all the computations required, including real-time data processing and graph generation. BWR out-of-phase oscillation was successfully simulated. By adjusting the reactivity feedback gains from boiling channels to the TRIGA reactor and to the first harmonic mode power simulation, limit cycle can be generated with both reactor power and the simulated first harmonic power. A 3-D display of spatial power distributions of fundamental mode, first harmonic, and total powers over the reactor cross section is shown

  18. EVALUACIÓN DEL RIESGO EN SISTEMAS DE DISTRIBUCIÓN DE AGUA POTABLE EN EL MARCO DE UN PLAN DE SEGURIDAD DEL AGUA

    Directory of Open Access Journals (Sweden)

    Claudia Patricia Amézquita Marroquín

    Full Text Available La evaluación del riesgo es una etapa clave de un Plan de Seguridad del Agua (PSA y se logra mediante la identificación de peligros o eventos peligrosos y la valoración del riesgo. Este estudio evaluó los riesgos en el Sistema de Distribución de Agua potable (SDA de la ciudad de Cali (Colombia abastecido por el río Cauca, identificando los eventos peligrosos y posteriormente realizando la estimación del riesgo usando una matriz semicuantitativa adaptada. La estimación del riesgo se efectuó inicialmente sin considerar las medidas de control existentes del SDA y luego se reestimó considerando el nivel de eficacia de las mismas. Los resultados mostraron los eventos con mayor nivel de riesgo asociados al deterioro de la integridad física e hidráulica del SDA (daños en tuberías, fluctuaciones de presión, ausencia de información sistematizada sobre el SDA, fallas humanas, falta de capacitación, supervisión, conciencia del concepto aseguramiento del agua, corrosión interna y externa de elementos del SDA. La evaluación del riesgo es un instrumento de gestión para empresas prestadoras del servicio que permite priorizar recursos humanos y financieros hacia el mejoramiento de las medidas de control como estrategia para reducir los riesgos y asegurar la calidad del agua potable en el SDA.

  19. Siemens Nuclear Power Corporation methods development for BWR/PWR reactor licensing

    International Nuclear Information System (INIS)

    Pruitt, D.W.

    1992-01-01

    This presentation addresses the Siemens Nuclear Power Corporation (SNP) perspective on the primary forces driving methods development in the nuclear industry. These forces are fuel design, computational environment and industry requirement evolution. The first segment of the discussion presents the SNP experience base. SNP develops, manufactures and licenses both BWR and PWR reload fuel. A review of this experience base highlights the accelerating rate at which new fuel designs are being introduced into the nuclear industry. The application of advanced BWR lattice geometries provides an example of fuel design trends. The second aspect of the presentation is the rapid evolution of the computing environment. The final subject in the presentation is the impact of industry requirements on code or methods development

  20. Recent SCDAP/RELAP5 improvements for BWR severe accident simulations

    International Nuclear Information System (INIS)

    Griffin, F.P.

    1995-01-01

    A new model for the SCDAP/RELAP5 severe accident analysis code that represents the control blade and channel box structures in a boiling water reactor (BWR) has been under development since 1991. This model accounts for oxidation, melting, and relocation of these structures, including the effects of material interactions between B 4 C, stainless steel, and Zircaloy. This paper describes improvements that have been made to the BWR control blade/channel box model during 1994 and 1995. These improvements include new capabilities that represent the relocation of molten material in a more realistic manner and modifications that improve the usability of the code by reducing the frequency of code failures. This paper also describes a SCDAP/RELAP5 assessment calculation for the Browns Ferry Nuclear Plant design based upon a short-term station blackout accident sequence

  1. Geologie study off gravels of the Agua Fria River, Phoenix, AZ

    Science.gov (United States)

    Langer, W.H.; Dewitt, E.; Adams, D.T.; O'Briens, T.

    2010-01-01

    The annual consumption of sand and gravel aggregate in 2006 in the Phoenix, AZ metropolitan area was about 76 Mt (84 million st) (USGS, 2009), or about 18 t (20 st) per capita. Quaternary alluvial deposits in the modern stream channel of the Agua Fria River west of Phoenix are mined and processed to provide some of this aggregate to the greater Phoenix area. The Agua Fria drainage basin (Fig. 1) is characterized by rugged mountains with high elevations and steep stream gradients in the north, and by broad alluvial filled basins separated by elongated faultblock mountain ranges in the south. The Agua Fria River, the basin’s main drainage, flows south from Prescott, AZ and west of Phoenix to the Gila River. The Waddel Dam impounds Lake Pleasant and greatly limits the flow of the Agua Fria River south of the lake. The southern portion of the watershed, south of Lake Pleasant, opens out into a broad valley where the river flows through urban and agricultural lands to its confluence with the Gila River, a tributary of the Colorado River.

  2. 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)

  3. Citotoxicidad y genotoxicidad de las aguas de los ríos Jequetepeque y Moche mediante el bioindicador ambiental Vicia faba L.

    Directory of Open Access Journals (Sweden)

    Raúl Antonio Beltrán Orbegoso

    2017-01-01

    Full Text Available La evaluación de la toxicidad de las aguas de los ríos como método complementario al análisis físico, químico y biológico proporciona una información integral de la calidad del agua, por tanto, el objetivo del estudio fue determinar los niveles de citotoxicidad y genotoxicidad de las aguas de las cuencas alta, media y baja de los ríos Moche y Jequetepeque, usando el bioindicador ambiental Vicia faba L. “haba” (2n = 12. Se germinaron semillas de V. faba L.; luego las raicillas emergentes se expusieron, durante tres horas, a siete tratamientos: T1 (100 ml de agua destilada, T2 (1 ml agua de río Jequetepeque / 99 ml de agua destilada, T3 (5 ml agua de río Jequetepeque/ 95 ml de agua destilada, T4 (10 ml agua de río Jequetepeque/ 90 ml de agua destilada, T5 (1 ml agua de río Moche/ 99 ml de agua destilada, T6 (5 ml agua de río Moche/ 95 ml de agua destilada y T7 (10 ml agua de río Moche/ 90 ml de agua destilada. Los ápices de las raicillas fueron sometidos a la técnica de Tjio y Levan. El agua de la cuenca media del río Moche del T7, presenta una alta citotoxicidad (índice mitótico de 5,4 % y alteraciones de los índices de fases y un alto efecto genotóxico; las aguas del río Jequetepeque no evidencian efecto citotóxico ni genotóxico de importancia.

  4. Signal analysis of acoustic and flow-induced vibrations of BWR main steam line

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa-Paredes, G., E-mail: gepe@xanum.uam.mx [División de Ciencias Básicas e Ingeniería, Universidad Autónoma Metropolitana-Iztapalapa, México, D.F. 09340 (Mexico); Prieto-Guerrero, A. [División de Ciencias Básicas e Ingeniería, Universidad Autónoma Metropolitana-Iztapalapa, México, D.F. 09340 (Mexico); Núñez-Carrera, A. [Comisión Nacional de Seguridad Nuclear y Salvaguardias, Doctor Barragán 779, Col. Narvarte, México, D.F. 03020 (Mexico); Vázquez-Rodríguez, A. [División de Ciencias Básicas e Ingeniería, Universidad Autónoma Metropolitana-Iztapalapa, México, D.F. 09340 (Mexico); Centeno-Pérez, J. [Instituto Politécnico Nacional, Escuela Superior de Física y Matemáticas Unidad Profesional “Adolfo López Mateos”, Av. IPN, s/n, México, D.F. 07738 (Mexico); Espinosa-Martínez, E.-G. [Departamento de Sistemas Energéticos, Universidad Nacional Autónoma de México, México, D.F. 04510 (Mexico); and others

    2016-05-15

    Highlights: • Acoustic and flow-induced vibrations of BWR are analyzed. • BWR performance after extended power uprate is considered. • Effect of acoustic side branches (ASB) is analyzed. • The ASB represents a reduction in the acoustic loads to the steam dryer. • Methodology developed for simultaneous analyzing the signals in the MSL. - Abstract: The aim of this work is the signal analysis of acoustic waves due to phenomenon known as singing in Safety Relief Valves (SRV) of the main steam lines (MSL) in a typical BWR5. The acoustic resonance in SRV standpipes and fluctuating pressure is propagated from SRV to the dryer through the MSL. The signals are analyzed with a novel method based on the Multivariate Empirical Mode Decomposition (M-EMD). The M-EMD algorithm has the potential to find common oscillatory modes (IMF) within multivariate data. Based on this fact, we implement the M-EMD technique to find the oscillatory mode in BWR considering the measurements obtained collected by the strain gauges located around the MSL. These IMF, analyzed simultaneously in time, allow obtaining an estimation of the effects of the multiple-SRV in the MSL. Two scenarios are analyzed: the first is the signal obtained before the installation of the acoustic dampers (ASB), and the second, the signal obtained after installation. The results show the effectiveness of the ASB to damp the strong resonances when the steam flow increases, which represents an important reduction in the acoustic loads to the steam dryer.

  5. Signal analysis of acoustic and flow-induced vibrations of BWR main steam line

    International Nuclear Information System (INIS)

    Espinosa-Paredes, G.; Prieto-Guerrero, A.; Núñez-Carrera, A.; Vázquez-Rodríguez, A.; Centeno-Pérez, J.; Espinosa-Martínez, E.-G.

    2016-01-01

    Highlights: • Acoustic and flow-induced vibrations of BWR are analyzed. • BWR performance after extended power uprate is considered. • Effect of acoustic side branches (ASB) is analyzed. • The ASB represents a reduction in the acoustic loads to the steam dryer. • Methodology developed for simultaneous analyzing the signals in the MSL. - Abstract: The aim of this work is the signal analysis of acoustic waves due to phenomenon known as singing in Safety Relief Valves (SRV) of the main steam lines (MSL) in a typical BWR5. The acoustic resonance in SRV standpipes and fluctuating pressure is propagated from SRV to the dryer through the MSL. The signals are analyzed with a novel method based on the Multivariate Empirical Mode Decomposition (M-EMD). The M-EMD algorithm has the potential to find common oscillatory modes (IMF) within multivariate data. Based on this fact, we implement the M-EMD technique to find the oscillatory mode in BWR considering the measurements obtained collected by the strain gauges located around the MSL. These IMF, analyzed simultaneously in time, allow obtaining an estimation of the effects of the multiple-SRV in the MSL. Two scenarios are analyzed: the first is the signal obtained before the installation of the acoustic dampers (ASB), and the second, the signal obtained after installation. The results show the effectiveness of the ASB to damp the strong resonances when the steam flow increases, which represents an important reduction in the acoustic loads to the steam dryer.

  6. BWR Assembly Optimization for Minor Actinide Recycling

    International Nuclear Information System (INIS)

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

    2010-01-01

    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). A top-level objective of the Advanced Fuel Cycle Systems Analysis program element of the DOE NERI program is to investigate spent fuel treatment and recycling options for current light water reactors (LWRs). Accordingly, this project targets to expand the traditional scope of nuclear fuel management optimization into the following two complementary specific objectives: (1) To develop a direct coupling between the pin-by-pin within-bundle loading control variables and core-wide (bundle-by-bundle) optimization objectives, (2) to extend the methodology developed to explicitly encompass control variables, objectives, and constraints designed to maximize minor actinide incineration in BWR bundles and cycles. The first specific objective is projected to 'uncover' dormant thermal margin made available by employing additional degrees of freedom within the optimization process, while the addition of minor actinides is expected to 'consume' some of the uncovered thermal margin. Therefore, a key underlying goal of this project is to effectively invest some of the uncovered thermal margin into achieving the primary objective.

  7. Thermochemistry in BWR. An overview of applications of program codes and databases

    International Nuclear Information System (INIS)

    Hermansson, H-P.; Becker, R.

    2010-01-01

    The Swedish work on thermodynamics of metal-water systems relevant to BWR conditions has been ongoing since the 70ies, and at present time a compilation and adaptation of codes and thermodynamic databases are in progress. In the previous work, basic thermodynamic data were compiled for parts of the system Fe-Cr-Ni-Co-Zn-S-H 2 O at 25-300 °C. Since some thermodynamic information necessary for temperature extrapolations of data up to 300 °C was not published in the earlier works, these data have now been partially recalculated. This applies especially to the parameters of the HKF-model, which are used to extrapolate the thermodynamic data for ionic and neutral aqua species from 25 °C to BWR temperatures. Using the completed data, e.g. the change in standard Gibbs energy (ΔG 0 ) and the equilibrium constant (log K) can be calculated for further applications at BWR/LWR conditions. In addition a computer program is currently being developed at Studsvik for the calculation of equilibrium conductivity in high temperature water. The program is intended for PWR applications, but can also be applied to BWR environment. Data as described above will be added to the database of this program. It will be relatively easy to further develop the program e.g. to calculate Pourbaix diagrams, and these graphs could then be calculated at any temperature. This means that there will be no limitation to the temperatures and total concentrations (usually 10 -6 to 10 -8 mol/kg) as reported in earlier work. It is also easy to add a function generating ΔG 0 and log K values at selected temperatures. One of the fundamentals for this work was also to overview and collect publicly available thermodynamic program codes and databases of relevance for BWR conditions found in open sources. The focus has been on finding already done compilations and reviews, and some 40 codes and 15 databases were found. Codes and data-bases are often integrated and such a package is often developed for

  8. El agua no cae del cielo: gobernación y gestión del agua en el Pacífico Sur

    OpenAIRE

    Farias Ferreira, Marcos

    2013-01-01

    La seguridad hídrica se está volviendo una preocupación central en el cotidiano de muchas comunidades rurales por todo el mundo y se relaciona con cada una de las siete dimensiones de la seguridad humana, ampliando todo tipo de vulnerabilidades. De acuerdo con el informe del Foro Económico Mundial sobre el nexo agua-alimentos-energía-clima, la gestión del agua se está volviendo una materia política urgente en el debate de la sostenibilidad y de la seguridad humana a escala global. Asimismo, h...

  9. Estudio fotogramétrico del depósito de agua de Canteras

    OpenAIRE

    Aparicio Cirre, María M.

    2008-01-01

    El Deposito de Agua de Canteras, forma parte de una manzana limitada entre las calles Trujillo, Tornavacas, Cestona y carretera del cementerio, por la cual se accede al inmueble. Y por su parte trasera está limitada por las canteras romanas. El Depósito de Agua está formado principalmente por dos naves, una longitudinal y otra transversal, en planta tiene forma de “t”. Las dimensiones de la nave longitudinal donde se almacena el agua son: 2naves x 9,8m de largo x 5,7m de ancho x 2,4m de pr...

  10. Calidad de las aguas meteóricas en la ciudad de Itajubá, Minas Gerais, Brasil

    Directory of Open Access Journals (Sweden)

    Herlane Costa Calheiros

    2014-04-01

    Full Text Available El objetivo de este estudio fue evaluar la calidad del agua meteórica en la ciudad de Itajubá, ubicado en la parte sur de Minas Gerais, Brasil. Para ello, se realizaron la colecta y análisis de la calidad de las muestras de agua de lluvia después de escurrir sobre la superficie de tres tipos de materiales; amianto, zinc y cerámica. También se realizó una colecta directa para comparar los resultados y verificar los cambios en la calidad del agua. Se observó que la calidad del agua de lluvia varía en función del material a través en el cual fluye, alterando de esta manera los parámetros físicos-microbiológicos como el pH, dureza, alcalinidad, turbidez y el contenido de coliformes. Por lo tanto, el material de la superficie de los sistemas de colección de agua de lluvia puede modificar la calidad del agua, y el destino final de este tipo de agua. A pesar que las aguas meteóricas de Itajubá presentaron un bajo grado de contaminación, se concluye que el tratamiento de estas aguas deben prever la remoción de sólidos, el ajuste de pH y la desinfección, de esta forma, se estará obteniendo una alternativa ventajosa, sustentable y asequible de uso en época de escases hídrica.

  11. Calidad del agua subterránea para usos agropecuarios en el departamento Villaguay, Entre Ríos

    Directory of Open Access Journals (Sweden)

    Eduardo Pedro Vivot

    2010-12-01

    Full Text Available El agua subterránea constituye una fuente relevante de agua dulce necesaria para la vida, el medio ambiente y el desarrollo de los pueblos. Este recurso se caracteriza tanto por su finitud como por su vulnerabilidad, aspectos aparentemente ignorados por el hombre que continúa contaminándolo y alterando sus aptitudes. La demanda mundial de agua dulce ha crecido en correlación con la población mundial, pero el sector agropecuario ha aumentado sensiblemente la explotación de los acuíferos, en particular para riego de cultivos, que insumen el 70 % del total. El objetivo de este trabajo consistió en realizar la caracterización hidroquímica del agua subterránea rural del departamento Villaguay (Entre Ríos y determinar la calidad para los usos rurales, utilizando para ello metodologías estandarizadas para analizarlas y aceptados criterios de evaluación. Los resultados muestran que las aguas se caracterizan como bicarbonatadas en los distritos al este del río Gualeguay, y como sulfatadas al oeste del mismo. La evaluación del agua para bebida animal indica que poseen aptitud buena a regular. En cuanto a calidad del agua para riego, presenta en general ligeras restricciones de uso. Las aguas para las aplicaciones de pesticidas muestran limitantes que requieren la corrección particular del pH y la dureza. Palabras clave: agua subterránea rural; caracterización hidroquímica; calidad para usos agropecuarios.

  12. Applied methods for mitigation of damage by stress corrosion in BWR type reactors; Metodos aplicados para la mitigacion del dano por corrosion bajo esfuerzo en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez C, R.; Diaz S, A.; Gachuz M, M.; Arganis J, C. [Instituto Nacional de Investigaciones Nucleares, Gerencia de Ciencia de Materiales, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1998-07-01

    The Boiling Water nuclear Reactors (BWR) have presented stress corrosion problems, mainly in components and pipes of the primary system, provoking negative impacts in the performance of energy generator plants, as well as the increasing in the radiation exposure to personnel involucred. This problem has caused development of research programs, which are guided to find solution alternatives for the phenomena control. Among results of greater relevance the control for the reactor water chemistry stands out particularly in the impurities concentration and oxidation of radiolysis products; as well as the supervision in the materials selection and the stresses levels reduction. The present work presents the methods which can be applied to diminish the problems of stress corrosion in BWR reactors. (Author)

  13. 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.

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

    NARCIS (Netherlands)

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

    2002-01-01

    The !-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.

  15. Power plant design: ESBWR - the latest passive BWR

    International Nuclear Information System (INIS)

    Arnold, H.; Yadigaroglu, G.; Stoop, P.C.

    1997-01-01

    When General Electric said it would end development of its 670 MWe SBWR (Simplified Boiling Water Reactor), it was not quite the end of the story. Also on the drawing board at the time was the larger ESBWR (standing for either European or Economic Simplified BWR) whose goal was to provide the improved economic performance that the SBWR could not. (UK)

  16. 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...

  17. BWR fuel experience with zinc injection

    International Nuclear Information System (INIS)

    Levin, H.A.; Garcia, S.E.

    1995-01-01

    In 1982 a correlation between low primary recirculation system dose rates in BWR's and the presence of ionic zinc in reactor water was identified. The source of the zinc was primarily from Admiralty brass condensers. Plants with brass condensers are called ''natural zinc'' plants. Brass condensers were also a source of copper that was implicated in crude induced localized corrosion (CILC) fuel failures. In 1986 the first BWR intentionally injected zinc for the benefits of dose rate control. Although zinc alone was never implicated in fuel degradation of failures, a comprehensive fuel surveillance program was initiated to monitor fuel performance. Currently there are 14 plants that are injecting zinc. Six of these plants are also on hydrogen water chemistry. This paper describes the effect on both Zircaloy corrosion and the cruding characteristics as a result of these changes in water chemistry. Fuel rod corrosion was found to be independent of the specific water chemistry of the plants. The corrosion behavior was the same with the additions of zinc alone or zinc plus hydrogen and well within the operating experience for fuel without either of these additions. No change was observed in the amounts of crude deposited on the fuel rods, both for the adherent and loosely held deposits. One of the effects of the zinc addition was the trend to form more of the zinc rich iron spinel in the fuel deposits rather than the hematite deposits that are predominantly formed with non additive water chemistry

  18. Assessment of boiling transition analysis code against data from NUPEC BWR full-size fine-mesh bundle tests

    International Nuclear Information System (INIS)

    Utsuno, Hideaki; Ishida, Naoyuki; Masuhara, Yasuhiro; Kasahara, Fumio

    2004-01-01

    Transient BT analysis code TCAPE based on mechanistic methods coupled with subchannel analysis has been developed for the evaluation on fuel integrity under abnormal operations in BWR. TCAPE consisted mainly of the drift-flux model, the cross-flow model, the film model and the heat transfer model. Assessment of TCAPE has been performed against data from BWR full-size fine-mesh bundle tests (BFBT), which consisted of two major parts: the void distribution measurement and the critical power measurement. Code and data comparison was made for void distributions with varying number of unheated rods in simulated actual fuel assembly. Prediction of steady-state critical power was compared with the measurement on full-scale bundle under a range of BWR operational conditions. Although the cross-sectional averaged void fraction was underestimated when it became lower, the accuracy was obtained that the averaged ratio 0.910 and its standard deviation 0.076. The prediction of steady-state critical power agreed well with the data in the range of BWR operations, where the prediction accuracy was obtained that the averaged ratio 0.997 and its standard deviation 0.043. These results demonstrated that TCAPE is well capable to predict two-phase flow distribution and liquid film dryout phenomena occurring in BWR rod bundles. Part of NUPEC BFBT database will be made available for an international benchmark exercise. The code assessment shall be continued against the OECD/NRC benchmark based on BFBT database. (author)

  19. Antecedentes hidroquímicos del Salar de Aguas Calientes I (Chile

    Directory of Open Access Journals (Sweden)

    Ingrid Garcés Millas

    2012-01-01

    Full Text Available El Salar de Aguas Calientes I es un sistema salino del Altiplano chileno, situado a4.280 m.s.n.m, expuesto a condiciones ambientales áridas. El presente trabajo da cuenta del estudio hidroquímico de las soluciones superficiales existentes en el salar, tanto de soluciones diluidas como concentradas en surgencias y acumulaciones lacustres, así como de la mineralogía de las sales precipitadas por evaporación de estas aguas lacustres. Los principales aportes de agua al salar ingresan por la zona norte y por el sector sur, siendo estos últimos de carácter termal. Los restantes aportes se limitan a escasas precipitaciones en forma de escorrentía superficial o subsuperficial. Todas estas aguas circulan hacia las zonas más bajas del salar, y se acumulan en distintos puntos a lo largo de su sector occidental como consecuencia de un ligero basculamiento en su superficie. Los resultados del análisis químico indican que, a pesar de tratarse de aguas con grados de concentración variable y que oscilan entre muy diluidas y altamente concentradas, todas ellas pertenecen al tipo químico Na-Cl, debido a la interacción de las aguas con los depósitos salinos preexistentes en el salar, en los que predominan halita y yeso. Además, todas las soluciones mostraron elevados contenidos en elementos químicos asociados a actividad hidrotermal como son Li, B y As, encontrándose este último en rangos de toxicidad incluso en las muestras diluidas. En el margen norte del salar, las aguas de una surgencia no termal caracterizadas por ser de muy baja concentración en sales minerales, discurren hacia el salar,alimentando una zona de bofedal en la que se desarrolla importante vida vegetal y sirven de sustento a los rebaños de camélidos del área. En cambio, las aguas de los sectores central y meridional (donde se encuentra una surgencia de carácter termal son mucho más concentradas, acumulándose en lagunas desprovistas de desarrollo vegetal. El an

  20. Agua que nos habita: una propuesta de transversalización de la cultura del agua en la Institución Educativa Rural Yarumito.

    OpenAIRE

    Pedraza Contreras, María Luisa

    2012-01-01

    El Ministerio de Ambiente y Desarrollo Sostenible, crea desde el Viceministerio de Ambiente el Programa Nacional de Cultura del Agua que tiene como objetivo “crear conciencia y conocimiento, educar, informar y hacer partícipes a los usuarios del recurso hídrico, acerca de la necesidad de realizar acciones para contribuir en: • Concientización personal y colectiva de la finitud del agua por las afectaciones y presiones a que es sometida; • Conservación y uso sostenible del recurso hídric...

  1. 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)

  2. Dose rate reduction method for NMCA applied BWR plants

    International Nuclear Information System (INIS)

    Nagase, Makoto; Aizawa, Motohiro; Ito, Tsuyoshi; Hosokawa, Hideyuki; Varela, Juan; Caine, Thomas

    2012-09-01

    BRAC (BWR Radiation Assessment and Control) dose rate is used as an indicator of the incorporation of activated corrosion by products into BWR recirculation piping, which is known to be a significant contributor to dose rate received by workers during refueling outages. In order to reduce radiation exposure of the workers during the outage, it is desirable to keep BRAC dose rates as low as possible. After HWC was adopted to reduce IGSCC, a BRAC dose rate increase was observed in many plants. As a countermeasure to these rapid dose rate increases under HWC conditions, Zn injection was widely adopted in United States and Europe resulting in a reduction of BRAC dose rates. However, BRAC dose rates in several plants remain high, prompting the industry to continue to investigate methods to achieve further reductions. In recent years a large portion of the BWR fleet has adopted NMCA (NobleChem TM ) to enhance the hydrogen injection effect to suppress SCC. After NMCA, especially OLNC (On-Line NobleChem TM ), BRAC dose rates were observed to decrease. In some OLNC applied BWR plants this reduction was observed year after year to reach a new reduced equilibrium level. This dose rate reduction trends suggest the potential dose reduction might be obtained by the combination of Pt and Zn injection. So, laboratory experiments and in-plant tests were carried out to evaluate the effect of Pt and Zn on Co-60 deposition behaviour. Firstly, laboratory experiments were conducted to study the effect of noble metal deposition on Co deposition on stainless steel surfaces. Polished type 316 stainless steel coupons were prepared and some of them were OLNC treated in the test loop before the Co deposition test. Water chemistry conditions to simulate HWC were as follows: Dissolved oxygen, hydrogen and hydrogen peroxide were below 5 ppb, 100 ppb and 0 ppb (no addition), respectively. Zn was injected to target a concentration of 5 ppb. The test was conducted up to 1500 hours at 553 K. Test

  3. 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.

  4. Void Reactivity Effects in the Second Charge of the Halden Boiling Water Reactor; Effets Cavitaires dans la Deuxieme Charge du Reacteur a Eau Lourde Bouillante de Halden (HBWR); Ehffekty pustotnoj reaktivnosti vo vtoroj zag HBWR; Effectos de Cavitacion en la Segunda Carga del Reactor de Agua Pesada Hirviente de Halden (HBWR)

    Energy Technology Data Exchange (ETDEWEB)

    Lunde, J. E. [OECD Halden Reactor Project (Norway)

    1964-02-15

    nucleaire a des temperatures differentes du ralentisseur comprises entre 150 et 230 Degree-Sign C et, a la. temperature la plus elevee, pour des puissances allant jusqu'a 16 MW. Le coefficient cavitaire est une quantite qu'il importe de connaitre lorsqu'on veut determiner le comportement dynamique d'un reacteur a eau bouillante. Or, la determination theorique de cette quantite est difficile du fait qu'il faut connaitre en detail la repartition des cavites dans le coeur. Cette repartition dans les conditions de puissance ne se prete pas facilement a une determination experimentale de sorte que les experiences avec vide simule conviennent mieux pour verifier les calculs de physique des reacteurs portant sur les effets cavitaires. Les donnees de ces experiences ont ete comparees aux resultats theoriques. On a applique la theorie de la diffusion a deux groupes et on peut conclure qu'il y a bon accord entre la theorie et l'experience en ce qui concerne les perturbations dans les parametres du reseau pour un coefficient cavitaire egal a 1, tant aux basses qu'aux hautes temperatures. Toutefois, pour les valeurs intermediaires du coefficient cavitaire, l'accord est moins bon. Pour le calcul macroscopique de l'effet sur la reactivite, on utilise une theorie de perturbation. (author) [Spanish] La ebullicion que se produce en el interior de los canales refrigerantes de la segunda carga de combustible del reactor de agua pesada hirviente de Halden provoca efectos de cavitacion que afectan a la reactividad. Este efecto se ha medido tanto en experimentos con vacio simulado de potencia nula como en condiciones de regimen normal. Los experimentos con vacio simulado consistieron en medir las alteraciones de la reactividad al introducir hasta diversas profundidades tubos vacios de paredes delgadas, que se colocaron en distintas posiciones entre las piezas de union de un haz combustible de siete barras, practicamente identico a los que constituyen la segunda carga de combustible. Este

  5. Vertical Drop of 44-BWR Waste Package With Lifting Collars

    Energy Technology Data Exchange (ETDEWEB)

    A.K. Scheider

    2005-08-23

    The objective of this calculation is to determine the structural response of a waste package (WP) dropped flat on its bottom from a specified height. The WP used for that purpose is the 44-Boiling Water Reactor (BWR) WP. The scope of this document is limited to reporting the calculation results in terms of stress intensities. The Uncanistered Waste Disposal Container System is classified as Quality Level 1 (Ref. 4, page 7). Therefore, this calculation is subject to the requirements of the Quality Assurance Requirements and Description (Ref. 16). AP-3. 12Q, Design Calculations and Analyses (Ref. 11) is used to perform the calculation and develop the document. The information provided by the sketches attached to this calculation is that of the potential design of the type of 44-BWR WP considered in this calculation and provides the potential dimensions and materials for that design.

  6. Study on thermal performance and margins of BWR fuel elements

    International Nuclear Information System (INIS)

    Stosic, Zoran

    1999-01-01

    This paper contributes to developing a methodology of predicting and analyzing thermal performance and margins of Boiling Water Reactor (BWR) fuel assemblies under conditions of reaching high quality Boiling Crisis and subsequent post-dryout thermal hydraulics causing temperature excursion of fuel cladding. Operational margins against dryout and potential for increasing fuel performance with appropriate benefits are discussed. The philosophy of modeling with its special topics are demonstrated on the HECHAN (HEated CHannel ANalyzer) model as the state-of-art for thermal-hydraulics analysis of BWR fuel assemblies in pre- and post-dryout two-phase flow regimes. The scope of further work either being or has to be performed concerning implementation of new physical aspects, including domain extension of HECHAN model applications to the Pressurized Water Reactors (PWRs), is discussed. Finally, a comprehensive overview of the literature dealing with development of the model is given. (author)

  7. Inventario y evaluación nacional de aguas superficiales

    OpenAIRE

    Oficina Nacional de Evaluación de Recursos Naturales

    1980-01-01

    Determina la potencialidad del recurso agua de escurrimiento superficial a nivel medio anual y su distribución en el territorio peruano. El informe incluye el Inventario y Evaluación Nacional de Aguas Superficiales, propiamente dicho y el Inventario Nacional de Ríos y se acompaña con el Mapa de Zonas de Escurrimiento del Perú y la propuesta para un Programa de Instalaciones Hidrométricas. Para el desarrollo de esta publicación se ha considerado las complejidades propias del territorio desde l...

  8. Sophistication of operator training using BWR plant simulator

    International Nuclear Information System (INIS)

    Ohshiro, Nobuo; Endou, Hideaki; Fujita, Eimitsu; Miyakita, Kouji

    1986-01-01

    In Japanese nuclear power stations, owing to the improvement of fuel management, thorough maintenance and inspection, and the improvement of facilities, high capacity ratio has been attained. The thorough training of operators in nuclear power stations also contributes to it sufficiently. The BWR operator training center was established in 1971, and started the training of operators in April, 1974. As of the end of March, 1986, more than 1800 trainees completed training. At present, in the BWR operator training center, No.1 simulator of 800 MW class and No.2 simulator of 1100 MW class are operated for training. In this report, the method, by newly adopting it, good result was obtained, is described, that is, the method of introducing the feeling of being present on the spot into the place of training, and the new testing method introduced in retraining course. In the simulator training which is apt to place emphasis on a central control room, the method of stimulating trainees by playing the part of correspondence on the spot and heightening the training effect of multiple monitoring was tried, and the result was confirmed. The test of confirmation on the control board was added. (Kako, I.)

  9. Un hidrogel de hidróxido de aluminio para eliminar el arsénico del agua

    Directory of Open Access Journals (Sweden)

    Luján Juan Carlos

    2001-01-01

    Full Text Available Objetivos. Describir la síntesis y los resultados preliminares de la aplicación de un hidrogel de hidróxido de aluminio que, agregado directamente al agua, pueda lograr la eliminación total del arsénico, cualquiera que sea la naturaleza del agua y el estado de oxidación del metaloide. Métodos. Las materias primas utilizadas para obtener el hidrogel de hidróxido de aluminio fueron: sulfato de aluminio hidratado (que se utiliza para potabilizar aguas, hipoclorito de calcio en polvo, hidróxido de amonio y agua destilada (cuando el gel se preparó a escala de laboratorio y agua de ósmosis inversa de igual o mejor calidad que el agua destilada (cuando se produjo el gel a escala piloto. El control de calidad del producto final consistió en la determinación de su capacidad para adsorber el arsénico y la realización de pruebas bacteriológicas para demostrar su esterilidad. El producto fue aplicado a muestras de agua a las que se añadió arsénico en el laboratorio y a muestras de aguas arsenicales naturales procedentes de la provincia de Tucumán, Argentina. Para el análisis del arsénico en el agua se utilizó el método colorimétrico del dietilditiocarbamato de plata. Resultados. La aplicación del hidrogel proporcionó una gran reducción del arsénico. Tanto en las aguas arsenicales naturales como en las artificiales, después del tratamiento las concentraciones de arsénico quedaron por debajo del límite de detección del método analítico utilizado (0,01 partes por millón. Las pruebas bacteriológicas del producto terminado revelaron la ausencia de bacterias viables. Conclusiones. La aplicación del hidrogel de hidróxido de aluminio proporcionó la deseada reducción de la concentración de arsénico en el agua. Este método de desarsenización es barato y fácil de utilizar en poblaciones rurales dispersas de zonas afectadas por el hidroarsenicismo que carecen de agua potable e infraestructura sanitaria y eléctrica.

  10. Control in fabrication of PWR and BWR type reactor fuel elements

    International Nuclear Information System (INIS)

    Gorskij, V.V.

    1981-01-01

    Both destructive and non-destructive testing methods now in use in fabrication of BWR and PWR type reactor fuel elements at foreign plants are reviewed. Technological procedures applied in fabrication of fuel elements and fuel assemblies are described. Major attention is paid to radiographic, ultrasonic, metallographic, visual and autoclavic testings. A correspondence of the methods applied to the ASTM standards is discussed. The most part of the countries are concluded the apply similar testing methods enabling one to reliably evaluate the quality of primary materials and fabricated fuel elements and thus meeting the demands to contemporary PWR and BWR type reactor fuel elements. Practically all fuel element and pipe fabrication plants in Western Europe, Asia and America use the ASTM standards as the basis for the quality contr [ru

  11. Development of a computerized operator support system for BWR power plant

    International Nuclear Information System (INIS)

    Monta, K.; Sekimizu, K.; Sato, N.; Araki, T.; Mori, N.

    1985-01-01

    A computerized operator support system for BWR power plant has been developed since 1980 supported by the Japanese government. The main functions of the systems are post trip operational guidance, disturbance analysis, standby system management, operational margin monitoring and control rod operational guidance. The former two functions aim at protection against incidents during operation of nuclear power plants and the latter three functions aim at their prevention. As the final stage of the development, these functions are combined with the plant supervision function and are organized as an advanced man-machine interface for BWR power plant. During the above process, operator task analyses are performed to enable synthesis of these support functions for right fit to operator tasks and to realize a hierarchical structure for CRT displays for right fit to operators cognitive needs. (author)

  12. Agua y ciudad

    Directory of Open Access Journals (Sweden)

    Carolina Maturana

    2007-10-01

    ¿Dónde y en qué se relaciona todo esto con la temática agua y ciudad? La mirada desde donde se construye cada una de las obras anteriores, para por una mirada que se detiene en la "otra ciudad" y en la memoria colectiva que entrecruza la ciudad oficial con ella; es en esa otra ciudad donde me detengo en el río Bío-Bío como cuerpo testigo, como contenedor de historias, como continente de despojos, industriales y humanos, como figura representacional de la marginalidad urbana.

  13. Prediction of droplet deposition around BWR fuel spacer by FEM flow analysis

    International Nuclear Information System (INIS)

    Yamamoto, Yasushi; Morooka, Shinichi

    1997-01-01

    The critical power of the BWR fuel assembly has been remarkably increased. That increase mainly depends on the improvement of the spacer which keeps fixed gaps between fuel rods. So far, these improvements have been carried out on the basis of what developers consider to be appropriate and the results of mockup tests of the BWR fuel assembly. However, continued reliance on these approaches for the development of a higher performance fuel assembly will prove time-consuming and costly. Therefore, it is hoped that the spacer effects for the critical power can be investigated by computer simulation, and it is significantly important to develop the critical power prediction method. Direct calculation of the two-phase flow in a BWR fuel channel s still difficult. Accordingly, a new method for predicting the critical power was proposed. Our method consists of CFD (computer fluid dynamics) code based on the single-phase flow analysis method and the subchannel analysis code. To verify our method, the critical power predictions for various spacer geometries were performed. The predicted results of the critical power were compared with the experimental data. The result of the comparison showed a good agreement and the applicability of our method for various spacer geometries. (author)

  14. La empresa agraria y el estudio del recurso agua en dos dimensiones

    OpenAIRE

    Maiztegui Martínez, Horacio Francisco

    2013-01-01

    El tema elegido refiere al problema de la degradación del agua en la Provincia de Entre Ríos, y la falta de adecuación de la ley Nacional como la ley 25688 que estableció un régimen de gestión ambiental, o la ley de Entre Ríos N° 9172 (Código de aguas) a los principios de la sustentabilidad concebidos en el art. 41 de la CN y la ley Nº 25.675 general del ambiente. Para superar la crisis actual, proponemos el estudio del agua en dos dimensiones, la primera dimensión (estática) es la considerac...

  15. CORRELACCIONES MATEMATICAS PARA LA OBTENCION DE RENDIMIENTO DE PRODUCCION, REMOCION DE CENIZAS Y PARTICION DE AGUA USANDO UN HIDROCICLON "SOLO AGUA"

    Directory of Open Access Journals (Sweden)

    JULIO ETAYO

    2009-01-01

    Full Text Available Se obtuvieron correlaciones matemáticas de rendimiento de producción, remoción de cenizas y partición de agua para describir el comportamiento de un hidrociclon "solo agua" (usa solamente agua como medio denso desde el punto de vista hidráulico y geométrico. Se utilizó un hidrociclón de 254mm de diámetro y un carbón de la mina la Yolanda (Valle del Cauca. La concentración másica de carbón usada fue entre 3.0 y 10.0% (p/p, la longitud del "vortex finder" entre 152.4 y 228.6mm y el diámetro del "apex" entre 19.1 y 44.5mm. A partir de las diferentes pruebas se obtuvieron rendimientos de producción entre 11.9 y 83.2% (p/p y remociones de cenizas entre 41.8 y 95.2% (p/p. Las ecuaciones matemáticas obtenidas presentaron factores de correlación superiores al 98.7% lo cual predice buena confiabilidad entre los resultados experimentales y los teóricos.

  16. Water chemistry control and decontamination experience with TEPCO BWR`s and the measures planned for the future

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, N.; Miyamaru, K. [Tokyo Electric Power Co. (Japan)

    1995-03-01

    The new TEPCO BWR`s are capable of having the occupational radiation exposure controlled successfully at a low level by selecting low cobalt steel, using corrosion-resistant steel, employing dual condensate polishing systems, and controlling Ni/Fe ratio during operation. The occupational radiation exposure of the old BWR`s, on the other hand, remains high though reduced substantially through the use of low cobalt replacement steel and the partial addition of a filter in the condensate polishing system. Currently under review is the overall decontamination procedure for the old BWR`s to find out to measures needed to reduce the amount of crud that is and has been carried over into the nuclear reactor. The current status of decontamination is reported below.

  17. 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

  18. PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR

    OpenAIRE

    MELARA SAN ROMÁN, JOSÉ

    2016-01-01

    [EN] Power and flow oscillations in a BWR are very undesirable. One of the major concerns is to ensure, during power oscillations, compliance with GDC 10 and 12. GDC 10 requires that the reactor core be designed with appropriate margin to assure that specified acceptable fuel design limits will not be exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. GDC 12 requires assurance that power oscillations which can result in conditions ...

  19. Valuation of power oscillations in a BWR after control rod banks withdrawal events

    International Nuclear Information System (INIS)

    Costa, A. L.; Pereira, C.; Da Silva, C. A. M.; Veloso, M. A. F.

    2009-01-01

    The out-of-phase mode of oscillation is a very challenging type of instability occurring in BWR (Boiling Water Reactor) and its study is relevant because of the safety implications related to the capability to promptly detect any such inadvertent occurrence by in-core neutron detectors, thus triggering the necessary countermeasures in terms of selected rod insertion or even reactor shutdown. In this work, control rod banks (CRB) withdrawal transient was considered to study the power instability occurring in a BWR. To simulate this transient, the control rod banks were continuously removed from the BWR core in different cases. The simulation resulted in a very large increase of power. To perform the instability simulations, the RELAP5/MOD3.3 thermal hydraulic system code was coupled with the PARCS/2.4 3D neutron kinetic code. Data from a real BWR, the Peach Bottom, have been used as reference conditions and reactor parameters. The trend of the mass flow rate, pressure, coolant temperature and the void fraction to four thermal hydraulic channels symmetrically located in the core with respect to the core centre, were taken. It appears that the velocity of the rod bank withdrawal is a very important aspect for reactor stability. The slowest CRB withdrawal (180 s) did not cause power perturbation while the fast removal (20 s) triggered a slow power oscillation that little by little amplified to reach levels of more 100% of the initial power after about 210 s. The investigation of the related thermo hydraulic parameters showed that the mass flow rate, the void fraction and also the coolant temperature began to oscillate at approximately the same time interval

  20. [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).

  1. 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.

  2. Analysis of Core Physics Experiments on Irradiated BWR MOX Fuel in REBUS Program

    International Nuclear Information System (INIS)

    Yamamoto, Toru; Ando, Yoshihira; Hayashi, Yamato

    2008-01-01

    As part of analyses of experimental data of a critical core containing a irradiated BWR MOX test bundle in the REBUS program, depletion calculations was performed for the BWR MOX fuel assemblies from that the MOX test rods were selected by using a general purpose neutronics code system SRAC. The core analyses were carried out using SRAC and a continuous energy Monte Carlo code MVP. The calculated k eff s were compared with those of the core containing a fresh MOX fuel bundle in the program. The SRAC-diffusion calculation underestimates k eff s of the both cores by 1.0 to 1.3 %dk and the k eff s of MVP are 1.001. The difference in k eff between the irradiated BWR MOX test bundle core and the fresh MOX one is 0.4 %dk in the SRAC-diffusion calculation and 0.0 %dk in the MVP calculation. The calculated fission rate distributions are in good agreement with the measurement in the SRAC-diffusion and MVP calculations. The calculated neutron flux distributions are also in good agreement with the measurement. The calculated burnup reactivity in the both calculations well reproduce the measurements. (authors)

  3. Informe: Agua potable - la EPA necesita adoptar medidas adicionales para garantizar que los pequeños sistemas de agua comunitarios señalados como graves infractores logren cumplir con las normas

    Science.gov (United States)

    Informe #16-P-0108, 22 de Marzo de 2016. La EPA puede proteger mejor al público del agua potable contaminada, lo que incluye a casi 200,000 personas en Puerto Rico que todavía carecen de agua potable segura.

  4. 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.

  5. OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes

    International Nuclear Information System (INIS)

    Ivanov, Kostadin; Olson, Andy; Sartori, Enrico

    2004-01-01

    An Organisation for Economic Co-operation and Development (OECD)/U.S. Nuclear Regulatory Commission (NRC)-sponsored coupled-code benchmark has been initiated for a boiling water reactor (BWR) turbine trip (TT) transient. Turbine trip transients in a BWR are pressurization events in which the coupling between core space-dependent neutronic phenomena and system dynamics plays an important role. In addition, the available real plant experimental data make this benchmark problem very valuable. Over the course of defining and coordinating the BWR TT benchmark, a systematic approach has been established to validate best-estimate coupled codes. This approach employs a multilevel methodology that not only allows for a consistent and comprehensive validation process but also contributes to the study of different numerical and computational aspects of coupled best-estimate simulations. This paper provides an overview of the OECD/NRC BWR TT benchmark activities with emphasis on the discussion of the numerical and computational aspects of the benchmark

  6. Privatización del agua y racismo ambiental en ciudades segregadas. La empresa Aguas del Illimani en las ciudades de La Paz y El Alto (1997-2005

    Directory of Open Access Journals (Sweden)

    Crespo Flores, Carlos O.

    2009-12-01

    Full Text Available Within the framework of environmental racism in the water sector, the water and sani - tation concession contract in the cities of La Paz and El Alto (Bolivia to Aguas del Illimani company, filial of Suez Group. Both cities are characterised as racially segregated spaces. The differentiated inclusion service policy of the company to neighbourhoods in La Paz and El Alto, particularly costs of connexion and tariffs, the exclusion of poor aymara zones and the environmental risks and impacts.

    Desde el concepto de racismo ambiental aplicado al sector agua, se analiza la concesión del servicio de agua y saneamiento en las ciudades de La Paz y El Alto a la empresa Aguas del Illimani (AISA, filial de la compañía francesa Suez. Ambas ciudades se caracterizan por ser socioeconómica y racialmente segregadas. Se muestra la política de inclusión diferenciada de la empresa respecto a las laderas de la ciudad de La Paz y El Alto, particularmente en los costos de conexión y tarifas del servicio, la exclusión de zonas pobres de aymaras migrantes, los impactos y riesgos ambientales.

  7. Requests on domestic nuclear data library from BWR design

    International Nuclear Information System (INIS)

    Maruyama, Hiromi

    2003-01-01

    Requests on the domestic nuclear data library JENDL and activities of the Nuclear Data Center have been presented from the perspective of BWR design and design code development. The requests include a standard multi-group cross section library, technical supports, and clarification of advantage of JENDL as well as requests from physical aspects. (author)

  8. 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.

  9. SISTEMA DE ELECTROCOAGULACIÓN COMO TRATAMIENTO DE AGUAS RESIDUALES GALVÁNICAS

    Directory of Open Access Journals (Sweden)

    Nelly Bibiana Morales Posada

    2010-01-01

    Full Text Available El presente artículo muestra la segunda fase del proyecto "Implementación y evaluación de un sistema piloto de electrocoagulación como tratamiento de aguas residuales con fines de reuso. Estudio de caso: aguas residuales industriales de origen galvánico". Para su desarrollo, se valoró y optimizó un prototipo existente en la Universidad, a partir de ensayos realizados en aguas residuales con contenido de metales, implementando un porcentaje mayor al 47% para la remoción de metales pesados como Cr+6, Pb y Zn de tales aguas, mediante proceso de electrocoagulación. Para el estudio, se utilizaron 10L de agua residual correspondientes al vertimiento de la empresa Compañía Eléctrica Ltda. Los análisis se hicieron, mediante la confrontación de parámetros de Cu, Cr, Cr+6, Ni, Pb y Zn, antes y después del tratamiento de electrocoagulación. Se obtuvo una reducción en Cr del 51.65%, donde el valor arrojado está por debajo de los estándares establecidos en materia de vertimientos (Res. No 1074 28 Oct. 1997, Ni del 18.09%, Pb del 50%, Zn del 47.37%, los cuales a pesar de la remoción producida, tienen valores superiores a lo estipulado en esta normativa. El Cu tuvo un aumento del 519.48%, debido a la placa empleada para el tratamiento. Los valores promedio obtenidos durante los ensayos fueron: pH: 3.18, conductividad: 21.83 mS/m y temperatura: 48.5 ºC. A pesar de que los valores de las variables y los parámetros no se encuentran dentro de los rangos generalmente expuestos por la literatura consultada para sistemas de electrocoagulación con aguas residuales, se obtuvo una reducción relevante en cuanto a la presencia de los metales estudiados.

  10. A study of heat capacity temperature limit of BWR

    International Nuclear Information System (INIS)

    Wang, Shih-Jen; Chen, Jyh-Jun; Chien, Chun-Sheng; Teng, Jyh-Tong

    2012-01-01

    Highlights: ► The purpose of this study is to verify the HCTL. ► MAAP4 was used as code to generate a realistic and convenient HCTL. ► The current HCTL curve causes confusing in reading data. ► The revised HCTL curves developed in this study. ► Users can obtain important parameters from the revised HCTL without confusion and interpolation. - Abstract: Heat capacity temperature limit (HCTL) is an important parameter for operation of BWR. Current version of the HCTL was derived, based on simple model of computation aids (CA) of BWR owners’ group (BWROG). However, some parts of the current HCTL are confusing to the users in reading data. The purpose of this study is to verify the HCTL by applying the MAAP4 code to the field of emergency operating procedure (EOP). The trends of HCTL generated by MAAP4 code are consistent with those obtained from CA. A series of revised HCTL evaluated at various times after scram are provided and the confusing part is eliminated.

  11. System control model of a turbine for a BWR

    International Nuclear Information System (INIS)

    Vargas O, Y.; Amador G, R.; Ortiz V, J.; Castillo D, R.; Delfin L, A.

    2009-10-01

    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)

  12. A study of heat capacity temperature limit of BWR

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Shih-Jen, E-mail: sjenwang@iner.gov.tw [Institute of Nuclear Energy Research (INER), 1000, Wunhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Chen, Jyh-Jun [Department of Mechanical Engineering, Chung Yuan Christian University, 200, Chung Pei Rd., Chung Li City, Taoyuan County 32023, Taiwan (China); Chien, Chun-Sheng [Institute of Nuclear Energy Research (INER), 1000, Wunhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Teng, Jyh-Tong [Department of Mechanical Engineering, Chung Yuan Christian University, 200, Chung Pei Rd., Chung Li City, Taoyuan County 32023, Taiwan (China)

    2012-02-15

    Highlights: Black-Right-Pointing-Pointer The purpose of this study is to verify the HCTL. Black-Right-Pointing-Pointer MAAP4 was used as code to generate a realistic and convenient HCTL. Black-Right-Pointing-Pointer The current HCTL curve causes confusing in reading data. Black-Right-Pointing-Pointer The revised HCTL curves developed in this study. Black-Right-Pointing-Pointer Users can obtain important parameters from the revised HCTL without confusion and interpolation. - Abstract: Heat capacity temperature limit (HCTL) is an important parameter for operation of BWR. Current version of the HCTL was derived, based on simple model of computation aids (CA) of BWR owners' group (BWROG). However, some parts of the current HCTL are confusing to the users in reading data. The purpose of this study is to verify the HCTL by applying the MAAP4 code to the field of emergency operating procedure (EOP). The trends of HCTL generated by MAAP4 code are consistent with those obtained from CA. A series of revised HCTL evaluated at various times after scram are provided and the confusing part is eliminated.

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

    International Nuclear Information System (INIS)

    Rajamaeki, Markku.

    1980-03-01

    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)

  14. Economía de agua, economía de instalaciones

    Directory of Open Access Journals (Sweden)

    Salas Serrano, Julián

    1988-08-01

    Full Text Available Water is a scare resource and for this reason it is necessary to use it wisely. This paper puts forward some techniques and strategies which have been developed in different countries, to minimize wasteful water consumption for domestic use. The reason for this is to avoid considerable public expense which is caused by the purifying of unneccessarily polluted water and by equipment and pipes which are too large for their purpose. Also this paper deals with the state of art on techniques saving money on sanitation and treatment of sewage.

    El agua es un recurso escaso y por lo tanto se considera cada vez más importante optimizar su uso. En este artículo se exponen algunas técnicas y estrategias desarrolladas, en diversos países, para minimizar las pérdidas y el consumo inútil de agua en usos domésticos y evitar los gastos que supone, a la colectividad, la depuración de agua innecesariamente contaminada, así como el sobredimensionamiento de equipos e instalaciones. También se presenta, de un modo general, el estado de la cuestión en cuanto a posibles ahorros económicos en saneamiento (entendido como las instalaciones sanitarias interiores de la vivienda y la red de evacuación exterior y en depuración de aguas residuales.

  15. Impact of advanced BWR core physics method on BWR core monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Moon, H; Wells, A [Siemens Power Corporation, Richland (United States)

    2000-07-01

    Siemens Power Corporation recently initiated development of POWERPLEX{sup TM}-III for delivery to the Grand Gulf Nuclear Power Station. The main change introduced in POWERPLEX{sup TM}-III as compared to its predecessor POWERPLEX{sup TM}-II is the incorporation of the advances BWR core simulator MICROBURN-B2. A number of issues were identified and evaluated relating to the implementation of MICROBURN-B2 and its impact on core monitoring. MICROBURN-B2 demands about three to five times more memory and two to three times more computing time than its predecessor MICROBURN-B in POWERPLEX {sup TM}-II. POWERPLEX{sup TM}-III will improve thermal margin prediction accuracy and provide more accurate plant operating conditions to operators than POWERPLEX{sup TM}-II due to its improved accuracy in predicted TIP values and critical k-effective. The most significant advantage of POWERPLEX{sup TM}-III is its capability to monitor a relaxed rod sequence exchange operation. (authors)

  16. Los Catastros y Registros de Aguas como herramientas indispensables para garantizar la gestión integrada y desarrollo ambientalmente sustentable de las aguas subterráneas

    Directory of Open Access Journals (Sweden)

    Diego De Rosa

    2013-12-01

    Full Text Available Los catastros y registros de aguas resultan ser herramientas indispensables para garantizar la  gestión integrada y desarrollo ambientalmente sustentable de las aguas subterráneas.  Ellos constituyen instrumentos fundamentales ya no solo para asegurar el control y vigilancia respecto a quién o quienes se otorgan estos permisos, derechos o usos -y a quienes éstos son transmitidos-; sino también, y fundamentalmente, para determinar  qué cantidad, qué calidad y qué regularidad se tiene o posee del recurso hídrico subterráneo. A pesar de estar legislados en normas provinciales, no en todas se hallan implementados.  He aquí unos breves contrastes surgidos entre un  análisis comparativo de legislación sobre aguas de la Provincia de Buenos Aires y Mendoza.

  17. Utilización terapéutica de las aguas y fangos mineromedicinales

    Directory of Open Access Journals (Sweden)

    Alicia Lagarto Parra

    2002-04-01

    Full Text Available Se presenta una revisión acerca del uso de las aguas y fangos mineromedicinales donde se tratan los antecedentes históricos, clasificación de las aguas minerales, indicaciones para la terapia dermatológica, aplicaciones terapéuticas de las aguas y fangos mineromedicinales en enfermedades como osteoartritis, osteoartrosis, artritis reumatoide y afecciones dermatológicasA review is made on the use of the mineral and medicinal waters and muds to deal with their historical background, classification of the mineral waters, indications for dermatological therapy, and therapeutic applications of the mineral and medicinal waters and muds in diseases such as osteoarthritis, osteoarthrosis, rheumatoid arthritis and skin affections.

  18. REGALÍA DE LAS AGUAS PÚBLICAS Y DOMINIO PÚBLICO HIDRÁULICO

    Directory of Open Access Journals (Sweden)

    Antonio Gil Olcina

    2010-01-01

    Full Text Available Hasta la promulgación de la Ley de 3 de agosto de 1866 sobre dominio, uso y provechamiento de aguas, en la España Peninsular el derecho sobre esta materia se adscribía a dos grandes tradiciones jurídicas: castellana y valenciana. Esta última, que informaría la susodicha norma, primer código español y europeo al respecto, acabaría por prevalecer, merced al destacado protagonismo en la redacción de aquélla del prestigio jurista Antonio Rodríguez de Cepeda, catedrático de Derecho Administrativo de la Universidad de Valencia, Decano de la Facultad de Derecho y del Colegio de Abogados, profundo conocedor del derecho de aguas valenciano. En la distinción del derecho foral valenciano entre aguas públicas y privadas, concepto el primero de contenido notoriamente más amplio que en las Partidas, quedaban sometidas aquéllas a la titularidad y dominio del Real Patrimonio. Dicha regalía sobre aguas públicas se halla en los orígenes del dominio público hidráulico que, ampliado y enriquecido por la Ley 29/1985, regula el modificado Texto Refundido de la Ley de Aguas.

  19. Development of membrane moisture separator for BWR off-gas system

    International Nuclear Information System (INIS)

    Ogata, H.; Kawamura, S.; Kumasaka, M.; Nishikubo, M.

    2001-01-01

    In BWR plant off-gas treatment systems, dehumidifiers are used to maintain noble gas adsorption efficiency in the first half of the charcoal hold-up units. From the perspective of simplifying and reducing the cost of such a dehumidification system, Japanese BWR utilities and plant fabricators have been developing a dehumidification system employing moisture separation membrane of the type already proven in fields such as medical instrumentation and precision measuring apparatus. The first part of this development involved laboratory testing to simulate the conditions found in an actual off-gas system, the results of which demonstrated satisfactory results in terms of moisture separation capability and membrane durability, and suggested favorable prospects for application in actual off-gas systems. Further, in-plant testing to verify moisture separation capability and membrane durability in the presence of actual gases is currently underway, with results so far suggesting that the system is capable of obtaining good moisture separation capability. (author)

  20. Flux and power distributions in BWR multi-bundle fuel arrays

    International Nuclear Information System (INIS)

    Cheng, H.S.

    1976-02-01

    Multi-bundle calculations have been performed in order to shed some light on an abnormal TIP trace recently discovered in a BWR/3. Transport theory was employed to perform the calculations with ENDF/B-IV data. The results indicate that a strong variation of the TIP reading does exist along the narrow water gap of a BWR due to the steep gradient of the thermal neutron flux; the maxima occurring at the intersections of the water gaps and the minima in between. Using this characteristic behavior of the TIP reading, together with the observed normal TIP trace, the abnormal behavior of the affected TIP trace exhibiting three peaks along the channel was roughly simulated. The calculations confirmed that the observed TIP trace anomaly was caused by the severe bending of the affected instrument tube as was actually discovered. The effect of hot water intrusion into the TIP guide tube, as well as that of loading the new 8 x 8 reload bundles, was also evaluated

  1. Damage by radiation in structural materials of BWR reactor vessels

    International Nuclear Information System (INIS)

    Robles, E.; Balcazar, M.; Alpizar, A.M.; Calderon, B.E.

    2002-01-01

    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 18 n/cm 2 ) in the TRIGA Mark III Salazar reactor and separately with Ni +3 ions in a Tandetrom accelerator (E= 4.8 MeV and an ion flux rank of 0.1 to 53 ions/A 2 ). (Author)

  2. Studies of fragileness in steels of vessels of BWR reactors

    International Nuclear Information System (INIS)

    Robles, E.F.; Balcazar, M.; Alpizar, A.M.; Calderon, B.E.

    2003-01-01

    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 18 n/cm 2 ) in the TRIGA MARK lll reactor and separately with Ni +3 ions in a Tandetrom accelerator, E = 4.8 MeV and range of the ionic flow of 0.1 to 53 iones/A 2 . (Author)

  3. Accident sequence analysis for a BWR [Boiling Water Reactor] during low power and shutdown operations

    International Nuclear Information System (INIS)

    Whitehead, D.W.; Hake, T.M.

    1990-01-01

    Most previous Probabilistic Risk Assessments have excluded consideration of accidents initiated in low power and shutdown modes of operation. A study of the risk associated with operation in low power and shutdown is being performed at Sandia National Laboratories for a US Boiling Water Reactor (BWR). This paper describes the proposed methodology for the analysis of the risk associated with the operation of a BWR during low power and shutdown modes and presents preliminary information resulting from the application of the methodology. 2 refs., 2 tabs

  4. 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.

  5. Nuevos retos en depuración y desalación de aguas en España

    OpenAIRE

    Olcina Cantos, Jorge

    2002-01-01

    La reciente aprobación del Plan Hidrológico Nacional ha abierto un nuevo marco de actuaciones para la planificación de los recursos de agua en España. Depuración y reutilización de aguas residuales y desalación de agua marina o salobre continental tienen un significado todavía pequeño entre los recursos hídricos que se aprovechan anualmente. Sin embargo, ofrecen grandes posibilidades de futuro dentro de la nueva concepción de la planificación de recursos de agua que valora el a...

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

    OpenAIRE

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

    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...

  7. Estudio de la contaminación de las aguas del río Chillón

    OpenAIRE

    Reyes Cubas, Carmen Martha; Reyes Cubas, Carmen Martha

    2012-01-01

    En el Perú uno de los principales problemas ambientales, generalmente es ocasionado por contaminación de aguas y residuos sólidos. El estado y los gobiernos locales le han dado poca importancia a la calidad del agua y los esfuerzos por detener este problema aun siguen siendo incipientes. Las aguas del río Chillón han sufrido un incremento en la contaminación de sus aguas, la contaminación a lo largo de la Cuenca del río Chillón depende de una serie de factores entre los que se destacan: la in...

  8. Seismic PRA of a BWR plant

    International Nuclear Information System (INIS)

    Nishio, Masahide; Fujimoto, Haruo

    2014-01-01

    Since the occurrence of nuclear power plant accidents in the Fukushima Daichi nuclear power station, the regulatory framework on severe accident (SA) has been discussed in Japan. The basic concept is to typify and identify the accident sequences leading to core/primary containment vessel (PCV) damage and to implement SA measures covering internal and external events extensively. As Japan is an earthquake-prone country and earthquakes and tsunami are important natural external events for nuclear safety of nuclear power plants, JNES performed the seismic probabilistic risk assessment (PRA) on a typical nuclear power plant and evaluated the dominant accident sequences leading to core/PCV damage to discuss dominant scenarios of severe accident (SA). The analytical models and the results of level-1 seismic PRA on a 1,100 MWe BWR-5 plant are shown here. Seismic PRA was performed for a typical BWR5 plant. Initiating events with large contribution to core damage frequency are the loss of all AC powers (station blackout) and the large LOCA. The top of dominant accident sequences is the simultaneous occurrence of station blackout and large LOCA. Important components to core damage frequency are electric power supply equipment. It needs to keep in mind that the results are influenced on site geologic characteristic to a greater or lesser. In the process of analysis, issues such as conservative assumptions related to damages of building or structure and success criteria for excessive LOCA are left to be resolved. These issues will be further studied including thermal hydric analysis in the future. (authors)

  9. Experimental study on reduced moderation BWR with Advanced Recycle System (BARS)

    International Nuclear Information System (INIS)

    Hiraiwa, K.; Yoshioka, K.; Yamamoto, Y.; Akiba, M.; Yamaoka, M.; Abe, N.; Mimatsu, J.

    2004-01-01

    Experimental study has been done for reduced-moderation spectrum boiling water reactor named BARS (BWR with Advanced Recycle System). The critical assembly experiment for triangular tight uranium lattice has been done in TOSHIBA critical assembly (NCA). Experimental method based on modified conversion ratio was adopted to evaluate the void reactivity effect. Void fraction was simulated by formed polystyrene in this experiment. The measured void coefficient for tight uranium lattice agreed with calculation. The thermal hydraulic test study has been done to study the coolability of BARS lattice. Visual test and high-pressure thermal hydraulic test have been done as the thermal hydraulic test. Visual test has indicated the flow behavior for BARS lattice is same as that of current BWR. The high-pressure thermal hydraulic test has indicated the applicability of modified Arai's correlation to the BARS lattice. (authors)

  10. Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

    International Nuclear Information System (INIS)

    Greneche, D.

    2014-01-01

    This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

  11. La ley de aguas y el principio de celeridad

    OpenAIRE

    Hidalgo Pulía, Ana María; Moyón Altamirano, Paola Alexandra

    2012-01-01

    La presente tesis intitulada “La Ley de Aguas y el Principio de celeridad” se realiza como requisito previo a la obtención del título de Magíster en Derecho Civil y Procesal Civil, se desarrolla en cuatro capítulos, cuyo contenido se detalla a continuación. En el Capítulo I, se aborda el problema que da lugar a esta investigación, esto es, la inaplicabilidad del principio de celeridad en los procesos de agua. El objetivo general proponer un anteproyecto de ley reformatorio a la Ley de A...

  12. Tema 1. Introducción a la geoquímica de las aguas subterráneas

    OpenAIRE

    Boluda Botella, Nuria

    2010-01-01

    Tema 1. Introducción a la geoquímica de las aguas subterráneas. Se presenta una introducción de la asignatura. Se manejan conceptos sobre calidad de aguas, muestreo y análisis químico de las aguas, procesos de contaminación, con énfasis en la geoquímica de la intrusión marina.

  13. 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.

  14. Estrategias para coadyuvar a la sustentabilidad en la gestión del agua en la ciudad de México

    Directory of Open Access Journals (Sweden)

    J. Jesús Ceja Pizano

    2013-06-01

    Full Text Available 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 cual se hace necesaria una guía de estrategias que marquen el camino a seguir involucrando a todos los actores y recursos para concluir exitosamente la meta: agua para todos sin privilegio.

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

    Directory of Open Access Journals (Sweden)

    Elizabeth Hernández-Acosta

    2014-01-01

    Full Text Available 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, Tulancingo, Hidalgo. El análisis bacteriológico y de helmintos se hizo acorde con las metodologías señaladas en la NMX-AA-003-1980, NOM-001-SEMARNAT-1996, PROY NMX-AA 042-SCFI-2008 y en la sección 9810 APHA. Se determinaron 16 sitios de muestreo de aguas en los canales de riego y se tomaron 54 muestras, tanto de suelo como de plantas. Las concentraciones más altas de coliformes fecales fueron 2 x 1010 NMP·100 mL-1 de agua, 109 NMP·100 g-1 de suelo, 109 NMP·100 g-1 de raíz y 3 x 109 NMP·100 g-1 de tallo. Once de los 16 sitios de muestreo tuvieron helmintos. Se sugiere tratar las aguas residuales antes de su uso, para evitar problemas de salud entre los usuarios.

  16. Diseño de nuevos catalizadores con paladio para la eliminación de bromatos en agua

    OpenAIRE

    Valera Evaristo, Ainhoa

    2016-01-01

    [ES] El presente Trabajo de Fin de Grado se centra en el tratamiento del agua contaminada por bromatos, ya que éstos se han clasificado en el grupo 2B (posiblemente cancerígeno para el ser humano). La Organización Mundial de la Salud establece como máximo valor admisible de bromatos en agua potable el de 10 µg/L. La contaminación del agua por bromatos suele producirse en los procesos de tratamiento de desinfección del agua por ozonización, ya que los bromuros presentes en ella ...

  17. Aging assessment of BWR control rod drive systems

    International Nuclear Information System (INIS)

    Greene, R.H.

    1992-01-01

    This Phase 1 Nuclear Plant Aging Research (NPAR) study examines the aging phenomena associated with boiling water reactor (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 NPRDS failure cases attributed to the CRD system, and (4) personal information exchange. As part of this study, nearly 3,500 NPRDS failure reports have been analyzed to examine the prevailing failure trends for CRD system components. An investigation has been conducted that summarizes the occurrence frequency of these component failures, discovery methods, reported failure causes, their respective symptoms, and actions taken by utilities to restore component and system service. The results of this research have identified the predominant CRDM failure modes and causes. In addition, recommendations are presented regarding specific actions that utilities can implement to mitigate CRDM aging. An evaluation has also been made of certain practices and tooling which have enabled some utilities to reduce ALARA exposures received from routine CRDM replacement and rebuilding activities

  18. Aging assessment of BWR control rod drive systems

    International Nuclear Information System (INIS)

    Greene, R.H.

    1991-01-01

    This study examines the aging phenomena associated with boiling water reactor (BWR) control rod drive mechanisms (CRDMs) and assess 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 Nuclear Plant Reliability Data System (NPRDS) failure cases attributed to the CRD system, and (4) personal information exchange with industry experts. As part of this study, nearly 3500 NPRDS failure reports have been analyzed to examine the prevailing failure trends for CRD system components. An investigation was conducted to summarize the occurrence frequency of these component failures, discovery methods, reported failure causes, their respective symptoms, and actions taken by utilities to restore component and system service. The results of this research have identified the predominant CRDM failure modes and causes. In addition, recommendations are presented that identify specific actions utilities can implement to mitigate CRDM aging. An evaluation has also been made of certain maintenance practices and tooling which have enabled some utilities to reduce ALARA exposures received from routine CRDM replacement and rebuilding activities. 5 refs., 8 figs., 2 tabs

  19. Appraisal of BWR plutonium burners for energy centers

    International Nuclear Information System (INIS)

    Williamson, H.E.

    1976-01-01

    The design of BWR cores with plutonium loadings beyond the self-generation recycle (SGR) level is investigated with regard to their possible role as plutonium burners in a nuclear energy center. Alternative plutonium burner approaches are also examined including the substitution of thorium for uranium as fertile material in the BWR and the use of a high-temperature gas reactor (HTGR) as a plutonium burner. Effects on core design, fuel cycle facility requirements, economics, and actinide residues are considered. Differences in net fissile material consumption among the various plutonium-burning systems examined were small in comparison to uncertainties in HTGR, thorium cycle, and high plutonium-loaded LWR technology. Variation in the actinide content of high-level wastes is not likely to be a significant factor in determining the feasibility of alternate systems of plutonium utilization. It was found that after 10,000 years the toxicity of actinide high-level wastes from the plutonium-burning fuel cycles was less than would have existed if the processed natural ores had not been used for nuclear fuel. The implications of plutonium burning and possible future fuel cycle options on uranium resource conservation are examined in the framework of current ERDA estimates of minable uranium resources

  20. Aging assessment of BWR control rod drive systems

    International Nuclear Information System (INIS)

    Greene, R.H.

    1991-01-01

    This Phase 1 Nuclear Plant Aging Research (NPAR) study examines the aging phenomena associated with boiling water reactor (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 NPRDS failure cases attributed to the CRD system, and (4) personal information exchange. As part of this study, nearly 3,500 NPRDS failure reports have been analyzed to examine the prevailing failure trends for CRD system components. An investigation has been conducted that summarizes the occurrence frequency of these component failures, discovery methods, reported failure causes, their respective symptoms, and actions taken by utilities to restore component and system service. The results of this research have identified the predominant CRDM failure modes and causes. In addition, recommendations are presented regarding specific actions that utilities can implement to mitigate CRDM aging. An evaluation has also been made of certain practices and tooling which have enabled some utilities to reduce ALARA exposures received from routine CRDM replacement and rebuilding activities

  1. Safety evaluation of BWR off-gas treatment systems

    International Nuclear Information System (INIS)

    Schultz, R.J.; Schmitt, R.C.

    1975-01-01

    Some of the results of a safety evaluation performed on current generic types of BWR off-gas treatment systems including cooled and ambient temperature adsorber beds and cryogenics are presented. The evaluation covered the four generic types of off-gas systems and the systems of five major vendors. This study was part of original work performed under AEC contract for the Directorate of Regulatory Standards. The analysis techniques employed for the safety evaluation of these systems include: Fault Tree Analysis; FMECA (Failure Mode Effects and Criticality Analysis); general system comparisons, contaminant, system control, and design adequacy evaluations; and resultant Off-Site Dose Calculations. The salient areas presented are some of the potential problem areas, the approach that industry has taken to mitigate or design against potential upset conditions, and areas where possible deficiencies still exist. Potential problem areas discussed include hydrogen detonation, hydrogen release to equipment areas, operator/automatic control interface, and needed engineering evaluation to insure safe system operation. Of the systems reviewed, most were in the category of advanced or improved over that commonly in use today, and a conclusion from the study was that these systems offer excellent potential for noble gas control for BWR power plants where more stringent controls may be specified -- now or in the future. (U.S.)

  2. A detailed BWR recirculation loop model for RELAP

    Energy Technology Data Exchange (ETDEWEB)

    Araiza-Martínez, Enrique, E-mail: enrique.araiza@inin.gob.mx; Ortiz-Villafuerte, Javier, E-mail: javier.ortiz@inin.gob.mx; Castillo-Durán, Rogelio, E-mail: rogelio.castillo@inin.gob.mx

    2017-01-15

    Highlights: • A new detailed BWR recirculation loop model was developed for RELAP. • All jet pumps, risers, manifold, suction and control valves, and recirculation pump are modeled. • Model is tested against data from partial blockage of two jet pumps. • For practical applications, simulation results showed good agreement with available data. - Abstract: A new detailed geometric model of the whole recirculation loop of a BWR has been developed for the code RELAP. This detailed model includes the 10 jet pumps, 5 risers, manifold, suction and control valves, and the recirculation pump, per recirculation loop. The model is tested against data from an event of partial blockage at the entrance nozzle of one jet pump in both recirculation loops. For practical applications, simulation results showed good agreement with data. Then, values of parameters considered as figure of merit (reactor power, dome pressure, core flow, among others) for this event are compared against those from the common 1 jet pump per loop model. The results show that new detailed model led to a closer prediction of the reported power change. The detailed recirculation loop model can provide more reliable boundary condition data to a CFD models for studies of, for example, flow induced vibration, wear, and crack initiation.

  3. Memorias del proyecto cultural Agua: un patrimonio que circula de mano en mano

    Directory of Open Access Journals (Sweden)

    Sandra Concha Roldan

    2013-09-01

    Full Text Available El interés de Banco de la República en trabajar un proyecto cultural sobre el agua tiene varios orígenes. Las inundaciones del 2010 le recordaron a Colombia que pase lo que pase, el agua vuelve a su cauce y recuerda su camino. Esos cauces se organizan en cuencas hidrográficas que conectan y estructuran la vida de quienescomparten el territorio. Las cuencas unen y afectan sin atender a las fronteras políticas y por ello la sostenibilidad del agua es una responsabilidad compartida, su mal uso nos afecta a todos y su futuro es una responsabilidad prioritaria del presente.

  4. Maintenance of BWR control rod drive mechanisms

    International Nuclear Information System (INIS)

    Greene, R.H.

    1991-01-01

    Control rod drive mechanism (CRDM) replacement and rebuilding is one of the highest dose, most physically demanding, and complicated maintenance activities routinely accomplished by BWR utilities. A recent industry workshop sponsored by the Oak Ridge National Laboratory, which dealt with the effects of CRDM aging, revealed enhancements in maintenance techniques and tooling which have reduced ALARA, improved worker comfort and productivity, and have provided revised guidelines for CRDM changeout selection. Highlights of this workshop and ongoing research on CRDM aging are presented in this paper

  5. Sensitiaztion of austenitic stainless steels and its significance as regards stress-corrosion cracking of BWR pipe systems

    International Nuclear Information System (INIS)

    Roberts, W.; Otterberg, R.

    1984-05-01

    A critical literature evaluation dealing with sensitization of austenitic stainless steels and its importance in the context of intergranular stress-corrosion cracking (IGSCC) in high-temperature, oxygenated water is presented. The factors influencing the degree of sensitization are discussed, principally for type-304 stainless steels, both as regards sensitization arising as a result of isothermal holding within the critical temperature range and weld sensitization. The phenomenon of low-temperature sensitization is described and its potential significance under BWR operating conditions speculated upon. The principal features of and mechanisms controlling IGSCC of sensitized 304 steels in BWR-type environments are reviewed and some thoughts are given to the relevance of laboratory SCC testing in predicting the occurrence of cracking in actual BWR systems. Finally various countermeasures against IGSCC in existing and projected reactors are presented and discussed. (Author)

  6. Rediseño y construcción de un sistema de filtro de agua automático y estudio para la disminución de la velocidad del agua en el canal

    OpenAIRE

    Cueva Jiménez, Jason Satalin

    2012-01-01

    El presente documento trata sobre el rediseño de un filtro de agua automático cuya finalidad es liberar de material flotante al agua que ingresa desde el Río Monjas en Bocatoma y que fluye por el canal de conducción hacia las turbinas Pelton de la planta generadora de energía de la central hidroeléctrica de Vindobona. La mayoría de material flotante que circula hacia el filtro es liviano ya que permanecen en la superficie, además las partículas más pesadas son separadas del agua en las pis...

  7. Application of eddy current inspection to the Inconel weld of BWR internals

    International Nuclear Information System (INIS)

    Machida, Eiji; Yusa, Noritaka

    2004-01-01

    In order to definite the basic specifications of application of ECT (Eddy Current Test) to Inconel weld of BWR internals, the inspection and numerical analysis were carried out. The characteristics of the existing ECT probe were studied by making sample as same as CRD stud tube, measuring the relative permeability and electric conductivity of Inconel and alloy and evaluating ECT probe. On the basis of the results obtained, the basic specifications were determined and a new eddy current probe for inspection was designed and produced. The new ECT probe was able to detect small notch in Inconel weld, to classify the defects by eddy current inspection signal and sizing the length and depth. It is concluded that the new ECT probe is able to apply the Inconel weld of BWR internals. (S.Y.)

  8. IFPE/IFA-432, Fission Gas Release, Mechanical Interaction BWR Fuel Rods, Halden

    International Nuclear Information System (INIS)

    Turnbull, J.A.

    1996-01-01

    Description: It contains data from experiments that have been performed at the IFE/OECD Halden Reactor Project, available for use in fuel performance studies. It covers experiments on thermal performance, fission product release, clad properties and pellet clad mechanical interaction. It includes also experimental data relevant to high burn-up behaviour. IFA-432: Measurements of fuel temperature response, fission gas release and mechanical interaction on BWR-type fuel rods up to high burn-ups. The assembly featured several variations in rod design parameters, including fuel type, fuel/cladding gap size, fill gas composition (He and Xe) and fuel stability. It contained 6 BWR-type fuel rods with fuel centre thermocouples at two horizontal planes, rods were also equipped with pressure transducers and cladding extensometers. Only data from 6 rods are compiled here

  9. Feasibility study on development of plate-type heat exchanger for BWR plants

    International Nuclear Information System (INIS)

    Ohyama, Nobuhiro; Suda, Kenichi; Ogata, Hiroshi; Matsuda, Shinichi; Nagasaka, Kazuhiro; Fujii, Toshi; Nozawa, Toshiya; Ishihama, Kiyoshi; Higuchi, Tomokazu

    2004-01-01

    In order to apply plate-type heat exchanger to RCW, TCW and FPC system in BWR plants, heat test and seismic test of RCW system heat exchanger sample were carried out. The results of these tests showed new design plate-type heat exchanger satisfied the fixed pressure resistance and seismic resistance and keep the function. The evaluation method of seismic design was constructed and confirmed by the results of tests. As anti-adhesion measure of marine organism, an ozone-water circulation method, chemical-feed method and combination of circulation of hot water and air bubbling are useful in place of the chlorine feeding method. Application of the plate-type heat exchanger to BWR plant is confirmed by these investigations. The basic principles, structure, characteristics, application limit and reliability are stated. (S.Y.)

  10. TVA experience in BWR reload design and licensing

    International Nuclear Information System (INIS)

    Robertson, J.D.

    1986-01-01

    TVA has developed and implemented the capability to perform BWR reload core design and licensing analyses. The advantages accruing from this capability include the tangible cost-savings from performing reload analyses in-house. Also, ''intangible'' benefits such as increased operating flexibility and the ability to accommodate multivendor fuel designs have been demonstrated. The major disadvantage with performing in-house analyses is the cost associated with development and maintenance of the analytical methods and staff expertise

  11. TIPOLOGÍAS DE CONSUMO DE AGUA EN ABASTECIMIENTOS URBANO-TURÍSTICOS DE LA COMUNIDAD VALENCIANA

    Directory of Open Access Journals (Sweden)

    Antonio M. Rico Amorós

    2007-01-01

    Full Text Available El análisis de las unidades de consumo de agua asociadas a las actividades turísticas resulta imprescindible para valorar la efi ciencia ambiental y socioeconómica del modelo de desarrollo territorial urbano-turístico valenciano. Este trabajo analiza el gasto de agua urbano-turístico en las distintas formas de implantación territorial de estas actividades, especialmente en la modalidades de alojamiento hotelero y residencial, comparando la eficiencia de la gestión del agua potable en modelos urbanos de baja densidad y de alta densidad (concentrados. Para dicho fin se ha recurrido a un método empírico, mediante encuestas y trabajos de campo realizados en empresas de agua potable de los principales destinos turísticos de la Comunidad Valenciana. Con la colaboración de estas empresas, se han analizado los principales sistemas de abastecimiento para valorar las tendencias de consumo, la estacionalidad, el rendimiento técnico de las redes y el ciclo integral del agua. Asimismo, se incluyen resultados sobre el consumo de agua realizado en hoteles, en sus diferentes categorías. También en las distintas categorías de viviendas ocupadas por turistas y residentes en periodos de vacaciones, y en otros establecimientos vinculados a las actividades turísticas (restaurantes, camping, etc.

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

    International Nuclear Information System (INIS)

    Bregani, F.

    1990-01-01

    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, HNO 3 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

  13. Analysis of void reactivity measurements in full MOX BWR physics experiments

    International Nuclear Information System (INIS)

    Ando, Yoshihira; Yamamoto, Toru; Umano, Takuya

    2008-01-01

    In the full MOX BWR physics experiments, FUBILA, four 9x9 test assemblies simulating BWR full MOX assemblies were located in the center of the core. Changing the in-channel moderator condition of the four assemblies from 0% void to 40% and 70% void mock-up, void reactivity was measured using Amplified Source Method (ASM) technique in the subcritical cores, in which three fission chambers were located. ASM correction factors necessary to express the consistency of the detector efficiency between measured core configurations were calculated using collision probability cell calculation and 3D-transport core calculation with the nuclear data library, JENDL-3.3. Measured reactivity worth with ASM correction factor was compared with the calculated results obtained through a diffusion, transport and continuous energy Monte Carlo calculation respectively. It was confirmed that the measured void reactivity worth was reproduced well by calculations. (author)

  14. Procesos de eliminación de contaminantes en aguas potabilizables

    OpenAIRE

    Acebrón Arribas, Francisco Javier

    2010-01-01

    El presente proyecto consiste en la preparación de los cálculos y planos necesarios para la realización de una estación de tratamiento de agua para su potabilización y posterior consumo doméstico, con la utilización del carbón activo como tratamiento de afino. Tanto los cálculos como los planos del presente proyecto se centran en el sistema y complementos necesarios para el tratamiento del agua potable y para el sistema de almacenamiento de los componentes que se requieren ...

  15. Demanda de agua en hogares urbanos y cambios tarifarios en Bogotá

    Directory of Open Access Journals (Sweden)

    Edwin Oswaldo Gil Mateus

    2011-06-01

    Full Text Available La teoría estándar del consumidor plantea que los agentes económicosresponden ante los cambios en los precios de un bien. Sin embargo, no todos los agentes responden con la misma velocidad ante estos cambios en algunos bienes particulares, este es el caso del agua potable. Este artículo analiza lacorrelación entre el consumo de agua por cuenta-contrato para cada estrato y el componente de cargo básico de la tarifa, para lo cual se estiman las elasticidades del consumo con respecto al rezago de un periodo de la tarifa. Así, se plantea que la tarifa variable básica es una herramienta efectiva para el control de consumos excesivos de agua en los estratos bajos —1, 2 y 3—, por el contrario, este no es un mecanismo eficaz en la disminución de los consumos por hogar para los estratos altos —4, 5 y 6—. Finalmente, se presentan alternativas que se sugieren en una parte de la literatura especializada, dirigidas al establecimiento de programas de gestión de la demanda de agua urbana.

  16. CALIDAD DEL AGUA EN EL ÁREA COSTERA DE SANTA MARTA (COLOMBIA

    Directory of Open Access Journals (Sweden)

    FRANCISCO GARCÍA

    2012-01-01

    Full Text Available Se usaron técnicas de análisis estadístico multivariado, para determinar la variación temporal y espacial de la calidad del agua en la zona costera de Santa Marta, donde se ubica un emisario submarino que descarga 1 m3/s de aguas residuales domésticas. La ANOVA de dos vías, los análisis de clúster y de componentes principales mas la interpolación de krigging, fueron considerados para este análisis. En la variación temporal se encontraron diferencias que marcan en el año dos periodos de tiempos heterogéneos, de diciembre a abril la concentración de los parámetros de calidad del agua es más alta. El resto del año (mayo, junio, agosto - noviembre, exceptuando el mes de julio donde se presentaron concentraciones altas, se registran concentraciones sensiblemente inferiores. En la variación espacial se reportan dos grupos de áreas en las cuales la calidad del agua es diferente, dicha diferencia está relacionada con la cercanía a la descarga del emisario submarino.

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

    International Nuclear Information System (INIS)

    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; 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)

  19. Patógenos e indicadores microbiológicos de calidad del agua para consumo humano

    Directory of Open Access Journals (Sweden)

    Sandra Ríos-Tobón

    2017-05-01

    Full Text Available Las mejoras en el suministro de agua son oportunidades para solucionar problemas de Salud Pública. De ahí la importancia de establecer modelos de evaluación y gestión integral que garanticen su calidad. Actualmente hay múltiples metodologías para detectar la contaminación microbiana del agua. Sin embargo, los elevados costos que representan, los tiempos de análisis y aislamiento en cultivo de microorganismos, han sido obstáculo para establecer la calidad microbiana del agua para consumo humano. El uso de microorganismos bioindicadores de calidad del agua disminuye los costos y facilita la implementación de medidas eficientes de tratamiento, control del agua y de enfermedades asociadas a su transmisión. El objetivo de la revisión fue describir los principales indicadores microbiológicos empleados para la evaluación del agua potable, como elementos clave para proponer un nuevo esquema de monitoreo en Colombia. Los resultados permiten considerar como bioindicadores, además de las bacterias y protozoos establecidos en la norma, algunos agentes microbianos como virus u otras bacterias y parásitos. Por otro lado indican la necesidad de establecer valores de referencia y definir los microorganismos a emplear con base en evaluaciones específicas de la situación microbiana del agua en monitoreos de validación, operación y verificación. Esta revisión aporta información importante para la actualización de la norma colombiana con base en el conocimiento de estándares internacionales, nacionales y locales.

  20. Effect of the inlet throttling on the thermal-hydraulic instability of the natural circulation BWR

    International Nuclear Information System (INIS)

    Furuya, Masahiro; Inada, Fumio; Yoneda, Kimitoshi

    1997-01-01

    Although it is well-established that inlet restriction has a stabilizing for forced circulation BWR, the effect of inlet on the thermal-hydraulic stability of natural circulation BWR remains unknown since increasing inlet restriction affect thermal-hydraulic stability due to reduction of the recirculation flow rate. Therefore experiments have been conducted to investigate the effect of inlet restriction on the thermal-hydraulic stability. A test facility used in this experiments was designed and constructed to have non-dimensional values which are nearly equal to those of natural circulation BWR. Experimental results showed that driving force of the natural circulation was described as a function of heat flux and inlet subcooling independent of inlet restriction. Stability maps in reference to the channel inlet subcooling, heat flux were presented for various inlet restriction which were carried out by an analysis based on the homogeneous flow various using this function. Instability region during the inlet subcooling shifted to the higher inlet subcooling with increasing inlet restriction and became larger with increasing heat flux. (author)

  1. Development of a coordinated control system for BWR nuclear power plant and HVDC transmission system

    International Nuclear Information System (INIS)

    Ishikawa, M.; Hara, T.; Hirayama, K.; Sekiya, K.

    1986-01-01

    The combined use of dc and ac transmissions or so-called hybrid transmission was under study, employing both dc and ac systems to enable stable transmission of 10,000 MW of electric power generated by the BWR nuclear plant, scheduled to be built about 800 km away from the center of the load. It was thus necessary to develop a hybrid power transmission control system, the hybrid power transmission system consisting of a high voltage dc transmission system (HVDC) and an ultrahigh ac transmission system (UHVAC). It was also necessary to develop a control system for HVDC transmission which protects the BWR nuclear power plant from being influenced by any change in transmission mode that occurs as a result of faults on the UHVAC side when the entire power of the BWR plant is being sent by the HVDC transmission. This paper clarifies the requirements for the HVDC system control during hybrid transmission and also during dc transmission. The control method that satisfies these requirements was studied to develop a control algorithm

  2. CECP, Decommissioning Costs for PWR and BWR

    International Nuclear Information System (INIS)

    Bierschbach, M.C.

    1997-01-01

    1 - Description of program or function: The Cost Estimating Computer Program CECP, designed for use on an IBM personal computer or equivalent, was developed for estimating the cost of decommissioning boiling water reactor (BWR) and light-water reactor (PWR) power stations to the point of license termination. 2 - Method of solution: Cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial volume and costs; and manpower staffing costs. Using equipment and consumables costs and inventory data supplied by the user, CECP calculates unit cost factors and then combines these factors with transportation and burial cost algorithms to produce a complete report of decommissioning costs. In addition to costs, CECP also calculates person-hours, crew-hours, and exposure person-hours associated with decommissioning. 3 - Restrictions on the complexity of the problem: The program is designed for a specific waste charge structure. The waste cost data structure cannot handle intermediate waste handlers or changes in the charge rate structures. The decommissioning of a reactor can be divided into 5 periods. 200 different items for special equipment costs are possible. The maximum amount for each special equipment item is 99,999,999$. You can support data for 10 buildings, 100 components each; ESTS1071/01: There are 65 components for 28 systems available to specify the contaminated systems costs (BWR). ESTS1071/02: There are 75 components for 25 systems available to specify the contaminated systems costs (PWR)

  3. A BWR licensing experience in the USA

    International Nuclear Information System (INIS)

    Powers, J.; Ogura, C.; Arai, K.; Thomas, S.; Mookhoek, B.

    2015-09-01

    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)

  4. 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)

  5. BWR type reactors

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1986-01-01

    Purpose: To enable to remove water not by way of mechanical operation in a reactor core and improve the fuel economy in BWR type reactors. Constitution: A hollow water removing rod of a cross-like profile made of material having a smaller neutron absorption cross section than the moderator is disposed to the water gap for each of unit structures composed of four fuel assemblies, and water is charged and discharged to and from the water removing rod. Water is removed from the water removing rod to decrease the moderators in the water gap to carry out neutron spectrum shift operation from the initial to the medium stage of reactor core cycles. At the final stage of the cycle, airs in the water removing rod are extracted and the moderator is introduced. The moderator is filled and the criticality is maintained with the accumulated nuclear fission materials. The neutron spectrum shift operation can be attained by eliminating hydrothermodynamic instability and using a water removing rod of a simple structure. (Horiuchi, T.)

  6. Planes de seguridad del agua. Fundamentos y perspectivas de implementación en Colombia

    Directory of Open Access Journals (Sweden)

    Andrea Pérez Vidal

    2009-09-01

    Full Text Available 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 están o- rientadas al desarrollo de metodologías para evaluación y gestión del riesgo en los sistemas de abastecimiento para proteger la salud pública. La aplicación de los Planes de Seguridad del Agua (PSA es una práctica orientada al suministro de agua de cali- dad, cuya estructura se basa en principios de barreras múltiples, análisis de peligros, puntos críticos de control (APPCC y hacer- camientos sistemáticos de gestión como la ISO 9001:2000. Experiencias internacionales han demostrado los beneficios de im- plementarlos como estrategia para garantizar la calidad del agua potable y la protección de la salud pública. En Colombia, la actual normatividad sobre agua potable exige la implementación de mapas de riesgos y evaluación de índices de calidad, lo que posibilitará que los PSA tengan gran perspectiva de implementación en el corto plazo.

  7. Transmutation of minor actinide using BWR fueled mixed oxide

    International Nuclear Information System (INIS)

    Susilo, Jati

    2000-01-01

    Nuclear spent fuel recycle has a strategic importance in the aspect of nuclear fuel economy and prevention of its spread-out. One among other application of recycle is to produce mixed oxide fuel (Mo) namely mixed Plutonium and uranium oxide. As for decreasing the burden of nuclear high level waste (HLW) treatment, transmutation of minor actinide (MA) that has very long half life will be carried out by conversion technique in nuclear reactor. The purpose of this study was to know influence of transition fuel cell regarding the percent weight of transmutation MA in the BWR fueled MOX. Calculation of cell BWR was used SRAC computer code, with assume that the reactor in equilibrium. The percent weight of transmutation MA to be optimum by increasing the discharge burn-up of nuclear fuel, raising ratio of moderator to fuel volume (Vm/Vf), and loading MA with percent weight about 3%-6% and also reducing amount of percent weight Pu in MOX fuel. For mixed fuel standard reactor, reactivity value were obtained between about -50pcm ∼ -230pcm for void coefficient and -1.8pcm ∼ -2.6pcm for fuel temperature coefficient

  8. Evaluation of thermal margin during BWR neutron flux oscillation

    International Nuclear Information System (INIS)

    Takeuchi, Yutaka; Takigawa, Yukio; Chuman, Kazuto; Ebata, Shigeo

    1992-01-01

    Fuel integrity is very important, from the view point of nuclear power plant safety. Recently, neutron flux oscillations were observed at several BWR plants. The present paper describes the evaluations of the thermal margin during BWR neutron flux oscillations, using a three-dimensional transient code. The thermal margin is evaluated as MCPR (minimum critical power ratio). The LaSalle-2 event was simulated and the MCPR during the event was evaluated. It was a core-wide oscillation, at which a large neutron flux oscillation amplitude was observed. The results indicate that the MCPR had a sufficient margin with regard to the design limit. A regional oscillation mode, which is different from a core-wide oscillation, was simulated and the MCPR response was compared with that for the LaSalle-2 event. The MCPR decrement is greater in the regional oscillation, than in the core wide -oscillation, because of the sensitivity difference in a flow-to-power gain. A study was carried out about regional oscillation detectability, from the MCPR response view point. Even in a hypothetically severe case, the regional oscillation is detectable by LPRM signals. (author)

  9. Logical model for the control of a BWR turbine

    International Nuclear Information System (INIS)

    Vargas O, Y.; Amador G, R.; Ortiz V, J.; Castillo D, R.

    2009-01-01

    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)

  10. Determinantes socioeconómicos de la calidad del agua superficial en México

    Directory of Open Access Journals (Sweden)

    María Eugenia Ibarrarán Viniegra

    2017-04-01

    Full Text Available La calidad y la disponibilidad de agua de los ríos en México son cruciales para el desarrollo regional y nacional, pero tienen problemas graves; en 2006, 74 por ciento de las aguas superficiales tenía grados diferentes de contaminación. El objetivo de esta investigación es identificar la influencia de algunas variables socioeconómicas en la calidad del agua superficial en las regiones hidrológicas administrativas, y proponer acciones para mejorarla. Según el análisis econométrico, la actividad económica y la densidad poblacional perjudican la calidad del agua superficial en dichas regiones. Es poco el efecto del aumento de las plantas de tratamiento de agua en cuanto a la contaminación; el incremento en el caudal tratado es contraproducente para la calidad del agua. Estos elementos presentan aspectos importantes para ser abordados por las políticas públicas. -------------------- The quality and availability of water in Mexican rivers is critical for regional and national development, but they pose serious problems. In 2006, 74 percent of the surface water in Mexico had different levels of pollution. The objective of this research is to identify the influence of socioeconomic variables in surface water quality on each of the hydrological-administrative regions (HARS and to propose actions in order to improve its quality. After an econometric analysis, results show that surface water quality in the different hars is affected by economic activity and population density. On the other hand, the increase of water treatment plants has little impact on reducing water pollution and the increase of treated water shows a counterproductive effect on water quality. All of these aspects should be considered when designing public policy.

  11. 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

    ....241A] Notice of Availability of Record of Decision for the Agua Fria National Monument and Bradshaw... availability of the Record of Decision (ROD)/Approved Resource Management Plan (RMP) for the Agua Fria National... of the planning area during prehistoric or historic times. The Agua Fria National Monument includes...

  12. TRATAMIENTO DE AGUAS DE ESCORRENTÍA MEDIANTE HUMEDALES ARTIFICIALES: ESTADO DEL ARTE

    Directory of Open Access Journals (Sweden)

    Carlos Andrés Peña Guzmán

    2012-01-01

    Full Text Available La concentración de contaminantes en aguas lluvia es un tema que preocupa a las entidades gubernamentales porque deterioran la calidad hídrica de las fuentes receptoras. En varios países, se han iniciado investigaciones y desarrollo de metodologías para tratar este tipo de aguas. Una de estas técnicas es la ejecución de humedales artificiales, y es una de las más aceptadas por su gran eficiencia en la remoción de contaminantes. El presente artículo expondrá el estado del conocimiento, estudiando los métodos de diseño, eficiencias y las nuevas tendencias en la investigación de humedales artificiales que tratan aguas lluvia y/o escorrentía urbana.

  13. 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.

  14. Valor económico de la calidad del agua: inferencias a partir de la demanda residencial de agua potable considerando percepción imperfecta de precios y complementariedad débil de las preferencias

    OpenAIRE

    Jaramillo de Souza, Samuel David

    2017-01-01

    Nuestro estudio aproxima una medida conservadora de la disposición a pagar (WTP) de las familias por evitar una reducción de la calidad bacteriológica del agua potable que consumen. Para ello se propone recuperar las preferencias individuales utilizando la función de demanda marshalliana por un bien privado que, se presume, es débilmente complementario a la calidad del agua: el volumen de agua potable consumido por el hogar. En la lógica de Mäller (1974) y Larson (1991), la existencia de una ...

  15. Power ramp tests of BWR-MOX fuels

    International Nuclear Information System (INIS)

    Asahi, K.; Oguma, M.; Higuchi, S.; Kamimua, K.; Shirai, Y.; Bodart, S.; Mertens, L.

    1996-01-01

    Power ramp test of BWR-MOX and UO 2 fuel rods base irradiated up to about 60 GWd/t in Dodewaard reactor have been conducted in BR2 reactor in the framework of the international DOMO programme. The MOX pellets were provided by BN (MIMAS process) and PNC (MH method). The MOX fuel rods with Zr-liner and non-liner cladding and the UO 2 fuel rods with Zr-liner cladding remained intact during the stepwise power ramp tests to about 600 W/cm, even at about 60 GWd/t

  16. Developing and modeling of the 'Laguna Verde' BWR CRDA benchmark

    International Nuclear Information System (INIS)

    Solis-Rodarte, J.; Fu, H.; Ivanov, K.N.; Matsui, Y.; Hotta, A.

    2002-01-01

    Reactivity initiated accidents (RIA) and design basis transients are one of the most important aspects related to nuclear power reactor safety. These events are re-evaluated whenever core alterations (modifications) are made as part of the nuclear safety analysis performed to a new design. These modifications usually include, but are not limited to, power upgrades, longer cycles, new fuel assembly and control rod designs, etc. The results obtained are compared with pre-established bounding analysis values to see if the new core design fulfills the requirements of safety constraints imposed on the design. The control rod drop accident (CRDA) is the design basis transient for the reactivity events of BWR technology. The CRDA is a very localized event depending on the control rod insertion position and the fuel assemblies surrounding the control rod falling from the core. A numerical benchmark was developed based on the CRDA RIA design basis accident to further asses the performance of coupled 3D neutron kinetics/thermal-hydraulics codes. The CRDA in a BWR is a mostly neutronic driven event. This benchmark is based on a real operating nuclear power plant - unit 1 of the Laguna Verde (LV1) nuclear power plant (NPP). The definition of the benchmark is presented briefly together with the benchmark specifications. Some of the cross-sections were modified in order to make the maximum control rod worth greater than one dollar. The transient is initiated at steady-state by dropping the control rod with maximum worth at full speed. The 'Laguna Verde' (LV1) BWR CRDA transient benchmark is calculated using two coupled codes: TRAC-BF1/NEM and TRAC-BF1/ENTREE. Neutron kinetics and thermal hydraulics models were developed for both codes. Comparison of the obtained results is presented along with some discussion of the sensitivity of results to some modeling assumptions

  17. Recycling systems for BWR type reactors

    International Nuclear Information System (INIS)

    Takagi, Akio; Yamamoto, Fumiaki; Fukumoto, Ryuji.

    1986-01-01

    Purpose: To stabilize the coolant flowing characteristics and reactor core reactivity. Constitution: The recycling system in a BWR type reactor comprises a recycling pump disposed to the outside of a reactor pressure vessel, a ring header connected to the recycling pump through main pipe ways, and a plurality of pipes branched from and connected with the ring header and connected to a plurality of jet pumps within the pressure vessel. Then, by making the diameter for the pipeways of each of the branched pipes different from each other, the effective cross-sectional area is varied to thereby average the coolant flow rate supplied to each of the jet pumps. (Seki, T.)

  18. Evaluation of PWR and BWR pin cell benchmark results

    International Nuclear Information System (INIS)

    Pijlgroms, B.J.; Gruppelaar, H.; Janssen, A.J.; Hoogenboom, J.E.; Leege, P.F.A. de; Voet, J. van der; Verhagen, F.C.M.

    1991-12-01

    Benchmark results of the Dutch PINK working group on PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs., 9 figs., 30 tabs

  19. Evaluation of PWR and BWR pin cell benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Pijlgroms, B.J.; Gruppelaar, H.; Janssen, A.J. (Netherlands Energy Research Foundation (ECN), Petten (Netherlands)); Hoogenboom, J.E.; Leege, P.F.A. de (Interuniversitair Reactor Inst., Delft (Netherlands)); Voet, J. van der (Gemeenschappelijke Kernenergiecentrale Nederland NV, Dodewaard (Netherlands)); Verhagen, F.C.M. (Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands))

    1991-12-01

    Benchmark results of the Dutch PINK working group on PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs., 9 figs., 30 tabs.

  20. Evaluation of PWR and BWR pin cell benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Pilgroms, B.J.; Gruppelaar, H.; Janssen, A.J. (Netherlands Energy Research Foundation (ECN), Petten (Netherlands)); Hoogenboom, J.E.; Leege, P.F.A. de (Interuniversitair Reactor Inst., Delft (Netherlands)); Voet, J. van der (Gemeenschappelijke Kernenergiecentrale Nederland NV, Dodewaard (Netherlands)); Verhagen, F.C.M. (Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands))

    1991-12-01

    Benchmark results of the Dutch PINK working group on the PWR and BWR pin cell calculational benchmark as defined by EPRI are presented and evaluated. The observed discrepancies are problem dependent: a part of the results is satisfactory, some other results require further analysis. A brief overview is given of the different code packages used in this analysis. (author). 14 refs.; 9 figs.; 30 tabs.

  1. Applied methods for mitigation of damage by stress corrosion in BWR type reactors

    International Nuclear Information System (INIS)

    Hernandez C, R.; Diaz S, A.; Gachuz M, M.; Arganis J, C.

    1998-01-01

    The Boiling Water nuclear Reactors (BWR) have presented stress corrosion problems, mainly in components and pipes of the primary system, provoking negative impacts in the performance of energy generator plants, as well as the increasing in the radiation exposure to personnel involucred. This problem has caused development of research programs, which are guided to find solution alternatives for the phenomena control. Among results of greater relevance the control for the reactor water chemistry stands out particularly in the impurities concentration and oxidation of radiolysis products; as well as the supervision in the materials selection and the stresses levels reduction. The present work presents the methods which can be applied to diminish the problems of stress corrosion in BWR reactors. (Author)

  2. 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.

  3. Estudio y propuestas de tratamiento de PPCP’s en aguas residuales

    OpenAIRE

    Serra i Prat, Gemma; Zélaskiewicz, Agnieszka

    2008-01-01

    La reutilización de las aguas residuales es una parte esencial del uso sostenible del agua. Sin embargo, las actuales plantas de tratamiento no están preparadas para tratar determinados compuestos como los llamados “contaminantes emergentes”. Los hábitos de consumo actuales estan generando una serie de residuos o microcontaminantes que hace tan solo unos años no existian. Entre esas nuevas sustancias aparecen los PPCP’s (Pharmaceuticals & Personal Care Products) que son un amplio grupo de com...

  4. BWR stability using a reducing dynamical model; Estabilidad de un BWR con un modelo dinamico reducido

    Energy Technology Data Exchange (ETDEWEB)

    Ballestrin Bolea, J M; Blazquez Martinez, J B

    1990-07-01

    BWR stability can be treated with reduced order dynamical models. When the parameters of the model came from 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 structure 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 is non-linear. Simple parametric calculation of decay ratio are performed, showing why BWRs become unstable when they are operated at low flow and high power. (Author)

  5. Fission product model for BWR analysis with improved accuracy in high burnup

    International Nuclear Information System (INIS)

    Ikehara, Tadashi; Yamamoto, Munenari; Ando, Yoshihira

    1998-01-01

    A new fission product (FP) chain model has been studied to be used in a BWR lattice calculation. In attempting to establish the model, two requirements, i.e. the accuracy in predicting burnup reactivity and the easiness in practical application, are simultaneously considered. The resultant FP model consists of 81 explicit FP nuclides and two lumped pseudo nuclides having the absorption cross sections independent of burnup history and fuel composition. For the verification, extensive numerical tests covering over a wide range of operational conditions and fuel compositions have been carried out. The results indicate that the estimated errors in burnup reactivity are within 0.1%Δk for exposures up to 100GWd/t. It is concluded that the present model can offer a high degree of accuracy for FP representation in BWR lattice calculation. (author)

  6. European BWR R and D cluster for innovative passive safety systems

    International Nuclear Information System (INIS)

    Hicken, E.F.; Lensa, W. von

    1996-01-01

    The main technological innovation trends for future nuclear power plants tend towards a broader use of passive safety systems for the prevention, mitigation and managing of severe accident scenarios. Several approaches have been undertaken in a number of European countries to study and demonstrate the feasibility and charateristics of innovative passive safety systems. The European BWR R and D Cluster combines those experimental and analytical efforts that are mainly directed to the introduction of passive safety systems into boiling water reactor technology. The Cluster is grouped around thermohydraulic test facilities in Europe for the qualification of innovative BWR safety systems, also taking into account especially the operating experience of the nuclear power plant Dodewaard and other BWRs, which already incorporated some passive safety features. The background, the objectives, the structure of the project and the work programme are presented in this paper as well as an outline of the significance of the expected results. (orig.) [de

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

    International Nuclear Information System (INIS)

    Hu, Rui; Kazimi, Mujid S.

    2009-01-01

    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)

  8. Dureza complexométrica del agua. Práctica interactiva.

    OpenAIRE

    Milla González, Miguel

    2011-01-01

    En este ejercicio se simula la determinación de la dureza de una muestra de agua por complexometría con AEDT disódico como valorante y negro de eriocromo T como indicador. En la parte de introducción se exponen los principios básicos de la determinación complexométrica de la dureza de un agua simulando mediante animaciones las reacciones que tienen lugar antes y durante la valoración. Se prepara a continuación la disolución del valorante mediante pesada y disolución de la cantidad pesada en u...

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

    OpenAIRE

    Lorena Salazar Gámez; Martí Crespi Rosell; Roberto Salazar

    2009-01-01

    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 Bior...

  10. Detection of failed fuel rods in shrouded BWR fuel assemblies

    International Nuclear Information System (INIS)

    Baero, G.; Boehm, W.; Goor, B.; Donnelly, T.

    1988-01-01

    A manipulator and an ultrasonic testing (UT) technique were developed to identify defective fuel rods in shrouded BWR fuel assemblies. The manipulator drives a UT probe axially through the bottom tie plate into the water channels between the fuel rods. The rotating UT probe locates defective fuel rods by ingressed water which attenuates the UT-signal. (author)

  11. CLARIFICACIÓN DE AGUAS USANDO COAGULANTES POLIMERIZADOS: CASO DEL HIDROXICLORURO DE ALUMINIO

    Directory of Open Access Journals (Sweden)

    JUAN MIGUEL COGOLLO FLÓREZ

    2011-01-01

    Full Text Available En este artículo se realiza un estudio del proceso de clarificación en sistemas de tratamiento de aguas industriales usando un coagulante inorgánico polimerizado (hidroxicloruro de aluminio. Inicialmente, se establecen los elementos conceptuales más importantes de las etapas del proceso de clarificación (coagulación, floculación y sedimentación. Luego, se señalan los principales coagulantes convencionales utilizados en el tratamiento de aguas y se abordan los policloruros de aluminio (PAC´s como integrantes de una nueva generación de coagulantes alternativos cuyo uso se ha incrementado en las últimas décadas dado su mejor desempeño respecto a los coagulantes convencionales; se especifican los aspectos técnicos y operativos que se deben considerar al momento de implementar un proceso de clarificación de aguas usando un PAC como coagulante. Finalmente, se presentan datos comparativos de condiciones operacionales reales de un proceso de clarificación de aguas, producto de un trabajo previo, donde se remplazó un coagulante convencional (sulfato de aluminio por hidroxicloruro de aluminio, donde se corrobora el mejor desempeño del proceso luego del remplazo.

  12. Assessment of severe accident prevention and mitigation features: BWR, Mark II containment design

    International Nuclear Information System (INIS)

    Lehner, J.R.; Hsu, C.J.; Eltawila, F.; Perkins, K.R.; Luckas, W.J.; Fitzpatrick, R.G.; Pratt, W.T.

    1988-07-01

    Plant features and operator actions, which have been found to be important in either preventing or mitigating severe accidents in BWRs with Mark II containments (BWR Mark II's) have been identified. These features and actions were developed from insights derived from reviews of in-depth risk assessments performed specifically for the Limerick and Shoreham plants and from other relevant studies. Accident sequences that dominate the core-damage frequency and those accident sequences that are of potentially high consequence were identified. Vulnerabilities of the BWR Mark II to severe-accident containment loads were also noted. In addition, those features of a BWR Mark II, which are important for preventing core damage and are available for mitigating fission-product release to the environment were also identified. This report is issued to provide focus to an analyst examining an individual plant. This report calls attention to plant features and operator actions and provides a list of deterministic attributes for assessing those features and actions found to be helpful in reducing the overall risk for Mark II plants. Thus, the guidance is offered as a resource in examining the subject plant to determine if the same, or similar, plant features and operator actions will be of value in reducing overall plant risk. This report is intended to serve solely as guidance

  13. Examination of minor actinide annihilation by BWR core

    International Nuclear Information System (INIS)

    Hida, Kazuki

    1995-01-01

    From the viewpoint of reducing burden for disposing high level waste generated from spent fuel, the examination of recycling minor actinide (MA) to reactors and reducing its accumulation has been advanced. In this study, the possibility of annihilation in the case of recycling it to a BWR was examined. The main MAs are 237 Np, 241 Am, 243 Am, 242 Cm, and 244 Cm. However, as for Cm isotopes, the half life is short, the amount of generation is small, and the rate of neutron emission is high, therefore, those are disposed as waste, and 237 Np, 241 Am and 243 Am were taken as the objects of recycling. In order to grasp the basic characteristics in the case of recycling MAs to a BWR, MAs were added to UO 2 fuel, MOX fuel and HCR fuel and burned, and the nuclear conversion characteristics were examined. As the result, it was found that they were converted to short half life nuclides, and as the neutron spectra were softer, the rate of annihilation was higher. In the case of recycling MAs by concentrating to a specific reactor, reactivity loss, the degree of uranium enrichment required for compensating reactivity, and the rate of MA annihilation were calculated. Based on these data, the MA recycling system was set up, and the rate of MA annihilation was evaluated. This is reported. (K.I.)

  14. Simplified compact containment BWR plant

    International Nuclear Information System (INIS)

    Heki, H.; Nakamaru, M.; Tsutagawa, M.; Hiraiwa, K.; Arai, K.; Hida, T.

    2004-01-01

    The reactor concept considered in this paper has a small power output, a compact containment and a simplified BWR configuration with comprehensive safety features. The Compact Containment Boiling Water Reactor (CCR), which is being developed with matured BWR technologies together with innovative systems/components, is expected to prove attractive in the world energy markets due to its flexibility in regard to both energy demands and site conditions, its high potential for reducing investment risk and its safety features facilitating public acceptance. The flexibility is achieved by CCR's small power output of 300 MWe class and capability of long operating cycle (refueling intervals). CCR is expected to be attractive from view point of investment due to its simplification/innovation in design such as natural circulation core cooling with the bottom located short core, internal upper entry control rod drives (CRDs) with ring-type dryers and simplified ECCS system with high pressure containment concept. The natural circulation core eliminates recirculation pumps and the maintenance of such pumps. The internal upper entry CRDs reduce the height of the reactor vessel (RPV) and consequently reduce the height of the primary containment vessel (PCV). The safety features mainly consist of large water inventory above the core without large penetration below the top of the core, passive cooling system by isolation condenser (IC), passive auto catalytic recombiner and in-vessel retention (IVR) capability. The large inventory increases the system response time in the case of design-base accidents, including loss of coolant accidents. The IC suppresses PCV pressure by steam condensation without any AC power. The recombiner decreases hydrogen concentration in the PCV in the case of a severe accident. Cooling the molten core inside the RPV if the core should be damaged by loss of core coolability could attain the IVR. The feasibility of CCR safety system has been confirmed by LOCA

  15. Stress corrosion cracking of L-grade stainless steels in boiling water reactor (BWR) plants

    International Nuclear Information System (INIS)

    Suzuki, Shunichi; Fukuda, Toshihiko; Yamashita, Hironobu

    2004-01-01

    L-grade stainless steels as 316NG, SUS316L and SUS304L have been used for the BWR reactor internals and re-circulation pipes as SCC resistant materials. However, SCC of the L-grade material components were reported recently in many Japanese BWR plants. The detail investigation of the components showed the fabrication process such as welding, machining and surface finishing strongly affected SCC occurrence. In this paper, research results of SCC of L-grade stainless steels, metallurgical investigation of core shrouds and re-circulation pipings, and features of SCC morphology were introduced. Besides, the structural integrity of components with SCC, countermeasures for SCC and future R and D planning were introduced. (author)

  16. 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.

  17. 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...

  18. Operation status display and monitoring system for BWR nuclear power plant

    International Nuclear Information System (INIS)

    Wakabayashi, Yasuo; Hayakawa, Hiroyasu; Kawamura, Atsuo; Kaneda, Mitsunori.

    1982-01-01

    Lately, the development of the system has been made for BWR plants, which monitors the operating status not only in normal operation but also in abnormal state and also for plant safety. Recently, the improvement of man-machine interface has been tried through the practical use of technique which displays data collectively on a CRT screen relating them mutually. As one of those results, the practical use of an electronic computer and color CRT display for No. 1 unit in the Fukushima No. 2 Nuclear Power Station (2F-1), Tokyo Electric Power Co., is described. Also, new centralized control panels containing such systems were used for the 1100 MWe BWR nuclear power plants now under construction, No. 3 unit of the Fukushima No. 2 Power Station and No. 1 unit of Kashiwazaki-Kariwa Nuclear Power Station (2F-3 and K-1, respectively). The display and monitoring system in 2F-1 plant is the first one in which a computer and color CRTs were practically employed for a BWR plant in Japan, and already in commercial operation. The advanced operating status monitoring system, to which the result of evaluation of the above system was added, was incorporated in the new centralized control panels presently under production for 2F-3 and K-1 plants. The outline of the system, the functions of an electronic computer, plant operating status monitor, surveillance test guide, the automation of plant operation and auxiliary operation guide are reported for these advanced monitoring system. It was confirmed that these systems are useful means to improve the man-machine communication for plant operation minitoring. (Wakatsuki, Y.)

  19. Comparación medioambiental de dos plantas de producción de agua potable basada en el método ACV

    OpenAIRE

    Poch Barrera, Andrés

    2013-01-01

    En la actualidad, las medidas adoptadas para reducir la contaminación del agua son varias. Sin embargo, la purificación del agua para consumo como agua potable en lasciudades requiere la implementación de procesos de purificación de carácter industrial.Estos procesos a su vez afectan el medio ambiente y contribuyen al cambio climático.La producción de agua potable es una actividad que puede implicar, entre otrosprocesos, la ultrafiltración del agua y por lo tanto exige un consumo de energíaco...

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

    International Nuclear Information System (INIS)

    Sehgal, B.R.; Peng, C.M.; Maly, J.

    1988-01-01

    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

  1. ECP measurements in the BWR-1 water loop relative to water composition changes

    Energy Technology Data Exchange (ETDEWEB)

    Kus, P.; Vsolak, R.; Kysela, J., E-mail: ksp@ujv.cz [Nuclear Research Inst. Rez plc, Husinec - Rez (Czech Republic); Hanawa, S.; Nakamura, T.; Uchida, S., E-mail: hanawa.satoshi@jaea.go.jp [Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan)

    2010-07-01

    The goal of this study is to investigate the usage of ECP sensors in nuclear power plants. ECP sensors were tested using the LVR-15 reactor at the Nuclear Research Institute Rez plc (NRI) in the Czech Republic. The experiment took place on the BWR-1 loop, which was designed for investigating the behaviour of structural materials and radioactivity transport under BWR conditions. The BWR-1 loop facilitates irradiation experiments within a wide range of operating parameters (max. pressure of 10 MPa, max. temperature of 573 K and a neutron flux of 1.0* 10{sup 18} n/m{sup 2}s). This study involves the measurement of electrochemical potential (ECP). Corrosion potential is the main parameter for monitoring of water composition changes in nuclear power plants (NPP). The electrochemical potentials of stainless steel were measured under high temperatures in a test loop (BWR-1) under different water composition conditions. Total neutron flux was ∼10{sup -3} to ∼10{sup 12} n/cm{sup 2}s (>0.1 MeV) at a temperature of 560K, neutral pH, and water resistivity of 18.2 MOhm. ECP sensor response related to changes in water composition was monitored. Switching from NWC (normal water conditions) to HWC (hydrogen water conditions) was controlled using oxygen dosage. Water chemistry was monitored approx. 50 meters from the active channel. The active channel temperature was maintained within a range of 543 - 561 K from the start of irradiation for the entire duration of the experiment. A total of 24 reference electrodes composed of platinum (Pt), silver/silver chloride (Ag/AgCl) and a zircon membrane containing silver oxide (Ag{sub 2}O) powder were installed inside the active channel of the LVR-15 test reactor. The active channel (Field tube) was divided into four zones, with each zone containing six sensors. A mathematical radiolysis code model was created in cooperation with the Japan Atomic Energy Agency. (author)

  2. 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.       

  3. Stability monitoring for BWR based on singular value decomposition method using artificial neural network

    International Nuclear Information System (INIS)

    Tsuji, Masashi; Shimazu, Yoichiro; Michishita, Hiroshi

    2005-01-01

    A new method for evaluating the decay ratios in a boiling water reactor (BWR) using the singular value decomposition (SVD) method had been proposed. In this method, a signal component closely related to the BWR stability can be extracted from independent components of the neutron noise signal decomposed by the SVD method. However, real-time stability monitoring by the SVD method requires an efficient procedure for screening such components. For efficient screening, an artificial neural network (ANN) with three layers was adopted. The trained ANN was actually applied to decomposed components of local power range monitor (LPRM) signals that were measured in stability experiments conducted in the Ringhals-1 BWR. In each LPRM signal, multiple candidates were screened from the decomposed components. However, decay ratios could be estimated by introducing appropriate criterions for selecting the most suitable component among the candidates. The estimated decay ratios are almost identical to those evaluated by visual screening in a previous study. The selected components commonly have the largest singular value, the largest decay ratio and the least squared fitting error among the candidates. By virtue of excellent screening performance of the trained ANN, the real-time stability monitoring by the SVD method can be applied in practice. (author)

  4. POTENCIAL ZETA (Z COMO CRITERIO DE OPTIMIZACIÓN DE DOSIFICACIÓN DE COAGULANTE EN PLANTA DE TRATAMIENTO DE AGUA POTABLE

    Directory of Open Access Journals (Sweden)

    BIBIANA BETANCUR C.

    2012-01-01

    Full Text Available La calidad del agua cruda del Río Otún que abastece la planta de tratamiento de agua potable de Aguas y Aguas de Pereira puede presentar fluctuaciones en cortos periodos de tiempo. Por esta razón se requiere un instrumento que permita tomar decisiones rápidas para modificar la dosis de coagulante a utilizar en el tratamiento con base en un criterio cuantificable y preciso como el potencial zeta (ζ. En este estudio se determinó que para un intervalo de ζ desde -2.28 mV a +1.2 mV del agua coagulada se obtienen valores bajos de turbiedad y color del agua sedimentada. Es posible alcanzar un óptimo desempeño del proceso de floculación y sedimentación efectuando mediciones de ζ en el agua coagulada como indicador de desestabilización de las partículas. ζ presenta una correlación positiva con la dosis de coagulante aplicada, modificando la dosis de coagulante es posible alcanzar valores de ζ cercanos a cero.

  5. Aporte del agua de bebida a los requerimientos de calcio de la población costarricense

    OpenAIRE

    Darner Mora Alvarado; Nuria Alfaro Herrera; Carlos Felipe Portuquez

    2000-01-01

    Se presenta la primera investigación a nivel nacional, para determinar el aporte del agua de bebida a los requerimientos de calcio del costarricense, asumiendo una ingesta diaria de 2 litros de agua. Para calcular las concentraciones porcentuales de calcio iónico, se promediaron y agruparon por cantones los contenidos de Carbonato de Calcio (CACO3) de las fuentes de agua utilizadas por acueductos rurales, municipales y los administrados por Acueductos y Alcantarillados; además, como complemen...

  6. Arsénico en aguas naturales del sudeste de la provincia de Córdoba, Argentina.

    Directory of Open Access Journals (Sweden)

    Alejo Leopoldo Perez Carrera

    2013-10-01

    Full Text Available En Argentina, existen grandes regiones que por sus características edafoclimáticas, poseen excelentes aptitudes agropecuarias, sin embargo, sufren limitaciones de desarrollo debido a la disponibilidad de agua y la calidad del recurso hídrico disponible. Uno de los elementos químicos presentes en el agua, con mayor impacto sobre la salud humana y animal, es el arsénico. La región afectada, abarca las provincias de Córdoba, La Pampa, Santiago del Estero, San Luis, Santa Fe, Buenos Aires, Chaco, Salta, Tucumán, San Juan y Mendoza. El objetivo de este trabajo es analizar la presencia y distribución del arsénico en agua superficial y subterránea en el sudeste de la provincia de Córdoba, una de las zonas más afectadas de Argentina por la presencia de arsénico en el agua.

  7. El conocimiento del ciclo del agua en el segundo ciclo de Educación Primaria

    Directory of Open Access Journals (Sweden)

    María Guerrero Valle

    2017-07-01

    Full Text Available El agua tiene una gran importancia e influencia en nuestras vidas y en nuestro planeta. En este trabajo se presenta una investigación sobre el conocimiento sobre el ciclo del agua en el segundo ciclo de la Educación Primaria. Para el estudio, se ha realizado en dos centros de Primaria un cuestionario sobre lluvia que recoge los conceptos claves para una comprensión básica del mecanismo de la lluvia como del ciclo del agua, junto con un dibujo sobre la lluvia. La investigación pone de manifiesto que el grado de conocimiento sobre el ciclo del agua de los estudiantes es alto, pero se trata de un conocimiento incompleto y, en algunas ocasiones, erróneo. Después de reflexionar sobre los resultados obtenidos, se propone la implicación educativa necesaria para mejorar dichos resultados.

  8. Assessment of two BWR accident management strategies

    International Nuclear Information System (INIS)

    Hodge, S.A.; Petek, M.

    1991-01-01

    A recently completed Oak Ridge effort proposes two management strategies for mitigation of the events that might occur in-vessel after the onset of significant core damage in a BWR severe accident. While the probability of such an accident is low, there may be effective yet inexpensive mitigation measures that could be implemented employing the existing plant equipment and requiring only additions to the plant emergency procedures. In this spirit, accident management strategies have been proposed for use of a borated solution for reactor vessel refill should control blade damage occur during a period of temporary core dryout and for containment flooding to maintain the core debris within the reactor vessel if injection systems cannot be restored. The proposed strategy for poisoning of the water used for vessel reflood should injection systems be restored after control blade damage has occurred has great promise, using only the existing plant equipment but employing a different chemical form for the boron poison. The dominant BWR severe accident sequence is Station Blackout and without means for mechanical stirring or heating of the storage tank, the question of being able to form the poisoned solution under accident conditions becomes of supreme importance. On the other hand, the proposed strategy for drywell flooding to cool the reactor vessel bottom head and prevent the core and structure debris from escaping to the drywell holds less promise. This strategy does, however, have potential for future plant designs in which passive methods might be employed to completely submerge the reactor vessel under severe accident conditions without the need for containment venting

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

    International Nuclear Information System (INIS)

    Boyd, Christopher; Skarda, Raymond

    2014-01-01

    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

  10. Assessment of the fracture toughness of irradiated stainless steel for BWR core shrouds

    International Nuclear Information System (INIS)

    Carter, R.G.; Gamble, R.M.

    2002-01-01

    Data from previously performed experiments were collected and evaluated to determine the relationship between fracture toughness and neutron fluence for conditions representative of BWR core shrouds. This relationship together with EPFM (elastic-plastic fracture mechanics) analysis methods similar to those in Appendix K of Section XI of the ASME Code were used to compute margin against failure as a function of neutron fluence for postulated cracks in BWR core shrouds. The results indicate that EPFM analyses can be used for flaw evaluation of core shrouds at fluence levels less than 3.10 21 n/cm 2 (E > 1 MeV). At fluence levels equal to or greater than 3.10 21 n/cm 2 , LEFM (linear-elastic fracture mechanics) analyses should be used with K Ic = 55 MPa-(m) 0.5 . (authors)

  11. Investigations on the thermal-hydraulics of a natural circulation cooled BWR fuel assembly

    Energy Technology Data Exchange (ETDEWEB)

    Kok, H.V.; Hagen, T.H.J.J. van der; Mudde, R.F. [Delft Univ. of Technology (Netherlands)

    1995-09-01

    A scaled natural circulation loop facility has been built after the Dodewaard Boiling Water Reactor, which is the only operating natural circulation cooled BWR in the world. The loop comprises one fuel assembly, a riser with a downcomer and a condenser with a cooling system. Freon-12 is used as a scaling liquid. This paper reports on the first measurements done with this facility. Quantities like the circulation flow, carry-under and the void-fraction have been measured as a function of power, pressure, liquid level, riser length, condensate temperature and friction factors. The behavior of the circulation flow can be understood by considering the driving force. Special attention has been paid to the carry-under, which has been shown to have a very important impact on the dynamics of a natural circulation cooled BWR.

  12. TRATAMIENTO DE AGUAS RESIDUALES EN LA URBANIZACIÓN CIUDAD POLITÉCNICA, CANTÓN BOLÍVAR, PROVINCIA DE MANABÍ

    Directory of Open Access Journals (Sweden)

    Ángel Mariano Montesdeoca Zambrano

    2013-06-01

    Full Text Available La urbanización Ciudad Politécnica está en fase de implementación, por lo que es necesario definir el suministro de los servicios básicos tales como agua potable, energía eléctrica, alcantarillado de aguas lluvia, de aguas servidas, etc. El presente estudio tuvo cómo objetivo diseñar una planta de tratamiento de las aguas residuales que se generarán, a futuro, en Ciudad Politécnica, que cumpla con las normas vigentes en el Ecuador. Se realizó una revisión de las leyes y normas vigentes para efluentes de plantas de tratamiento de aguas residuales, planificación urbanística, disponibilidad de terreno para la ubicación de la planta de tratamiento; determinándose que el proceso de lodos activados mediante reactores secuenciales por tandas, es el mejor sistema para el tratamiento de aguas residuales de comunidades pequeñas que, gran parte del día, están fuera de su domicilio y por lo tanto, generan bajo volumen e intermitente flujo de aguas residuales. La línea base permitió realizar los cálculos de ingeniería y finalmente, el diseño hidráulicosanitario y ambiental de la planta.

  13. International comparison calculations for a BWR lattice with adjacent gadolinium pins

    International Nuclear Information System (INIS)

    Maeder, C.; Wydler, P.

    1984-09-01

    The results of burnup calculations for a simplified BWR fuel element with two adjacent gadolinium rods are presented and discussed. Ten complete solutions were contributed by Denmark, France, Italy (3), Japan (3), Switzerland and the UK. Partial results obtained from Poland and the USA are included in an Appendix. (Auth.)

  14. Trend of field data on pipe wall thinning for BWR power plants

    International Nuclear Information System (INIS)

    Hakii, Junichi; Hiranuma, Naoki; Hidaka, Akitaka

    2009-01-01

    Strongly motivated by every stakeholder not to repeat Mihama Nuclear Power Station pipe rupture accident in August 2004, JSME Main Committee on Codes and Standards on Power Generation Facilities immediately launched a special task force to develop Rules on Pipe Wall Thinning Management for BWR, PWR and fossil Power Plants respectively. The authors describes the process of the development of Rules for BWR Power Plans from the view point of collections and analysis of fields data of pipe wall thinning. Through its activities, the authors confirmed the existing findings, like the effect of Oxygen injection, turbulence and dependence on coolant temperature, derived from series of laboratory-scaled experiments in FAC and coolant velocities effects in LDI. Further based upon the said proven findings with field data, they explain the adequacy of major concept of the rule such as separate treatment of FAC (Flow Accelerated Corrosion) and LDI (Liquid Droplet Impingement). (author)

  15. Hydro geochemistry of uranium in Aguas de Lindoia (Sao Paulo State)

    International Nuclear Information System (INIS)

    Silveira, E.G. da.

    1992-01-01

    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)

  16. Productividad del agua en algunos cultivos agrícolas en Cuba

    OpenAIRE

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

    2014-01-01

    Para el mejor uso económico y social del agua se requieren de métodos para evaluar su productividad, a fin de tomar mejores decisiones en cuanto a políticas y estrategias de utilización de manera sostenible. Los administradores del agua para el riego necesitan iden- tificar tendencias en los patrones de uso y niveles de eficiencia con vistas a fijar metas y mejorar la productividad por unidad de volumen utilizado y/o consumido. El objetivo de este trabajo fue presentar los indicadores de prod...

  17. Estrategias para el abastecimiento de agua a comunidades marginadas y urbanas.

    OpenAIRE

    Juan Martínez, José

    2012-01-01

    Esta investigación tuvo como objetivo formular estrategias y escenarios para el abastecimiento de agua para consumo humano, uso doméstico y productivo, considerando las condiciones socioculturales, económicas y modos de producción; con el propósito de identificar tecnologías que atienden las demandas actuales y futuras en materia de agua en la entidad del DF y Estado de México. Se inició con el diseño de cinco escenarios de caso: casa rural marginada, urbana, residencia, mediana industria e i...

  18. Tecnología de electromembrana cerámica para la desinfección de aguas

    OpenAIRE

    Gomilla Villalonga, Joan Jose

    2015-01-01

    La difícil tarea en algunos lugares de abastecerse de agua potable ha llevado a los países, empresas y organizaciones gubernamentales a desarrollar una tecnología que permita desinfectar los suministros de agua y que sea a un coste bajo. Los avances en la electrolisis de la salmuera han permitido producir una solución que además de permitir la desinfección del agua no salubre no sea tóxico para las personas, animales y plantas. Esta tecnología se conoce como Activación Electroquímica (ECA). ...

  19. BWR - Spent Fuel Transport and Storage with the TNTM9/4 and TNTM24BH Casks

    International Nuclear Information System (INIS)

    Wattez, L.; Marguerat, Y.; Hoesli, C.

    2006-01-01

    The Swiss Nuclear Utilities have started in 2001 to store spent fuel in dry metallic dual-purpose casks at ZWILAG, the Swiss interim storage facility. BKW FMB Energy Ltd., the Muehleberg Nuclear Power Plant owner, is involved in this process and has elected to store its BWR spent fuel in a new high capacity dual-purpose cask, the TNeTeM24BH from the COGEMA Logistics/TRANSNUCLEAR TN TM 24 family. The Muehleberg BWR spent fuels are transported by road in a medium size shuttle transport cask and then transferred to a heavy transport/storage cask (dry transfer) in the hot cell of ZWILAG site. For that purpose, COGEMA Logistics designed and supplied: - Two shuttle casks, TN TM 9/4, mainly devoted to transport of spent fuel from Muehleberg NPP to ZWILAG. Licensed according to IAEA 1996, the TN TM 9/4 is a 40 ton transport cask, for 7 BWR high bum-up spent fuel assemblies. - A series of new high capacity dual-purpose casks, TN TM 24BH, holding 69 BWR spent fuels. Two transport campaigns took place in 2003 and 2004. For each campaign, ten TN TM 9/4 round trips are performed, and one TN TM 24BH is loaded. 5 additional TN TM 24BH are being manufactured for BKW, and the next transport campaigns are scheduled from 2006. The TN TM 24BH high capacity dual purpose cask and the TN TM 9/4 transport cask characteristics and capabilities will then be detailed. (authors)

  20. Applicability of the diffusion and simplified P3 theories for BWR pin-by-pin core analysis

    International Nuclear Information System (INIS)

    Tada, Kenichi; Yamamoto, Akio; Kitamura, Yasunori; Yamane, Yoshihiro; Watanabe, Masato; Noda, Hiroshi

    2007-01-01

    The pin-by-pin fine mesh core calculation method is considered as a candidate of next-generation core calculation method for BWR. In this study, the diffusion and the simplified P 3 (SP 3 ) theories are applied to the pin-by-pin core analysis of BWR. Performances of the diffusion and the SP 3 theories for cell-homogeneous pin-by-pin fine mesh BWR core analysis are evaluated through comparison with cell-heterogeneous detailed transport calculation by the method of characteristics (MOC). In this study, two-dimensional, 2x2 multi-assemblies geometry is used to compare the prediction accuracies of the diffusion and the SP 3 theories. The 2x2 multi- assemblies geometry consists of two types of 9x9 UO 2 assembly that have two different enrichment splittings. To mitigate the cell-homogenization error, the SPH method is applied for the pin-by-pin fine mesh calculation. The SPH method is a technique that reproduces a result of heterogeneous calculation by that of homogeneous calculation. The calculation results indicated that diffusion theory shows larger discrepancy than that of SP 3 theory on pin-wise fission rates. Furthermore, the accuracy of the diffusion theory would not be sufficient for the pin-by-pin fine mesh calculation. In contrast to the diffusion theory, the SP 3 theory shows much better accuracy on pin wise fission rates. Therefore, if the SP 3 theory is applied, the accuracy of the pin-by-pin fine mesh BWR core analysis will be higher and will be sufficient for production calculation. (author)

  1. A simplified spatial model for BWR stability

    International Nuclear Information System (INIS)

    Berman, Y.; Lederer, Y.; Meron, E.

    2012-01-01

    A spatial reduced order model for the study of BWR stability, based on the phenomenological model of March-Leuba et al., is presented. As one dimensional spatial dependence of the neutron flux, fuel temperature and void fraction is introduced, it is possible to describe both global and regional oscillations of the reactor power. Both linear stability analysis and numerical analysis were applied in order to describe the parameters which govern the model stability. The results were found qualitatively similar to past results. Doppler reactivity feedback was found essential for the explanation of the different regions of the flow-power stability map. (authors)

  2. Level 2 PRA for a German BWR

    International Nuclear Information System (INIS)

    Sassen, F.; Rapp, W.; Tietsch, W.; Roess, P.

    2007-01-01

    A concept for a Level 2 Probabilistic Risk Assessment (L2 PRA) for a German Boiling Water Reactor (BWR) has been developed taking into account the role of L2 PRA within the German regulatory landscape. According to this concept, a plant specific evaluation of the severe accident phenomenology as well as analyses of the accident progression for the severe accident scenarios has been performed. Furthermore a plant specific MELCOR 1.8.6 model has been developed and special MELCOR source term calculations have been performed for the different release paths. This paper will present examples from the different areas described above. (author)

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

    International Nuclear Information System (INIS)

    Cole, Steven E.; Garner, Norman L.; Lippert, Hans-Joachim; Graebert, Rüdiger; Mollard, Pierre; Hahn, Gregory C.

    2014-01-01

    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)

  4. Managing the aging of BWR control rod drive systems

    International Nuclear Information System (INIS)

    Greene, R.H.; Farmer, W.S.

    1992-01-01

    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

  5. Physical model of nonlinear noise with application to BWR stability

    International Nuclear Information System (INIS)

    March-Leuba, J.; Perez, R.B.

    1983-01-01

    Within the framework of the present model it is shown that the BWR reactor cannot be unstable in the linear sense, but rather it executes limited power oscillations of a magnitude that depends on the operating conditions. The onset of these oscillations can be diagnosed by the decrease in stochasticity in the power traces and by the appearance of harmonics in the PSD

  6. 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...

  7. BWR transient analysis using neutronic / thermal hydraulic coupled codes including uncertainty quantification

    International Nuclear Information System (INIS)

    Hartmann, C.; Sanchez, V.; Tietsch, W.; Stieglitz, R.

    2012-01-01

    The KIT is involved in the development and qualification of best estimate methodologies for BWR transient analysis in cooperation with industrial partners. The goal is to establish the most advanced thermal hydraulic system codes coupled with 3D reactor dynamic codes to be able to perform a more realistic evaluation of the BWR behavior under accidental conditions. For this purpose a computational chain based on the lattice code (SCALE6/GenPMAXS), the coupled neutronic/thermal hydraulic code (TRACE/PARCS) as well as a Monte Carlo based uncertainty and sensitivity package (SUSA) has been established and applied to different kind of transients of a Boiling Water Reactor (BWR). This paper will describe the multidimensional models of the plant elaborated for TRACE and PARCS to perform the investigations mentioned before. For the uncertainty quantification of the coupled code TRACE/PARCS and specifically to take into account the influence of the kinetics parameters in such studies, the PARCS code has been extended to facilitate the change of model parameters in such a way that the SUSA package can be used in connection with TRACE/PARCS for the U and S studies. This approach will be presented in detail. The results obtained for a rod drop transient with TRACE/PARCS using the SUSA-methodology showed clearly the importance of some kinetic parameters on the transient progression demonstrating that the coupling of a best-estimate coupled codes with uncertainty and sensitivity tools is very promising and of great importance for the safety assessment of nuclear reactors. (authors)

  8. Agua y Plan Hidrológico en la Región de Murcia

    Directory of Open Access Journals (Sweden)

    Miguel Ángel Tobarra González

    2002-01-01

    Full Text Available En este trabajo se plantea la necesidad de contemplar el agua como un activo social y no sólo como un mero factor de producción, admitiendo que esta última concepción proporciona un alto valor a la producción final agraria regional. Se hace, además, un análisis de las demandas y consumos de agua, se estudian las causas y consecuencias de la escasez de recursos hídricos que conduce inevitablemente a la sobreexplotación de los acuíferos. Finalmente se estudian los precios y problemas de los distintos tipos de agua que se consumen en la región de Murcia y las razones por las cuales es necesario que cuanto antes se culmine el Plan Hidrológico Nacional.

  9. VIM Monte Carlo versus CASMO comparisons for BWR advanced fuel designs

    International Nuclear Information System (INIS)

    Pallotta, A.S.; Blomquist, R.N.

    1994-01-01

    Eigenvalues and two-dimensional fission rate distributions computed with the CASMO-3G lattice physics code and the VIM Monte Carlo Code are compared. The cases assessed are two advanced commercial BWR pin bundle designs. Generally, the two codes show good agreement in K inf , fission rate distributions, and control rod worths

  10. Agua y medio ambiente en España: diagnóstico y perspectivas de algunas líneas de acción

    Directory of Open Access Journals (Sweden)

    Miguel Sánchez Fabre

    2010-01-01

    Full Text Available Teniendo como referente el trascendente papel de las aguas continentales en el medio ambiente, se analiza el cambio de perspectiva que la aplicación de la Directiva Marco Europea del Agua supone en esta relación agua-medioambiente. En este contexto, se abordan algunos de los principales problemas que actualmente afectan al agua y, a través de las masas de agua y los ecosistemas hídricos, al medio ambiente. Finalmente, se plantean diversas iniciativas de gestión y restauración encaminadas a conseguir el buen estado ecológico de las masas de agua continentales. En el artículo queda patente la estrecha interrelación agua-medioambiente, la existencia actualmente en nuestro país de un marco legal que posibilita más que nunca la gestión del agua desde una perspectiva de conservación y mejora del medio ambiente, y la necesidad de que la aplicación de las diferentes normativas conduzca, en la práctica, a la obtención del buen estado ecológico de las masas de agua continental mediante la resolución de diferentes problemas a través de medidas de protección y restauración.

  11. The source, discharge, and chemical characteristics of water from Agua Caliente Spring, Palm Springs, California

    Science.gov (United States)

    Contributors: Brandt, Justin; Catchings, Rufus D.; Christensen, Allen H.; Flint, Alan L.; Gandhok, Gini; Goldman, Mark R.; Halford, Keith J.; Langenheim, V.E.; Martin, Peter; Rymer, Michael J.; Schroeder, Roy A.; Smith, Gregory A.; Sneed, Michelle; Martin, Peter

    2011-01-01

    Agua Caliente Spring, in downtown Palm Springs, California, has been used for recreation and medicinal therapy for hundreds of years and currently (2008) is the source of hot water for the Spa Resort owned by the Agua Caliente Band of the Cahuilla Indians. The Agua Caliente Spring is located about 1,500 feet east of the eastern front of the San Jacinto Mountains on the southeast-sloping alluvial plain of the Coachella Valley. The objectives of this study were to (1) define the geologic structure associated with the Agua Caliente Spring; (2) define the source(s), and possibly the age(s), of water discharged by the spring; (3) ascertain the seasonal and longer-term variability of the natural discharge, water temperature, and chemical characteristics of the spring water; (4) evaluate whether water-level declines in the regional aquifer will influence the temperature of the spring discharge; and, (5) estimate the quantity of spring water that leaks out of the water-collector tank at the spring orifice.

  12. Development of a detailed BWR core thermal-hydraulic analysis method based on the Japanese post-BT standard using a best-estimate code

    International Nuclear Information System (INIS)

    Ono, H.; Mototani, A.; Kawamura, S.; Abe, N.; Takeuchi, Y.

    2004-01-01

    The post-BT standard is a new fuel integrity standard or the Atomic Energy Society of Japan that allows temporary boiling transition condition in the evaluation for BWR anticipated operational occurrences. For application of the post-BT standard to BWR anticipated operational occurrences evaluation, it is important to identify which fuel assemblies and which axial, radial positions of fuel rods have temporarily experienced the post-BT condition and to evaluates how high the fuel cladding temperature rise was and how long the dryout duration continued. Therefore, whole bundle simulation, in which each fuel assembly is simulated independently by one thermal-hydraulic component, is considered to be an effective analytical method. In the present study, a best-estimate thermal-hydraulic code, TRACG02, has been modified to extend it predictive capability by implementing the post-BT evaluation model such as the post-BT heat transfer correlation and rewetting correlation and enlarging the number of components used for BWR plant simulation. Based on new evaluation methods, BWR core thermal-hydraulic behavior has been analyzed for typical anticipated operational occurrence conditions. The location where boiling transition occurs and the severity of fuel assembly in the case of boiling transition conditions such as fuel cladding temperature, which are important factors in determining whether the reuse of the fuel assembly can be permitted, were well predicted by the proposed evaluation method. In summary, a new evaluation method for a detailed BWR core thermal-hydraulic analysis based on the post-BT standard of the Atomic Energy Society of Japan has been developed and applied to the evaluation of the post-BT standard during the actual BWR plant anticipated operational occurrences. (author)

  13. 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.

  14. EVALUACIÓN DE LA CALIDAD MICROBIOLÓGICA DEL AGUA ENVASADA EN BOLSAS PRODUCIDA EN SINCELEJO- COLOMBIA

    Directory of Open Access Journals (Sweden)

    Jhon Vidal D

    2009-08-01

    Full Text Available Objetivo. Evaluar la calidad microbiológica y fisico-quimica del agua envasada en bolsas producidad en la ciudad de Sincelejo-Colombia con destino al consumo humano. Materiales y métodos. Para la estimación de organismos coliformes totales y fecales, Pseudomona aeruginosa y mesófilos en el agua envasada de 13 marcas, se utilizó el método de filtración por membrana (FxM. Resultados. El 92 % de las marcas de agua envasada en bolsa que se produce en la ciudad de Sincelejo presentaron bacterias mesófilas en su producto, mientras que en el 33% de ellas se encontraron coliformes totales. Cabe destacar que una marca presentó coliformes fecales, otra Pseudomonas aeruginosa y el reporte microbiano fue mayor en las envasadoras que poseían registro INVIMA. Conclusiones. Gran parte del agua envasada en bolsas de la ciudad de Sincelejo genera un riesgo a la salud de los consumidores, debido a la presencia de microorganismos patógenos, lo que está relacionado con inadecuados procesos de producción y a la intermitencia del suministro del agua utilizada como materia prima.

  15. NUEVOS SISTEMAS ELECTROQUÍMICOS Y FOTOQUÍMICOS PARA EL TRATAMIENTO DE AGUAS RESIDUALES Y DE BEBIDA

    Directory of Open Access Journals (Sweden)

    Victor Sarria

    2008-03-01

    Full Text Available Con la creciente presión hacia un uso más racional del recurso hídrico, el desarrollo de tecnologías apropiadas de tratamientode aguas es cada vez más urgente. Debido a ello, en los últimos años se han propuesto procesos de oxidación fotoquímicos y electroquímicos como alternativa para el tratamiento de aguas contaminadas con sustancias antropogénicas difícilmente biodegradables, así como para eliminar bacterias en aguas destinadas al consumo humano. El objetivo de este trabajo es presentar algunas de nuestras más recientes investigaciones que demuestran que tanto la electroquímica como la fotoquímica, al igual que el acople de estos procesos con tratamientos biológicos, son alternativas muy prometedoras para aumentar la calidad del agua

  16. An analysis of instabilities of nuclear-coupled density-wave in BWR using modern frequency-domain control theory

    International Nuclear Information System (INIS)

    Zhao Yangping; Gao Huahun; Fu Longzhou

    1991-01-01

    A state-of-the-art multi-variable frequency-domain model has been developed for analysis of instabilities of nuclear-coupled density-wave in BWR core. The characteristic locus method is used for analysing the stability of BWR. A computer code-NUCTHIA has been derived. The model has been tested against the existing experimental data and compared with results of past single-variable analyses. By using the NUCTHIA code, the investigations of effects of main system parameters on BWW core stability have also been made. All the results are consistent with the experimental data

  17. Un hidrogel de hidróxido de aluminio para eliminar el arsénico del agua

    OpenAIRE

    Luján Juan Carlos

    2001-01-01

    Objetivos. Describir la síntesis y los resultados preliminares de la aplicación de un hidrogel de hidróxido de aluminio que, agregado directamente al agua, pueda lograr la eliminación total del arsénico, cualquiera que sea la naturaleza del agua y el estado de oxidación del metaloide. Métodos. Las materias primas utilizadas para obtener el hidrogel de hidróxido de aluminio fueron: sulfato de aluminio hidratado (que se utiliza para potabilizar aguas), hipoclorito de calcio en polvo, hidróxido ...

  18. BWR containments license renewal industry report; revision 1. Final report

    International Nuclear Information System (INIS)

    Smith, S.; Gregor, F.

    1994-07-01

    The U.S. nuclear power industry, through coordination by the Nuclear Management and Resources Council (NUMARC), and sponsorship by the U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), has evaluated age-related degradation effects for a number of major plant systems, structures, and components, in the license renewal technical Industry Reports (IR's). License renewal applicants may choose to reference these IR's in support of their plant-specific license renewal applications as an equivalent to the integrated plant assessment provisions of the license renewal rule (IOCFR54). The scope of the IR provides the technical basis for license renewal for U.S. Boiling Water Reactor (BWR) containments. The scope of the report includes containments constructed of reinforced or prestressed concrete with steel liners and freestanding stell containments. Those domestic BWR containments designated as Mark I, Mark II or Mark III are covered, but no containments are addressed before these designs. The report includes those items within the jurisdictional boundaries for metal and concrete containments defined by Section III of the ASME Boiler and Pressure Vessel Code, Division 1, Subsection NE (Class MC) and Division 2 (Class CC) and their supports, but excluding snubbers

  19. A direct comparison of MELCOR 1.8.3 and MAAP4 results for several PWR ampersand BWR accident sequences

    International Nuclear Information System (INIS)

    Leonard, M.T.; Ashbaugh, S.G.; Cole, R.K.; Bergeron, K.D.; Nagashima, K.

    1996-01-01

    This paper presents a comparison of calculations of severe accident progression for several postulated accident sequences for representative Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) nuclear power plants performed with the MELCOR 1.8.3 and the MAAP4 computer codes. The PWR system examined in this study is a 1100 MWe system similar in design to a Westinghouse 3-loop plant with a large dry containment; the BWR is a 1100 MWe system similar in design to General Electric BWR/4 with a Mark I containment. A total of nine accident sequences were studied with both codes. Results of these calculations are compared to identify major differences in the timing of key events in the calculated accident progression or other important aspects of severe accident behavior, and to identify specific sources of the observed differences

  20. Influencia del agua en el desempeño de los pavimentos: lluvia ácida

    Directory of Open Access Journals (Sweden)

    Carlos Javier Obando Gamboa

    2017-11-01

    Full Text Available El agua superficial contribuye en la oxidación del asfalto, más aún cuando ingresa por los poros de la capa de rodadura, sin embargo, el mayor efecto destructivo se manifiesta en forma combinada con las cargas del tráfico ya que el agua alojada en las fisuras, poros e intersticios del pavimento por efecto de la presión de los neumáticos, genera una presión de vacíos que gradualmente destruye el pavimento asfáltico. Es conocido que diferentes agentes químicos pueden modificar las características mecánicas y desempeño de los concretos asfálticos, esta es la base para el uso y desarrollo de diferentes modificadores con el objeto de mejorar el comportamiento del asfalto frente a diferentes solicitudes y/o factores, así mismo las adiciones y aditivos en los pavimentos hidráulicos. Partiendo del hecho que existen agentes químicos y que el agua superficial puede infiltrarse en el concreto asfáltico e hidráulico, y que ésta sometida a fuerzas externas causarán inevitables esfuerzos internos adicionales, podemos inferir que los agentes químicos presentes en el agua de escorrentía o agua lluvia podrían verse potencializados, modificar el comportamiento mecánico de los concretos utilizados en los pavimentos, acelerar los procesos de envejecimiento y causar daños estructurales.