The technology transfer and the Laguna Verde power plants

International Nuclear Information System (INIS)

Garza, R.F. de La

1991-01-01

The process of technology transfer to the construction of Laguna Verde Nuclear Power Plants, Mexico, is described. The options and the efforts for absorbing the technology of Nuclear Power Plant design and construction by the mexican engineers are emphasized. (author)

Transient analysis for Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Ramos Pablos, J.C. et.al.

1991-01-01

Relationship between transients analysis and safety of Laguna Verde nuclear power plant is described a general panorama of safety thermal limits of a nuclear station, as well as transients classification and events simulation codes are exposed. Activities of a group of transients analysis of electrical research institute are also mentioned (Author)

Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde

International Nuclear Information System (INIS)

Salas M, B.

2014-08-01

The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

Structuring a risk-informed and performance-based process for optimization of regulation for Laguna Verde NPP

International Nuclear Information System (INIS)

Rodriguez-Hernandez, A.

2001-01-01

This work describes the plan for a process to incorporate into the regulatory activities the risk information derived from probabilistic risk assessments, as well as information generated by the periodic evaluation of the Maintenance Rule (MR, 10CFR50.65). The current status of the Laguna Verde NPP (LVNPP) risk analysis, PSA Level 1, allows determining in a reliable way the accident scenarios and the involved systems having significant impact on safety. The determination of system's risk significance allows carrying out a prioritization of safety issues to be evaluated and inspected; for example, operational events, changes to technical specifications, design modifications, inspection priorities, etc. In addition, complementary and basic information are the results generated by the performance monitoring of structures, systems and components (SSCs) under the scope of the MR. The SSCs performance trends are indicatives to focus evaluation and inspection activities on important issues. Then, with the reportability in short periods the performance evaluations of SSCs and the incorporation of a process of risk management, the evaluation and inspection activities will be directed to those risk significant systems showing degraded performance. Therefore, based on systems performance results and risk information, it is feasible to have certain flexibility or a better balance between the regulatory requirements. Inside this process, a consensus is needed with the utility to establish quality attributes for the plant-specific PSA, as well as the rules to be followed in the use of this tool and the kind of information to be reported for MR results. (author)

Dynamic analysis of the condensate and of the feed water in the Laguna Verde nuclear power station; Analisis dinamico del sistema de condensado y agua de alimentacion de la nucleoelectrica de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Macedo Muth, Javier; Sandoval Pena, Ramon [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1988-12-31

This article shows a non-lineal mathematical model for the condensate, and feed water systems and for feed water heater drains at the Laguna Verde Nuclear Power Station for its simulation in real time. The model allows the calculation of flows and pressures in all the piping system and equipment that integrate the systems. It was obtained by using the force unbalance in the fluid concept and is capable of reproducing its dynamic behavior through variations induced by the different operation modes and more common failures. The final model objective is to form part of the Laguna Verde simulator that will be used for operator training of this Nuclear Power Plant. [Espanol] En este articulo se muestra un modelo matematico no lineal de los sistemas de condensado, agua de alimentacion y drenes de calentadores de la central nuclear de Laguna Verde para su simulacion en tiempo real. El modelo permite calcular los flujos y las presiones en toda la red de tuberias y equipos que integran los sistemas. Se obtuvo utilizando el concepto de desbalance de fuerzas en el fluido, y es capaz de reproducir su comportamiento dinamico ante variaciones inducidas por los diversos modos de operacion y fallas mas comunes. El objetivo final del modelo es formar parte del simulador de Laguna Verde que se empleara para el adiestramiento de los operadores de dicha central nuclear.

Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis

International Nuclear Information System (INIS)

Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

1993-01-01

The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the I nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant , CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

Proposal for implementation of alternative source term in the nuclear power plant of Laguna Verde; Propuesta de implementacion del termino fuente alternativo en la central nuclear Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Bazan L, A.; Lopez L, M.; Vargas A, A.; Cardenas J, J. B. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km. 7.5 Carretera Veracruz-Medellin, Dos Bocas, Veracruz (Mexico)], e-mail: ariadna.bazan@cfe.gob.mx

2009-10-15

In 2010 the nuclear power plant of Laguna Verde will implement the extended power upbeat in both units of the plant. Agree with methodology of NEDC-33004P-A, (constant pressure power up rate), and the source term of core, for accidents evaluations, were increased in proportion to the ratio of power level. This means that for the case of a design basis accident of loss of coolant an increase of power of 15% originated an increase of 15% in dose to main control room. Using the method of NEDC-33004P-A to extended power upbeat conditions was determined that the dose value to main control room is very near to regulatory limit established by SRP 6.4. By the above and in order to recover the margin, the nuclear power plant of Laguna Verde will calculate an alternative source term following the criteria established in RG 1.183 (alternative radiological source term for evaluating DBA at nuclear power reactor). This approach also have a more realistic dose value using the criterion of 10-CFR-50.67, in addition is predicted to get the benefit of additional operational flexibilities. This paper present the proposal of implementing the alternative source term in Laguna Verde. (Author)

Electrical systems at the nuclear power plant of Laguna Verde after the event in Fukushima; Sistemas electricos en la central nucleoelectrica Laguna Verde despues del evento de Fukushima

Energy Technology Data Exchange (ETDEWEB)

Lopez J, J. F., E-mail: jflopez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose M. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

2016-09-15

During the event at the nuclear power plant of Fukushima Daichii (Japan), the electrical systems were affected both Onsite and Offsite, which were lost for a long time with irreversible consequences. Therefore, the Mexican Regulatory Body known as the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has taken various actions to review the current capacity of the electrical systems at the nuclear power plant of Laguna Verde (NPP-LV) before an event beyond the design bases. The CNSNS made special inspections to the NPP-LV to verify the current capacity of the electrical systems of Ac and Dc; as a result of the inspections, requirements were generated that must be met to demonstrate that has the capacity to deal with events beyond the design bases. In addition, CNSNS has participated in the Ibero-American Forum to deal with resistance testing. Is important to note that prior to the event at the nuclear power plant of Fukushima, the NPP-LV had implemented 1) the project Extended Power Increase in both Units of the NPP-LV, and 2) the Generic Charter 2006-02, both issues are considered contributions in the robustness of electrical systems. But it is also important to mention that the US Nuclear Regulatory Commission will soon issue mitigation strategies for a Station Blackout event, which could involve new actions at nuclear power plants. Based on the aforementioned, the CNSNS concludes that all the actions being taken contribute to the strengthening of the NPP-LV electrical systems, in order to increase their reliability, safety and operation when these are required to deal with events beyond the design bases as the event occurred in Fukushima Daichii and avoid as far as possible, damage in the reactor cores of the NPP-LV. (Author)

Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis; Analisis de Eventos Internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Analisis de sistemas

Energy Technology Data Exchange (ETDEWEB)

Huerta B, A; Aguilar T, O; Nunez C, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

1993-07-01

The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant{sup ,} CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

Modernization of the turbo in the Laguna Verde Nuclear Power Plant; Modernizacion del turbogrupo en la Central Nuclear de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Liebana, B.; Merino, A.; Cobos, A.; Gonzalez, J. J.

2010-07-01

The power increase of the Laguna Verde Nuclear Power Plant is a project for the rehabilitation and modernization of the turbo and associated equipment to get an increase of its power and of its service life. The project scope includes the design, the engineering, the equipment supply, the installation, the testing and the commissioning. This paper describes the first phase of the project.

Generation of the ECP database (ECP02.DAT) at the beginning of the cycle 1 of the Unit 1 of Laguna Verde; Generacion de la base ECP (ECP02.DAT) al inicio del ciclo 1 de la Unidad 1 de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Perusquia C, R. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1992-10-15

In order to carrying out a comparison among the results provided for the Program of Estimate of the ECP Critical Position and the Shutdown/Startup produced in the Cycle 1 of the Unit 1 of Laguna Verde, it was generated the base of the ECP program, following the outlines settled down in the Procedure 'Generation of ECP Database for Laguna Verde' (IT.SN/DFR 074). Next the data sheets filled when being generated the ECP02.DAT database at the beginning of the cycle are provided. In the IT.SN/DFR 079 report 'Adjustment and Preliminary Evaluation of the Predictions of Criticity of the ECP Program with Reported Data of Cycle 1 of the Unit 1 of Laguna Verde, the results of the comparison among the estimates of the ECP program using the ECP02.DAT with the real data of the Cycle 1 of the Unit 1 of Laguna Verde are presented. (Author)

Temporary storage in dry of the spent nuclear fuel in the Nuclear Power Plant of Laguna Verde; Almacenamiento temporal en seco del combustible nuclear gastado en la Central Nuclear Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Hernandez M, N.; Vargas A, A., E-mail: natividad.hernandez@cfe.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Carretera Veracruz-Medellin Km. 7.5, 94270 Dos Bocas, Veracruz (Mexico)

2013-10-15

To guarantee the continuity in the operation of the two nuclear reactors of the nuclear power plant of Laguna Verde (NPP-L V) is an activity of high priority of the Comision Federal de Electricidad (CFE) in Mexico. At the present time, the CFE is working in the storage project in dry of the spent fuel with the purpose of to liberate space of the pools and to have the enlarged capacity of storage of the spent fuel that is discharged of the reactors. This work presents the storage option in dry of the spent fuel, considering that the original capacity of the spent fuel pools of the NPP-L V was of 1242 spaces each one and that in 1991, through a modification of the original design, the storage capacity was increased to 3177 spaces by pool. At present, the cells occupied by unit are of 2165 (68%) for the Unit-I and 1839 (58%) for the Unit-2, however, in 2017 and 2022 the capacity to discharge the complete core will be limited by what is required of a retirement option of spent fuel assemblies to liberate spaces. (author)

Negative sequence relay applied to generator 1 of the Laguna Verde nuclear power plant; Aplicacion de un relevador de secuencia negativa en el generador 1 de la central de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Diaz de la Serna P, Enrique [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1988-12-31

The rotor of a synchronous generator can be dangerously heated in a short time by stator current unbalance, therefore it must be protected with a specific relay. This article discusses the protection and the adjustments selected for Unit 1 of the Comision Federal de Electricidad Laguna Verde Nuclear Nuclear Power Station. [Espanol] El rotor de un generador sincrono puede calentarse peligrosamente en un tiempo corto debido a desbalance de corrientes en el estator, por lo que debe protegerse con un relevador especifico. En este articulo se describen la proteccion y los ajustes seleccionados para la unidad 1, de la central nucleoelectrica Laguna Verde de la Comision Federal de Electricidad.

Modeling of the vapor cycle of Laguna Verde with the PEPSE code to conditions of thermal power licensed at present (2027 MWt); Modelado del ciclo de vapor de Laguna Verde con el codigo PEPSE a condiciones de potencia termica actualmente licenciada (2027 MWt)

Energy Technology Data Exchange (ETDEWEB)

Castaneda G, M. A.; Maya G, F.; Medel C, J. E.; Cardenas J, J. B.; Cruz B, H. J.; Mercado V, J. J., E-mail: miguel.castaneda01@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)

2011-11-15

By means of the use of the performance evaluation of power system efficiencies (PEPSE) code was modeled the vapor cycle of the nuclear power station of Laguna Verde to reproduce the nuclear plant behavior to conditions of thermal power, licensed at present (2027 MWt); with the purpose of having a base line before the implementation of the project of extended power increase. The model of the gauged vapor cycle to reproduce the nuclear plant conditions makes use of the PEPSE model, design case of the vapor cycle of nuclear power station of Laguna Verde, which has as main components of the model the great equipment of the vapor cycle of Laguna Verde. The design case model makes use of information about the design requirements of each equipment for theoretically calculating the electric power of exit, besides thermodynamic conditions of the vapor cycle in different points. Starting from the design model and making use of data of the vapor cycle measured in the nuclear plant; the adjustment factors were calculated for the different equipment s of the vapor cycle, to reproduce with the PEPSE model the real vapor cycle of Laguna Verde. Once characterized the model of the vapor cycle of Laguna Verde, we can realize different sensibility studies to determine the effects macros to the vapor cycle by the variation of certain key parameters. (Author)

Laguna Verde - A photo story

Energy Technology Data Exchange (ETDEWEB)

NONE

1980-04-15

Safety is one of the main factors in the construction and operation of a modern nuclear power plant. There are many barriers between the fission products produced in the fuel elements of the core, and the environment: the cladding of the fuel pins which are enclosed in the reactor core, the pressure vessel containing the core and which in turn is enclosed in the reactor containment, all this being located in a low-pressure secondary containment or reactor building. Despite these precautions, nuclear safety is still a widely-discussed issue. The important fact remains, however, that there has not been a single radiation-induced fatality or serious injury at any civilian nuclear power plant during 20 years of nuclear power generation. This includes the accident that occurred in March 1979 at the Three Mile Island nuclear plant in the USA. A substantial component contributing to safety in a nuclear power plant is the containment. The following photos of Laguna Verde, Mexico's first nuclear power station being constructed at Alta Lucero in Vera Cruz, give an impression of how strong this concrete and steel containment actually is. Laguna Verde consists of two 600 MWe units and the plant is scheduled for commercial operation in 1982. Construction began in 1974. Both units are boiling-water reactors. The photos show, in general, the construction of the primary containment for the reactors (the dry wells). The dry well contains the reactor itself and has two layers: the leak-tight steel liner and the heavy concrete building. The purpose of the primary containment is to retain steam and gases that might escape in an emergency and to direct these through relief tubes to a water pond for cooling. Surrounding this primary containment will be a reactor building which serves as a secondary low-pressure containment, able to operate at pressures up to 0.2 atmospheres.

Experiences in the implementation of the Coaching project in the nuclear power plant of Laguna Verde (NPP-L V); Experiencias en la implementacion del proyecto Coaching en la Central Nucleoelectrica Laguna Verde (CNLV)

Energy Technology Data Exchange (ETDEWEB)

Mendez M, H. I., E-mail: hugo.mendez01@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Departamento del Centro de Entrenamiento, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

2012-10-15

This document has the purpose of to share acquired experiences during the implementation of the Coaching project focused the training of supervisors and directive personnel of the nuclear power plant of Laguna Verde (NPP-L V). Derived of the improvement areas identified by the supervisor organization of the nuclear power stations WANO (World Association Nuclear of Operators) and of the auto-evaluations realized by the expert personnel of the same power station that based on external experiences carried out through the Benchmarking (comparison with other power stations) they have reflected the necessity to activate a training process in Coaching with a practical focus toward the directive and supervisor personnel in the power station. By means of the observation of the personnel's acting so much in the control rooms like in different areas, three focus areas have been identified for the training in Coaching, these are the personnel's motivation, the organizational communication so much in vertical form as horizontal and the perception of confidence lack among directive, supervisors, operators and technicians. The plan focused in the abilities training of Coaching with practical sense was development, supported with an evaluation of 360 grades as tool of competitions development through a computer application e-Coaching. The use of application and Coaching following techniques facilitated the conformation of the practical focus, same that are of continuous use starting from the training of the supervisor and directive personnel. (Author)

Considerations for increasing unit 1 spent fuel pool capacity at the Laguna Verde station

International Nuclear Information System (INIS)

Vera, A.

1992-01-01

To increase the spent fuel storage capacity at the Laguna Verde Station in a safe and economical manner and assure a continuous operation of the first Mexican Nuclear Plant, Comision Federal de Electricidad (CFE), the Nation's Utility, seeked alternatives considering the overall world situation, the safety and licensing aspects, as well as the economics and the extent of the nuclear program of Mexico. This paper describes the alternatives considered, their evaluation and how the decision taken by CFE in this field, provides the Laguna Verde Station with a maximum of 37 years storage capacity plus full core reserve

Simulation of the electric systems of the Laguna Verde nuclear power station; Simulacion de los sistemas electricos de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Rodriguez Lozano, Saul; Ruiz Ponce, Gerardo E [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1992-03-01

In this article, the electric system models of the Laguna Verde Nuclear Power Station (CNLV) simulator, are presented. These models permit the functioning simulation, in the different operation modes of the main generator (Ruiz and Rodriguez 1991a), of the auxiliaries system and of the substation (Ruiz and Rodriguez 1991b), and of the emergency diesel generators system (Ruiz and Rodriguez 1991c). The general characteristics of such systems, considered as the basis to obtain the representative models, which were developed as modules in an independent way to be integrated in the simulator, are also described. [Espanol] En este articulo, se presenta los modelos de los sistemas electricos del simulador de la Central Laguna Verde (CLV). Estos modelos permiten simular el funcionamiento, en los diferentes modos de operacion del generador principal (Ruiz y Rodriguez, 1991a), del sistema de auxiliares y de la subestacion (Ruiz y Rodriguez, 1991b) y del sistema de generadores diesel de emergencia (Ruiz y Rodriguez, 1991c). Asimismo, se describen las caracteristicas generales de tales sistemas, consideradas como la base para obtener los modelos representativos, los cuales fueron desarrollados como modulos en forma independiente para integrarse al simulador.

Design optimization for fuel reloading in Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Cortes Campos, C.C.; Montes Tadeo, J.L.

1991-01-01

Procedure followed to perform the design optimation in fuel reloading is described in general words and also is shown an example in which such procedure was uses for analysis of BWR type reactor in unit 1 of Laguna Verde nuclear power plant (Author)

Geological-Geophysical integration in the Laguna Verde Nuclear Power Plant site and its surroundings

International Nuclear Information System (INIS)

Flores Ruiz, J.H.

1990-01-01

As part of comprehensive, nationwide evaluation of the Seismic risk at the Nuclear Power Plant site of the Laguna Verde (LVNP) the first of the acceleration ground motion maps, covering for a circular distance value 200 Km around, has been prepared. The maps were created the acceleration grounds motion expected over intervals 1, 25, 50, 100 and 200 years by using Gumbel's (I, III) theory of extreme value statistics of the seismic data. It's reaching operating basis earthquake (OBE) value 0.1 g. in 100 years forecasting and 200 years this value is 0.114 G is more than OBE, but minor than safety shutdown earthquake (SSE). The acceleration ground motion risk maps are compared to regional geology, seismicity (1920-1982) and gravity data. Good correlations are found between the accelerations ground motion risk and seismicity. A spatial correlation observed between gravity and structure with acceleration ground motion rise is considered a secondary the structural effect. Locations of the currently operating NPP correspond to low seismicity risk area. Based on these comparations, it is concluded that the method provides geologically reasonable results which are usable in a nationwide NPP assessment program (Author)

Experiences in the implementation of the Coaching project in the nuclear power plant of Laguna Verde (NPP-L V)

International Nuclear Information System (INIS)

Mendez M, H. I.

2012-10-01

This document has the purpose of to share acquired experiences during the implementation of the Coaching project focused the training of supervisors and directive personnel of the nuclear power plant of Laguna Verde (NPP-L V). Derived of the improvement areas identified by the supervisor organization of the nuclear power stations WANO (World Association Nuclear of Operators) and of the auto-evaluations realized by the expert personnel of the same power station that based on external experiences carried out through the Benchmarking (comparison with other power stations) they have reflected the necessity to activate a training process in Coaching with a practical focus toward the directive and supervisor personnel in the power station. By means of the observation of the personnel's acting so much in the control rooms like in different areas, three focus areas have been identified for the training in Coaching, these are the personnel's motivation, the organizational communication so much in vertical form as horizontal and the perception of confidence lack among directive, supervisors, operators and technicians. The plan focused in the abilities training of Coaching with practical sense was development, supported with an evaluation of 360 grades as tool of competitions development through a computer application e-Coaching. The use of application and Coaching following techniques facilitated the conformation of the practical focus, same that are of continuous use starting from the training of the supervisor and directive personnel. (Author)

Gamma thermometer longevity test: Laguna Verde 2 instruments recent performance

International Nuclear Information System (INIS)

Cuevas V, G.; Avila N, A.; Calleros M, G.

2013-10-01

This paper is informative of the General Electric Hitachi and Global Nuclear Fuel - Americas are collaboration with Comision Federal de Electricidad in a longevity test of thermocouples as power monitoring devices. The test conclusions will serve for final engineering design in detailing the Automated Fixed In-core Probes for calibration of the Local Power Range Monitors (LPRMs) of the Economic Simplified Boiling Water Reactor. This paper introduces the collaboration description and some recent performance evaluation of the thermocouples that are sensitive to gamma radiation and are known generically as Gamma Thermometers (G T). The G Ts in Laguna Verde 2 are radially located inside six instrumentation tubes in the core and consist of seven thermocouples, four are aligned with the LPRM heights and three are axially located between LPRM heights. The Laguna Verde 2 G T test has become the longest test of thermocouples as power monitoring devices in a BWR industry history and confirms their reliability in terms of time-dependent small noise under steady state reactor conditions and good agreement against Traversing In-core Probes power measurements. (Author)

Gamma thermometer longevity test: Laguna Verde 2 instruments recent performance

Energy Technology Data Exchange (ETDEWEB)

Cuevas V, G. [Global Nuclear Fuel, Americas, 3901 Castle Hayne Road, Wilmington, North Carolina (United States); Avila N, A.; Calleros M, G., E-mail: Gabriel.Cuevas-Vivas@gnf.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verda, Carretera Veracruz-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

2013-10-15

This paper is informative of the General Electric Hitachi and Global Nuclear Fuel - Americas are collaboration with Comision Federal de Electricidad in a longevity test of thermocouples as power monitoring devices. The test conclusions will serve for final engineering design in detailing the Automated Fixed In-core Probes for calibration of the Local Power Range Monitors (LPRMs) of the Economic Simplified Boiling Water Reactor. This paper introduces the collaboration description and some recent performance evaluation of the thermocouples that are sensitive to gamma radiation and are known generically as Gamma Thermometers (G T). The G Ts in Laguna Verde 2 are radially located inside six instrumentation tubes in the core and consist of seven thermocouples, four are aligned with the LPRM heights and three are axially located between LPRM heights. The Laguna Verde 2 G T test has become the longest test of thermocouples as power monitoring devices in a BWR industry history and confirms their reliability in terms of time-dependent small noise under steady state reactor conditions and good agreement against Traversing In-core Probes power measurements. (Author)

National autonomous university of Mexico RELAP/SCDAPSIM-based plant simulation and training applications to the Laguna Verde NPP

International Nuclear Information System (INIS)

Chavez-Mercado, C.; Hohorst, J.K.; Allison, C.M.

2004-01-01

The RELAP/SCDAPSIM code, designed to predict the behavior of reactor systems during normal and accident conditions, is being developed by Innovative Systems Software as part of the International SCDAP Development and Training Program (SDTP). This code is being used as the simulator engine for the National Autonomous University of Mexico's Simulation and Training Facility located at the Campus Morelos in Jiutepec, Mexico. This paper describes the RELAP/SCDAPSIM code, the Simulation and Training facility at the National Autonomous University of Mexico, and the application of the training system to the Laguna Verde Nuclear Power Plant located in the Mexican state of Veracruz. (author)

Generation of the ECP database (ECP01.DAT) of the cycle 1 of the Unit 1 of Laguna Verde with burnt of 1377 MWD/MT; Generacion de la base ECP (ECP01.DAT) del ciclo 1 de la Unidad 1 de Laguna Verde con quemado de 1377 MWD/MT

Energy Technology Data Exchange (ETDEWEB)

Perusquia C, R. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1992-10-15

In order to carrying out a comparison among the results provided by the Program of Estimate of the ECP Critical Position and the Shutdown/Startup produced in the Cycle 1 of the Unit 1 of Laguna Verde, it was generated the base of the ECP program, following the outlines settled down in the Procedure 'Generation of ECP Database for Laguna Verde' (IT.SN/DFR-074). Next the data sheets filled when being generated the ECP01.DAT database with a burnt of 1377 MWD/MT are provided. In the report IT.SN/DFR-079 'Adjustment and Preliminary Evaluation of the Predictions of Criticity of the ECP Program with Reported Data of the Cycle 1 of the Unit 1 of Laguna Verde', the results of the comparison among those estimates of the ECP program using the ECP01.DAT database with the real data of the Cycle 1 of the Unit 1 of Laguna Verde are presented. (Author)

Generation of the ECP database (ECP02.DAT) at the beginning of the cycle 1 of the Unit 1 of Laguna Verde

International Nuclear Information System (INIS)

Perusquia C, R.

1992-10-01

In order to carrying out a comparison among the results provided for the Program of Estimate of the ECP Critical Position and the Shutdown/Startup produced in the Cycle 1 of the Unit 1 of Laguna Verde, it was generated the base of the ECP program, following the outlines settled down in the Procedure 'Generation of ECP Database for Laguna Verde' (IT.SN/DFR 074). Next the data sheets filled when being generated the ECP02.DAT database at the beginning of the cycle are provided. In the IT.SN/DFR 079 report 'Adjustment and Preliminary Evaluation of the Predictions of Criticity of the ECP Program with Reported Data of Cycle 1 of the Unit 1 of Laguna Verde, the results of the comparison among the estimates of the ECP program using the ECP02.DAT with the real data of the Cycle 1 of the Unit 1 of Laguna Verde are presented. (Author)

Prototype fuel fabrication for nuclear reactors of Laguna Verde

International Nuclear Information System (INIS)

Nocetti, C.; Torres, J.; Medrano, A.

1996-01-01

Four prototype fuel bundles for the Laguna Verde Nuclear Power Plant have been fabricated. the type of nuclear fuel produced is described and the process used is commented. As an example of the fabrication criteria adopted, the production model to determine the density of the U O 2 pellets for the different batches of ceramic powder is described. the results are evaluated using the statistical indexes C p and C pk . (author)

Modeling of the vapor cycle of Laguna Verde with the PEPSE code to conditions of thermal power licensed at present (2027 MWt)

International Nuclear Information System (INIS)

Castaneda G, M. A.; Maya G, F.; Medel C, J. E.; Cardenas J, J. B.; Cruz B, H. J.; Mercado V, J. J.

2011-11-01

By means of the use of the performance evaluation of power system efficiencies (PEPSE) code was modeled the vapor cycle of the nuclear power station of Laguna Verde to reproduce the nuclear plant behavior to conditions of thermal power, licensed at present (2027 MWt); with the purpose of having a base line before the implementation of the project of extended power increase. The model of the gauged vapor cycle to reproduce the nuclear plant conditions makes use of the PEPSE model, design case of the vapor cycle of nuclear power station of Laguna Verde, which has as main components of the model the great equipment of the vapor cycle of Laguna Verde. The design case model makes use of information about the design requirements of each equipment for theoretically calculating the electric power of exit, besides thermodynamic conditions of the vapor cycle in different points. Starting from the design model and making use of data of the vapor cycle measured in the nuclear plant; the adjustment factors were calculated for the different equipment s of the vapor cycle, to reproduce with the PEPSE model the real vapor cycle of Laguna Verde. Once characterized the model of the vapor cycle of Laguna Verde, we can realize different sensibility studies to determine the effects macros to the vapor cycle by the variation of certain key parameters. (Author)

Start-up and commercial operation of the Laguna Verde power plants, unit 1

International Nuclear Information System (INIS)

Torres R, J.F.

1991-01-01

The main features of the unit 1 of the Laguna Verde Power Plant is presented as well as the phases of the start-up process. The process includes various steps and tests up to start the commercial operation. (author)

Severe Accident Simulation of the Laguna Verde Nuclear Power Plant

Directory of Open Access Journals (Sweden)

Gilberto Espinosa-Paredes

2012-01-01

Full Text Available The loss-of-coolant accident (LOCA simulation in the boiling water reactor (BWR of Laguna Verde Nuclear Power Plant (LVNPP at 105% of rated power is analyzed in this work. The LVNPP model was developed using RELAP/SCDAPSIM code. The lack of cooling water after the LOCA gets to the LVNPP to melting of the core that exceeds the design basis of the nuclear power plant (NPP sufficiently to cause failure of structures, materials, and systems that are needed to ensure proper cooling of the reactor core by normal means. Faced with a severe accident, the first response is to maintain the reactor core cooling by any means available, but in order to carry out such an attempt is necessary to understand fully the progression of core damage, since such action has effects that may be decisive in accident progression. The simulation considers a LOCA in the recirculation loop of the reactor with and without cooling water injection. During the progression of core damage, we analyze the cooling water injection at different times and the results show that there are significant differences in the level of core damage and hydrogen production, among other variables analyzed such as maximum surface temperature, fission products released, and debris bed height.

Proposal for implementation of alternative source term in the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Bazan L, A.; Lopez L, M.; Vargas A, A.; Cardenas J, J. B.

2009-10-01

In 2010 the nuclear power plant of Laguna Verde will implement the extended power upbeat in both units of the plant. Agree with methodology of NEDC-33004P-A, (constant pressure power up rate), and the source term of core, for accidents evaluations, were increased in proportion to the ratio of power level. This means that for the case of a design basis accident of loss of coolant an increase of power of 15% originated an increase of 15% in dose to main control room. Using the method of NEDC-33004P-A to extended power upbeat conditions was determined that the dose value to main control room is very near to regulatory limit established by SRP 6.4. By the above and in order to recover the margin, the nuclear power plant of Laguna Verde will calculate an alternative source term following the criteria established in RG 1.183 (alternative radiological source term for evaluating DBA at nuclear power reactor). This approach also have a more realistic dose value using the criterion of 10-CFR-50.67, in addition is predicted to get the benefit of additional operational flexibilities. This paper present the proposal of implementing the alternative source term in Laguna Verde. (Author)

Electrical systems at the nuclear power plant of Laguna Verde after the event in Fukushima

International Nuclear Information System (INIS)

Lopez J, J. F.

2016-09-01

During the event at the nuclear power plant of Fukushima Daichii (Japan), the electrical systems were affected both Onsite and Offsite, which were lost for a long time with irreversible consequences. Therefore, the Mexican Regulatory Body known as the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has taken various actions to review the current capacity of the electrical systems at the nuclear power plant of Laguna Verde (NPP-LV) before an event beyond the design bases. The CNSNS made special inspections to the NPP-LV to verify the current capacity of the electrical systems of Ac and Dc; as a result of the inspections, requirements were generated that must be met to demonstrate that has the capacity to deal with events beyond the design bases. In addition, CNSNS has participated in the Ibero-American Forum to deal with resistance testing. Is important to note that prior to the event at the nuclear power plant of Fukushima, the NPP-LV had implemented 1) the project Extended Power Increase in both Units of the NPP-LV, and 2) the Generic Charter 2006-02, both issues are considered contributions in the robustness of electrical systems. But it is also important to mention that the US Nuclear Regulatory Commission will soon issue mitigation strategies for a Station Blackout event, which could involve new actions at nuclear power plants. Based on the aforementioned, the CNSNS concludes that all the actions being taken contribute to the strengthening of the NPP-LV electrical systems, in order to increase their reliability, safety and operation when these are required to deal with events beyond the design bases as the event occurred in Fukushima Daichii and avoid as far as possible, damage in the reactor cores of the NPP-LV. (Author)

Super compacting of drums with dry solid radioactive waste in the nuclear power plant of Laguna Verde;Super compactacion de bidones con desecho radiactivo solido seco en la central nucleo electrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Ramirez G, R.; Lara H, M. A.; Cabrera Ll, M.; Verdalet de la Torre, O., E-mail: marco.lara@cfe.gob.m [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Nautla-Cardel Km. 42.5, Alto Lucero, Veracruz (Mexico)

2009-10-15

The nuclear power plant of Laguna Verde located in the Gulf of Mexico, completes in this 2009, nineteen years to produce by nuclear means 4.78% of the electric power that Mexico requires daily. During this time, the Unit 1 has generated more of 88.85 million mega watt-hour and the Unit 2 more of 69.48 million mega watt-hour with an availability average of 83.55%. Derived of their operation cycles, the nuclear power plant has generated (as any other installation of its type) radioactive wastes of low activity that at the moment are temporarily stored in the site. Due to the life cycle of the nuclear power plant, actually has become necessary to begin a project series focused to continue guaranteeing the storage of these wastes, guarantee that is a license requirement for the operation of this nuclear installation before the National Commission of Nuclear Security and Safeguards. The Federal Commission of Electricity beginning a project that allows continue guaranteeing space of sufficient storage for the wastes that the nuclear power plant of Laguna Verde could generate for the rest of its useful life, this project consisted on a process of physical volume reduction of dry solid radioactive wastes denominated super compacting, it has made possible to reduce the volume that these wastes occupy in the temporary storage noted Dry Solid Radioactive Wastes Deposit located inside the site that occupies the nuclear power plant of Laguna Verde. This work presents the super compacting results, as well as a description of the realization of this task until concluding with the super compacting of 5,854 drums with dry solid radioactive waste of low activity. We will enunciate which were the radiological controls that the Department of Radiological Protection of the nuclear power plant of Laguna Verde applied to this work that was realized for first time in Mexico and the nuclear power plant. (Author)

Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

International Nuclear Information System (INIS)

Torres Ramirez, J.F.

1991-01-01

Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

Energy Technology Data Exchange (ETDEWEB)

Huerta B, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

1995-07-01

This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

Safety evaluation of the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Delgado G, J.L.

1991-01-01

The present work describe the licensing process for the first nuclear power plant built in Mexico, it presents the difficulties found during the several years of construction and tests until the phrase a level of safety equivalent to that of the country of origin of the nuclear steam supply system could be applicable to Laguna Verde, at least from the point of view of the mexican regulatory body, and also that this statement could be signed for the inspectors of international organizations. (author)

Modernization of the turbo in the Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Liebana, B.; Merino, A.; Cobos, A.; Gonzalez, J. J.

2010-01-01

The power increase of the Laguna Verde Nuclear Power Plant is a project for the rehabilitation and modernization of the turbo and associated equipment to get an increase of its power and of its service life. The project scope includes the design, the engineering, the equipment supply, the installation, the testing and the commissioning. This paper describes the first phase of the project.

The continuous improvement system of nuclear power plant of Laguna Verde; El sistema de mejora continua de la central nucleoelectrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Rivera C, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km. 42.5 Cardel-Nautla, Veracruz (Mexico)], e-mail: arr99999@cfe.gob.mx

2009-10-15

This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

Fuel failure at the Laguna Verde unit 1- during Cycle 4

International Nuclear Information System (INIS)

Espinosa Vega, Juan Manuel

1996-01-01

The present work describes the event occurred at the Laguna Verde nuclear power plants Unit 1 during its fourth cycle ensembles; the first failure, by means of a test of power suppression, and the second one, during the sipping accomplished in the four refuelling of the unit. Also it describes the re-evaluation of the event accomplished by the licenser, the manufacturer and the Mexican agency

Generation of the ECP database (ECP01.DAT) of the cycle 1 of the Unit 1 of Laguna Verde with burnt of 1377 MWD/MT

International Nuclear Information System (INIS)

Perusquia C, R.

1992-10-01

In order to carrying out a comparison among the results provided by the Program of Estimate of the ECP Critical Position and the Shutdown/Startup produced in the Cycle 1 of the Unit 1 of Laguna Verde, it was generated the base of the ECP program, following the outlines settled down in the Procedure 'Generation of ECP Database for Laguna Verde' (IT.SN/DFR-074). Next the data sheets filled when being generated the ECP01.DAT database with a burnt of 1377 MWD/MT are provided. In the report IT.SN/DFR-079 'Adjustment and Preliminary Evaluation of the Predictions of Criticity of the ECP Program with Reported Data of the Cycle 1 of the Unit 1 of Laguna Verde', the results of the comparison among those estimates of the ECP program using the ECP01.DAT database with the real data of the Cycle 1 of the Unit 1 of Laguna Verde are presented. (Author)

Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

International Nuclear Information System (INIS)

Huerta B, A.; Lopez M, R.

1995-01-01

This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

International Nuclear Information System (INIS)

Huerta B, A.; Lopez M, R.

1995-01-01

This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

Introduction of fuel GE14 in the nuclear power plant of Laguna Verde for the extended increase of power; Introduccion del combustible GE14 en la central nuclear Laguna Verde para el aumento de potencia extendido

Energy Technology Data Exchange (ETDEWEB)

Hernandez M, N.; Vargas A, A. F.; Cardenas J, J. B.; Contreras C, P. [CFE, Central Nuclear Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5 (Mexico)]. e-mail: natividad.hernandez@cfe.gob.mx

2008-07-01

The project of extended increase of power responds to a necessity of electrical energy in the country, increasing the thermal exit of the reactors of the nuclear power plant of Laguna Verde of 2027 MWt to 2317 MWt. In order to support this transition, changes will make in the configuration of the reactor core and in the operation strategies of the cycle, also they will take initiatives to optimize the economy in fuel cycle. At present in both reactors of the nuclear plant of Laguna Verde fuel GE12 is used. The fuel GE14 presents displays with respect to the GE12, some improvements in the mechanical design and consequently in its performance generally. Between these improvements we can mention: 1. Spacers of high performance. 2. Shielding with barrier. 3. Filter for sweepings {sup d}ebris{sup a}nd 4. Fuel rods of minor partial length. The management of nuclear power plants has decided to introduce the use of fuel GE14 in Laguna Verde in the reload 14 for Unit 1 and of the reload 10 for Unit 2. The process of new introduction fuel GE14 consists of two stages, first consists on subjecting the one new design of fuel to the regulator organism in the USA: Nuclear Regulatory Commission, in Mexico the design must be analyzed and authorized by the National Commission of Nuclear Safety and Safeguards, for its approval of generic form, by means of the demonstration of the fulfillment with the amendment 22 of GESTAR II, the second stage includes the specific analyses of plant to justify the use of the new fuel design in a reload core. The nuclear plant of Laguna Verde would use some of the results of the security analyses that have been realized for the project of extended increase of power with fuel GE14, to document the specific analyses of plant with the new fuel design. The result of the analyses indicates that the reload lots are increased of 116-120 assemblies in present conditions (2027 MWt) to 140-148 assemblies in conditions of extended increase of power (2317 MWt

Simulation of overpressure events with a Laguna Verde model for the RELAP code to conditions of extended power up rate; Simulacion de eventos de sobrepresion con un modelo de Laguna Verde para el codigo RELAP a condiciones de aumento de potencia extendido

Energy Technology Data Exchange (ETDEWEB)

Rodriguez H, A.; Araiza M, E.; Fuentes M, L.; Ortiz V, J., E-mail: andres.rodriguez@inin.gob.mx [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2012-10-15

In this work the main results of the simulation of overpressure events are presented using a model of the nuclear power plant of Laguna Verde developed for the RELAP/SCDAPSIM code. As starting point we have the conformation of a Laguna Verde model that represents a stationary state to similar conditions to the operation of the power station with Extended Power Up rate (EPU). The transitory of simulated pressure are compared with those documented in the Final Safety Analysis Report of Laguna Verde (FSAR). The results of the turbine shot transitory with and without by-pass of the main turbine are showed, and the event of closes of all the valves of main vapor isolation. A preliminary simulation was made and with base in the results some adjustments were made for the operation with EPU, taking into account the Operation Technical Specifications of the power station. The results of the final simulations were compared and analyzed with the content in the FSAR. The response of the power station to the transitory, reflected in the model for RELAP, was satisfactory. Finally, comments about the improvement of the model are included, for example, the response time of the protection and mitigation systems of the power station. (Author)

Components production and assemble of the irradiation capsule of the Surveillance Program of Materials of the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Medrano, A.

2009-01-01

To predict the effects of the neutrons radiation and the thermal environment about the mechanical properties of the reactor vessel materials of the nuclear power plant of Laguna Verde, a surveillance program is implemented according to the outlines settled by Astm E185-02 -Standard practice for design of surveillance programs for light-water moderated nuclear power reactor vessels-. This program includes the installation of three irradiation capsules of similar materials to those of the reactor vessels, these samples are test tubes for mechanical practices of impact and tension. In the National Institute of Nuclear Research and due to the infrastructure as well as of the actual human resources of the Pilot Plant of Nuclear Fuel Assembles Production it was possible to realize the materials rebuilding extracted in 2005 of Unit 2 of nuclear power plant of Laguna Verde as well as the production, assemble and reassignment of the irradiation capsule made in 2006. At the present time the surveillance materials extracted in 2008 of Unit 1 of the nuclear power plant of Laguna Verde are reconstituting and the components are manufactured for the assembles of the irradiation capsule that will be reinstalled in the reactor vessel in 2010. The purpose of the present work is to describe the necessary components as well as its disposition during the assembles of the irradiation capsule for the surveillance program of the reactors vessel of the nuclear power plant of Laguna Verde. (Author)

Internal event analysis for Laguna Verde Unit 1 Nuclear Power Plant. Accident sequence quantification and results

International Nuclear Information System (INIS)

Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

1994-01-01

The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the I nternal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant, CNSNS-TR 004, in five volumes. The reports are organized as follows: CNSNS-TR 004 Volume 1: Introduction and Methodology. CNSNS-TR4 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR 004 Volume 3: System Analysis. CNSNS-TR 004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR 005 Volume 5: Appendices A, B and C. This volume presents the development of the dependent failure analysis, the treatment of the support system dependencies, the identification of the shared-components dependencies, and the treatment of the common cause failure. It is also presented the identification of the main human actions considered along with the possible recovery actions included. The development of the data base and the assumptions and limitations in the data base are also described in this volume. The accident sequences quantification process and the resolution of the core vulnerable sequences are presented. In this volume, the source and treatment of uncertainties associated with failure rates, component unavailabilities, initiating event frequencies, and human error probabilities are also presented. Finally, the main results and conclusions for the Internal Event Analysis for Laguna Verde Nuclear Power Plant are presented. The total core damage frequency calculated is 9.03x 10-5 per year for internal events. The most dominant accident sequences found are the transients involving the loss of offsite power, the station blackout accidents, and the anticipated transients without SCRAM (ATWS). (Author)

Participation of the ININ in the external radiological emergency plan of the Laguna Verde power plant; Participacion del ININ en el plan de emergencia radiologica externo de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Martinez S, R; Cervini L, A [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1991-07-01

The planning of performances in radiological emergencies, with the object of reducing the consequences as much as possible on the population to accidental liberations of radioactive material coming from Nuclear power plant, it has been of main interest in the nuclear community in the world. In Mexico it has not been the exception, since with the setting in march of the Laguna Verde nuclear power plant exists an executive program of planning for emergencies that it outlines the activities to follow trending to mitigate the consequences that are derived of this emergency. As integral part of this program this the External Plan of Radiological Emergency (PERE) that covers the emergencies that could leave the frontiers of the Laguna Verde power plant. In the PERE it settles down the planning, address and control of the preparation activities, response and recovery in emergencies, as well as the organization and coordination of the institutions that participate. The National Institute of Nuclear Research (ININ), like integral part of these institutions in the PERE, has an infrastructure that it allows to participate in the plan in a direct way in the activities of 'Control of the radiological exhibition the response personnel and control of water and foods' and of support way and consultant ship in the activities of 'Monitoring, Classification and decontamination of having evaluated' and 'Specialized medical radiological attention'. At the moment the ININ has a radiological mobile unit and this conditioning a second mobile unit to carry out part of the activities before mentioned; also accounts with 48 properly qualified people that directly intervene in the plan. In order to guarantee an adequate response in the PERE an organization it has been structured like that of the annex as for the personnel, transport, team, procedures and communication system, with the objective always of guaranteeing the security and the population's health in emergency situations in the

The continuous improvement system of nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Rivera C, A.

2009-10-01

This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

Internal event analysis for Laguna Verde Unit 1 Nuclear Power Plant. Accident sequence quantification and results; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Cuantificacion de secuencias de accidente y resultados

Energy Technology Data Exchange (ETDEWEB)

Huerta B, A; Aguilar T, O; Nunez C, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

1994-07-01

The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant, CNSNS-TR 004, in five volumes. The reports are organized as follows: CNSNS-TR 004 Volume 1: Introduction and Methodology. CNSNS-TR4 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR 004 Volume 3: System Analysis. CNSNS-TR 004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR 005 Volume 5: Appendices A, B and C. This volume presents the development of the dependent failure analysis, the treatment of the support system dependencies, the identification of the shared-components dependencies, and the treatment of the common cause failure. It is also presented the identification of the main human actions considered along with the possible recovery actions included. The development of the data base and the assumptions and limitations in the data base are also described in this volume. The accident sequences quantification process and the resolution of the core vulnerable sequences are presented. In this volume, the source and treatment of uncertainties associated with failure rates, component unavailabilities, initiating event frequencies, and human error probabilities are also presented. Finally, the main results and conclusions for the Internal Event Analysis for Laguna Verde Nuclear Power Plant are presented. The total core damage frequency calculated is 9.03x 10-5 per year for internal events. The most dominant accident sequences found are the transients involving the loss of offsite power, the station blackout accidents, and the anticipated transients without SCRAM (ATWS). (Author)

Simulation of overpressure events with a Laguna Verde model for the RELAP code to conditions of extended power up rate

International Nuclear Information System (INIS)

Rodriguez H, A.; Araiza M, E.; Fuentes M, L.; Ortiz V, J.

2012-10-01

In this work the main results of the simulation of overpressure events are presented using a model of the nuclear power plant of Laguna Verde developed for the RELAP/SCDAPSIM code. As starting point we have the conformation of a Laguna Verde model that represents a stationary state to similar conditions to the operation of the power station with Extended Power Up rate (EPU). The transitory of simulated pressure are compared with those documented in the Final Safety Analysis Report of Laguna Verde (FSAR). The results of the turbine shot transitory with and without by-pass of the main turbine are showed, and the event of closes of all the valves of main vapor isolation. A preliminary simulation was made and with base in the results some adjustments were made for the operation with EPU, taking into account the Operation Technical Specifications of the power station. The results of the final simulations were compared and analyzed with the content in the FSAR. The response of the power station to the transitory, reflected in the model for RELAP, was satisfactory. Finally, comments about the improvement of the model are included, for example, the response time of the protection and mitigation systems of the power station. (Author)

Validation of the thermal balance of Laguna Verde turbine under conditions of extended power increase; Validacion del balance termico de turbina de Laguna Verde en condiciones de aumento de potencia extendido

Energy Technology Data Exchange (ETDEWEB)

Castaneda G, M. A.; Cruz B, H. J.; Mercado V, J. J.; Cardenas J, J. B.; Garcia de la C, F. M., E-mail: miguel.castaneda01@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

2012-10-15

The present work is a continuation of the task: Modeling of the vapor cycle of Laguna Verde with the PEPSE code to conditions of thermal power licensed at present (2027 MWt) in which the modeling of the vapor cycle of the nuclear power plant of Laguna Verde was realized with PEPSE code (Performance Evaluation of Power System Efficiencies). Once reached the conditions of nominal operation of extended power increase, operating both units to 2371 MWt; after the tests phase of starting-up and operation is necessary to carry out a verification of the proposed design of the vapor cycle for the new operation conditions. All this, having in consideration that the vapor cycle designer only knows the detail of the prospective performance of the main turbine, for all the other components (for example pumps, heat inter changers, valves, reactor, humidity separators and re-heaters, condensers, etc.) makes generic suppositions based on engineering judgment. This way carries out the calculations of thermal balance to determine the guaranteed gross power. The purpose of the present work is to comment the detail of the validation carried out of the specific thermal balance (thermal kit) of the nuclear power plant, making use of the design characteristics of the different components that conform the vapor cycle. (Author)

Strategic planning 2007-2011, an opportunity for quality, competitiveness and excellence of the Laguna Verde Central; Planeacion estrategica 2007-2011, una oportunidad para la calidad, competitividad y excelencia de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Rivera C, A. [CFE, Central Laguna Verde, Kilometro 42.5 Cardel Nautla, Veracruz (Mexico)]. e-mail: arr99999@cfe.gob.mx

2007-07-01

The reason is to give to know to the nuclear community in Mexico the good results that it located in the 2006 to the Laguna Verde Nucleo electric Central in the classification of the World Association of Nuclear Operators (WANO) like one of the best in the worldwide scale, and their Strategic Plan 2007-2011 like an opportunity to continue improving the Quality, the Competitiveness and the Excellency in their Generating Units. It stands out that the fuel reloads are carried out in systemic form in less than 30 days, and also other achievements like it is the certificate granted by PROFEPA of Clean Industry, the renovation of the Certifications of the ISO-9001 and the ISO-14001, as well as the accredit of the Laboratories, and they will give data of the project of the increment of power that their power rose in 15%. For those results in the Strategic Planning 2007-2011 are pointed out that the Laguna Verde Central is a highly viable option in Mexico, when continuing with reloads that will allow a capacity factor up of 90%, and the other concepts that will give the obtaining of the qualification level 1 of WANO in this strategic period. Finally I will conclude with the good news for the Nuclear Industry in Mexico that published the Reforma newspaper at November 01, 2006: 'To the president of Mexico, Felipe Calderon, interests him to impel during his command the alternating energy sources to the hydrocarbons, known it is that the hydrocarbons (petroleum, coal or natural gas) they are finite, while the appetite of the world for the energy is infinite. As you they know, Mexico possesses a nuclear plant that generates energy starting from enriched uranium: the famous Laguna Verde Thermonuclear Central. He declared that Mexico can and it should advance for the one on the way to the energy generation for the nuclear road.' (Author)0.

New aspects in the radiological emergency plan outside the Nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Alva L, S.

1991-01-01

The Mexican government through the National Commission of Nuclear Safety and Safeguards has imposed to the Federal Commission of Electricity to fulfill the requirement of having a functional Emergency Plan and under the limits that the regulator organisms in the world have proposed. The PERE (Plan of External Radiological Emergency) it has been created for the Nuclear Power station of Laguna Verde, Mexico

SIMPRO, a practical tool for training the staff of Laguna Verde nuclear power plant; El SIMPRO, una herramienta practica para la capacitacion y entrenamiento del personal de la CNLV

Energy Technology Data Exchange (ETDEWEB)

Hernandez Valdez, Guillermo Omar; Gomez Camargo, Octavio; Castelo Cuevas, Luis; Vazquez Bustos, Jesus [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

2012-06-22

Laguna Verde Nuclear Power Plant (LVNPP) has implemented a real physical model, which represents several parts of a simplified version of its process. This development has proved to be very useful to improve the compliance with training programs and staff training maintenance in the different disciplines of engineering. Such programs are required by regulations and standards applicable for Nuclear Power Plants (NPP), so that the personnel working in these facilities can be able to respond on time to any contingency that might arise. This paper outlines the creation of the real physical model, how it is integrated and some of the practices that can be performed on this model. [Spanish] La Central Nucleoelectrica de Laguna Verde ha implementado un modelo fisico real que representa varias partes de una version simplificada de su proceso. Este desarrollo ha demostrado ser muy util para mejorar el cumplimiento de programas de adiestramiento, incluidos los del personal de mantenimiento, en diferentes disciplinas de ingenieria. Dichos programas son requeridos por las regulaciones y normas aplicables a las centrales nucleoelectricas, de manera que el personal que trabaja en estas instalaciones pueda ser capaz de responder oportunamente a cualquier contingencia que pudiera surgir. Este articulo describe la creacion del modelo fisico real, como se integra y algunas de las practicas que pueden llevarse a cabo con el.

A radiation monitoring system model for the Laguna Verde nuclear power training simulator

International Nuclear Information System (INIS)

Ocampo, M.H.; DeAlbornoz, B.A.

1988-01-01

A model for the Radiation Monitoring System of the Laguna Verde Boiling Water Reactor training simulator is presented. This model comprises enough definitions to assure interactions with the processes related, directly or indirectly, with the transport of radioisotopes. It is capable of following a dynamic behavior of the plant so an operator could be trained to become aware of nuclear radiation hazards. The model is composed of three parts: the electronics for the Process and Area Radiation Monitoring System; a lumped parameter transport model for the most representative radioisotopes; and the interactions with the modeled processes as well as with process not being simulated. The first part represents the radiation monitor controls in the vertical board panels of the nuclear station. The second part allows the carrying of nuclear isotopes between processes. The third part defines the way that the process interacts with the electronics at the point of release to environment or the point of detection. Each part of the model has been tested individually, and the transport model has been incorporated as a part of each process required to simulate nuclear radiation. The model parameters has been calculated using typical BWR nuclear radiation data, and Laguna Verde heat balance data at 100% design power. However, tunning will be necessary once the Simulator is integrated and tested. The tunning allows each detecting channel to behave as expected

Modernization of electric power systems of the Laguna Verde Nuclear Power Plant; Modernizacion de los sistemas electricos de potencia de la Central Nuclear de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Gabaldon, M. A.; Gonzalez, J. J.; Prieto, I.

2011-07-01

The Power Increase Project of Laguna Verde Nuclear Plant has entailed the replacement, in one unique outage, of the main power electrical systems of the Plant (Isolated Phase Bars, Generator Circuit Breaker and Main Transformer) as well as the replacement of the Turbo-group. The simultaneous substitution of these entire system has never been done by any other Plant in the world, representing an engineering challenge that embraced the design of the new equipment up to the planning, coordination and management of the construction and commissioning works, which were successfully carried out by Iberdrola within the established outage period /47 days) for both units. (Author)

Introduction of fuel GE14 in the nuclear power plant of Laguna Verde for the extended increase of power

International Nuclear Information System (INIS)

Hernandez M, N.; Vargas A, A. F.; Cardenas J, J. B.; Contreras C, P.

2008-01-01

The project of extended increase of power responds to a necessity of electrical energy in the country, increasing the thermal exit of the reactors of the nuclear power plant of Laguna Verde of 2027 MWt to 2317 MWt. In order to support this transition, changes will make in the configuration of the reactor core and in the operation strategies of the cycle, also they will take initiatives to optimize the economy in fuel cycle. At present in both reactors of the nuclear plant of Laguna Verde fuel GE12 is used. The fuel GE14 presents displays with respect to the GE12, some improvements in the mechanical design and consequently in its performance generally. Between these improvements we can mention: 1. Spacers of high performance. 2. Shielding with barrier. 3. Filter for sweepings d ebris a nd 4. Fuel rods of minor partial length. The management of nuclear power plants has decided to introduce the use of fuel GE14 in Laguna Verde in the reload 14 for Unit 1 and of the reload 10 for Unit 2. The process of new introduction fuel GE14 consists of two stages, first consists on subjecting the one new design of fuel to the regulator organism in the USA: Nuclear Regulatory Commission, in Mexico the design must be analyzed and authorized by the National Commission of Nuclear Safety and Safeguards, for its approval of generic form, by means of the demonstration of the fulfillment with the amendment 22 of GESTAR II, the second stage includes the specific analyses of plant to justify the use of the new fuel design in a reload core. The nuclear plant of Laguna Verde would use some of the results of the security analyses that have been realized for the project of extended increase of power with fuel GE14, to document the specific analyses of plant with the new fuel design. The result of the analyses indicates that the reload lots are increased of 116-120 assemblies in present conditions (2027 MWt) to 140-148 assemblies in conditions of extended increase of power (2317 MWt). (Author)

Modernization of the Electric Power Systems (transformers, rods and switches) in the Laguna Verde Nuclear Power Plant (Mexico)

International Nuclear Information System (INIS)

Gonzalez Solarzano, J. J.; Gabaldon Martin, M. A.; Pallisa Nunez, J.; Florez Ordeonez, A.; Fernandez Corbeira, A.; Prieto Diez, I.

2010-01-01

Description of the changes made in the Electric Power Systems as a part of the power increase project in the Laguna Verde Nuclear Power Plant (Mexico). The main electrical changes to make, besides the turbo group, are the main generation transformers, the isolated rods and the generation switch.

Technical assistance in relationship with the reloading analysis of the Laguna Verde Unit 2 reactor. Executive abstract

International Nuclear Information System (INIS)

Alonso V, G.; Castro B, M.; Gallegos E, R.; Hernandez L, H.; Montes T, J.L.; Ortiz S, J. J.; Perusquia C, R.

1993-11-01

The objective of the report was to carry out a comparative analysis of costs of energy generation among the designs GE9B of General Electric, 9X9-IX of SIEMENS and SVEA-96 of ABB ATOM, proposed to be used as recharge fuel in the Unit 2 of the Laguna Verde Nuclear Power station. (Author)

Validation of the thermal balance of Laguna Verde turbine under conditions of extended power increase

International Nuclear Information System (INIS)

Castaneda G, M. A.; Cruz B, H. J.; Mercado V, J. J.; Cardenas J, J. B.; Garcia de la C, F. M.

2012-10-01

The present work is a continuation of the task: Modeling of the vapor cycle of Laguna Verde with the PEPSE code to conditions of thermal power licensed at present (2027 MWt) in which the modeling of the vapor cycle of the nuclear power plant of Laguna Verde was realized with PEPSE code (Performance Evaluation of Power System Efficiencies). Once reached the conditions of nominal operation of extended power increase, operating both units to 2371 MWt; after the tests phase of starting-up and operation is necessary to carry out a verification of the proposed design of the vapor cycle for the new operation conditions. All this, having in consideration that the vapor cycle designer only knows the detail of the prospective performance of the main turbine, for all the other components (for example pumps, heat inter changers, valves, reactor, humidity separators and re-heaters, condensers, etc.) makes generic suppositions based on engineering judgment. This way carries out the calculations of thermal balance to determine the guaranteed gross power. The purpose of the present work is to comment the detail of the validation carried out of the specific thermal balance (thermal kit) of the nuclear power plant, making use of the design characteristics of the different components that conform the vapor cycle. (Author)

Multi-disciplinary organization for the completion and start-up of the Laguna Verde-2 power reactor

International Nuclear Information System (INIS)

1995-01-01

The optimization of the human and material resources for the pre-operational tests in the Laguna Verde-2 nuclear plant is described. About three thousand specialist of different groups were involved and each one had its own routines and functions with a complicated communication system among them. The optimization aimed at integrating and coordinating the organizational resources and defining the goals to be reached

15 years of production of electric energy of the Laguna Verde power plant, its plans and future; 15 anos de produccion de energia electrica de la Central Laguna Verde, sus planes y futuro

Energy Technology Data Exchange (ETDEWEB)

Rivera C, A [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

2005-07-01

In the year 2005 Laguna Verde power plant reaches 15 years of producing electric power in Mexico arriving to but of 100 million Megawatts-hour from their beginning of commercial activities. The Unit 1 that entered at July 29, 1990 and the Unit 2 at April 10, 1995, obtaining the Disposability Factors from their origin is: 84.63% in Unit 1 and 83.67% in Unit 2. The march of the X XI century gives big challenges of competition to the Laguna Verde Central, with the possible opening of the electric market to private investment, for their Goals and Objectives of a world class company, taking the evaluation system and qualification of the World Association of Nuclear Operators (WANO) that promotes the Excellence in the operation of the nuclear power stations in all their partners. This Association supports the development of programs that allow the monitoring of the behavior in Safety Culture, Human fulfilment, Equipment reliability, Industrial Safety, Planning, Programming and Control, Personalized Systematic Training, and the use of the Operational experience in the daily tasks. The present work tries to explain the system of evaluation/qualification of WANO, the definition of Goals and Objectives to reach the excellence and of the programs, it will present the Program of the Reliability of Equipment with its main actions the productivity. (Author)

30 years in the Veracruz state coast landscape: Laguna Verde nuclear power station. 1. ed.; 30 anos de paisaje costero veracruzano: Central Nucleoelectrica Laguan Verde

Energy Technology Data Exchange (ETDEWEB)

Guevara, S; Moreno Casasola, P; Castillo Campos, G; Dorantes, C; Gonzalez Garcia, F; Halffter, G; Isunza, E; Lot H, A; Mendoza, R; Paradowska, K; Priego, A; Sanchez Vigil, C; Vazquez, G [Comision Federal de Electricidad and Instituto Nacional de Ecologia A.C. (Mexico)

2008-07-01

36 years ago one of the most important power projects of Mexico was born; the design and construction of the Nuclear power station Laguna Verde. This project became reality thanks to the commitment of a group of Mexican professionals that gave the best of them for its accomplishment. At that time, there was not in Mexico a legislation that contemplated the environmental protection; nevertheless, the Mexican Constitution anticipates that when in the country there is not legislation for the development of a project, this must adopt the legislation of the country that is selling it. In the specific case of Laguna Verde, the legislation of the United States of America was adopted and in the environmental part it had to issue the first Manifest of Environmental impact, that was called Informe Ambiental para la Contruccion de Laguna Verde en el Estado de Veracruz. This study was performed by several national as well as foreign institutions. Among the most outstanding are the Universidad Nacional Autonoma de Mexico, the Intituto Politecnico Nacional, the Universidad Veracruzana, the Intituto National para la Investigacion de Recursos Biologicos, the Instituto de Ecologia, A.C. With this report, the engineers undertook the task of designing and constructing, the biologists and ecologists to realize the studies to mitigate the effects caused to the environment during the construction and later, during the operation of the Nuclear power station. After 18 years of commercial operation of the power station the present book is completed, in which the results obtained in 1972, when the studies of the environmental report began are compared against the ones obtained throughout this period. It is important to see in the results of the different studies and indicators presented/displayed in this book, that the important changes on the environment are due, to the change of the ground use and the over-exploitation of the natural resources as it happens in almost all the country. The

Modernization of the Electric Power Systems (transformers, rods and switches) in the Laguna Verde Nuclear Power Plant (Mexico); Modernizacion de los Sistemas Electricos de Potencia (Transformadores de Principales, Interruptor de Generacion, Barras de Fase Aislada) de la Central Nuclear de Laguna Verde (Mexico)

Energy Technology Data Exchange (ETDEWEB)

Gonzalez Solarzano, J. J.; Gabaldon Martin, M. A.; Pallisa Nunez, J.; Florez Ordeonez, A.; Fernandez Corbeira, A.; Prieto Diez, I.

2010-07-01

Description of the changes made in the Electric Power Systems as a part of the power increase project in the Laguna Verde Nuclear Power Plant (Mexico). The main electrical changes to make, besides the turbo group, are the main generation transformers, the isolated rods and the generation switch.

The National Institute of Nuclear Research (ININ) and its participation in the External Radiological Emergency Plans at Laguna Verde Power plant; El ININ y su participacion en el Plan de Emergencia Radiologica Externo de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Suarez, G. [Instituto Nacional de Investigaciones Nucleares, Departamento de Proteccion Radiologica, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

1998-07-01

In this article it is described the form in which the ININ participates in the External Radiological Emergency Plan at Laguna Verde Power plant. It is set the objective, mission and organization of this plan. The responsibilities and activities that plan has assigned are mentioned also the organization to fulfil them and the obtained results during 9 years of participation. (Author)

Strategic planning 2007-2011, an opportunity for quality, competitiveness and excellence of the Laguna Verde Central

International Nuclear Information System (INIS)

Rivera C, A.

2007-01-01

The reason is to give to know to the nuclear community in Mexico the good results that it located in the 2006 to the Laguna Verde Nucleo electric Central in the classification of the World Association of Nuclear Operators (WANO) like one of the best in the worldwide scale, and their Strategic Plan 2007-2011 like an opportunity to continue improving the Quality, the Competitiveness and the Excellency in their Generating Units. It stands out that the fuel reloads are carried out in systemic form in less than 30 days, and also other achievements like it is the certificate granted by PROFEPA of Clean Industry, the renovation of the Certifications of the ISO-9001 and the ISO-14001, as well as the accredit of the Laboratories, and they will give data of the project of the increment of power that their power rose in 15%. For those results in the Strategic Planning 2007-2011 are pointed out that the Laguna Verde Central is a highly viable option in Mexico, when continuing with reloads that will allow a capacity factor up of 90%, and the other concepts that will give the obtaining of the qualification level 1 of WANO in this strategic period. Finally I will conclude with the good news for the Nuclear Industry in Mexico that published the Reforma newspaper at November 01, 2006: 'To the president of Mexico, Felipe Calderon, interests him to impel during his command the alternating energy sources to the hydrocarbons, known it is that the hydrocarbons (petroleum, coal or natural gas) they are finite, while the appetite of the world for the energy is infinite. As you they know, Mexico possesses a nuclear plant that generates energy starting from enriched uranium: the famous Laguna Verde Thermonuclear Central. He declared that Mexico can and it should advance for the one on the way to the energy generation for the nuclear road.' (Author)

Participation of the ININ in the external radiological emergency plan of the Laguna Verde power plant

International Nuclear Information System (INIS)

Martinez S, R.; Cervini L, A.

1991-01-01

The planning of performances in radiological emergencies, with the object of reducing the consequences as much as possible on the population to accidental liberations of radioactive material coming from Nuclear power plant, it has been of main interest in the nuclear community in the world. In Mexico it has not been the exception, since with the setting in march of the Laguna Verde nuclear power plant exists an executive program of planning for emergencies that it outlines the activities to follow trending to mitigate the consequences that are derived of this emergency. As integral part of this program this the External Plan of Radiological Emergency (PERE) that covers the emergencies that could leave the frontiers of the Laguna Verde power plant. In the PERE it settles down the planning, address and control of the preparation activities, response and recovery in emergencies, as well as the organization and coordination of the institutions that participate. The National Institute of Nuclear Research (ININ), like integral part of these institutions in the PERE, has an infrastructure that it allows to participate in the plan in a direct way in the activities of 'Control of the radiological exhibition the response personnel and control of water and foods' and of support way and consultant ship in the activities of 'Monitoring, Classification and decontamination of having evaluated' and 'Specialized medical radiological attention'. At the moment the ININ has a radiological mobile unit and this conditioning a second mobile unit to carry out part of the activities before mentioned; also accounts with 48 properly qualified people that directly intervene in the plan. In order to guarantee an adequate response in the PERE an organization it has been structured like that of the annex as for the personnel, transport, team, procedures and communication system, with the objective always of guaranteeing the security and the population's health in emergency situations in the

Turbine model for the Laguna Verde nucleo electric central based in the RELAP code; Modelo de turbina para la Central nucleoelectrica de Laguna Verde basado en el codigo RELAP

Energy Technology Data Exchange (ETDEWEB)

Cortes M, F.S.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [Facultad de Ingenieria, Division de Estudios de Posgrado, Grupo de Ingenieria Nuclear, UNAM (Mexico)]. e-mail: cchavez2@cableonline.com.mx

2003-07-01

The Nuclear Power stations as Laguna Verde occupy at the present time a place every time but important as non pollutant alternative, economic and trusty to generate electricity. It is for it that the Group of Nuclear Engineering of the Engineering Faculty (GrlNFI) of the National Autonomous University of Mexico (UNAM) it develops investigation projects applied to Nuclear Centrals. One of the projects in process is the development of a Classroom simulator, which it can configures to consent to diverse models of nuclear systems with training purposes in normal operation, or, to consent to specialized nuclear codes for the analysis of transitory events and have a severe accident. This work describes the development, implementation and it proves of a simplified model of the Main turbine to be integrated to the group of models of the Classroom simulator. It is part of the current effort of GrlNFI guided to obtain a representation of all the dynamic models necessary to simulate the Plant Balance of the Laguna Verde Central. It is included the development of the unfolding graphic which represent the modeling of the Main turbine, and of the control interface that allows the user to manipulate in simple way, direct and interactive this device during the training or the analysis. With this work it is wanted to contribute to the training of new technicians and to support the operation personnel of the Centrals. Also, the developed infrastructure is guided to contribute in the design and analysis of new Nuclear Power stations with the contribution of new computational tools for the visualization, simulation and process control. (Author)

Modernization of electric power systems of the Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Gabaldon, M. A.; Gonzalez, J. J.; Prieto, I.

2011-01-01

The Power Increase Project of Laguna Verde Nuclear Plant has entailed the replacement, in one unique outage, of the main power electrical systems of the Plant (Isolated Phase Bars, Generator Circuit Breaker and Main Transformer) as well as the replacement of the Turbo-group. The simultaneous substitution of these entire system has never been done by any other Plant in the world, representing an engineering challenge that embraced the design of the new equipment up to the planning, coordination and management of the construction and commissioning works, which were successfully carried out by Iberdrola within the established outage period /47 days) for both units. (Author)

Estimation of fast neutron fluence in steel specimens type Laguna Verde in TRIGA Mark III reactor; Estimacion de la fluencia de neutrones rapidos en probetas de acero tipo Laguna Verde en el reactor Triga Mark III

Energy Technology Data Exchange (ETDEWEB)

Galicia A, J.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Aguilar H, F., E-mail: blink19871@hotmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

The main purpose of this work is to obtain the fluence of fast neutrons recorded within four specimens of carbon steel, similar to the material having the vessels of the BWR reactors of the nuclear power plant of Laguna Verde when subjected to neutron flux in a experimental facility of the TRIGA Mark III reactor, calculating an irradiation time to age the material so accelerated. For the calculation of the neutron flux in the specimens was used the Monte Carlo code MCNP5. In an initial stage, three sheets of natural molybdenum and molybdenum trioxide (MoO{sub 3}) were incorporated into a model developed of the TRIGA reactor operating at 1 M Wth, to calculate the resulting activity by setting a certain time of irradiation. The results obtained were compared with experimentally measured activities in these same materials to validate the calculated neutron flux in the model used. Subsequently, the fast neutron flux received by the steel specimens to incorporate them in the experimental facility E-16 of the reactor core model operating at nominal maximum power in steady-state was calculated, already from these calculations the irradiation time required was obtained for values of the neutron flux in the range of 10{sup 18} n/cm{sup 2}, which is estimated for the case of Laguna Verde after 32 years of effective operation at maximum power. (Author)

Laguna Verde after the extended power increase

International Nuclear Information System (INIS)

Herrera C, M. N.; Castaneda G, M. A.; Cardenas J, J. B.; Garcia de la C, F. M.

2012-10-01

The project of extended power increase that was implemented in both units of the nuclear power plant of Laguna Verde beginning with the stage feasibility evaluation in nuclear side of the facilities, that is to say the affectation of the power increase in the equipment s, systems and components of the nuclear power plant; besides the feasibility evaluation a study cost-benefit for the rehabilitated and modernization of the equipment s, systems and components of Plant Balance was realized. Once considered technical and economically feasible the project began the engineering evaluations required to carry out the licensing of the new operation conditions, as well as beginning to the elaboration of the technical specifications purchase of the equipment s, systems and components of the Plant Balance. While on one hand was carried out the administration of the licensing of the extended power increase for other was carried out the necessary engineering to make the physical changes in the conventional side of the nuclear power plant. Once concluded the constructive stage beginning the final stage of the project, the starting-up tests, operation and performance of the Units under the new operation conditions. This work describes this last stage that contains the technical base, the realized tests and the obtained results. (Author)

Estimation of fast neutron fluence in steel specimens type Laguna Verde in TRIGA Mark III reactor

International Nuclear Information System (INIS)

Galicia A, J.; Francois L, J. L.; Aguilar H, F.

2015-09-01

The main purpose of this work is to obtain the fluence of fast neutrons recorded within four specimens of carbon steel, similar to the material having the vessels of the BWR reactors of the nuclear power plant of Laguna Verde when subjected to neutron flux in a experimental facility of the TRIGA Mark III reactor, calculating an irradiation time to age the material so accelerated. For the calculation of the neutron flux in the specimens was used the Monte Carlo code MCNP5. In an initial stage, three sheets of natural molybdenum and molybdenum trioxide (MoO 3 ) were incorporated into a model developed of the TRIGA reactor operating at 1 M Wth, to calculate the resulting activity by setting a certain time of irradiation. The results obtained were compared with experimentally measured activities in these same materials to validate the calculated neutron flux in the model used. Subsequently, the fast neutron flux received by the steel specimens to incorporate them in the experimental facility E-16 of the reactor core model operating at nominal maximum power in steady-state was calculated, already from these calculations the irradiation time required was obtained for values of the neutron flux in the range of 10 18 n/cm 2 , which is estimated for the case of Laguna Verde after 32 years of effective operation at maximum power. (Author)

Radiological protection in Laguna Verde, the challenge of being better

International Nuclear Information System (INIS)

Serrano R, H.

2008-01-01

The operation of the nuclear power plants in the last decade is based on the application of standard directed towards the excellence. The nuclear power plant of Laguna Verde (CNLV), is not the exception and in the 18 years of commercial operation, the safety culture has matured in the personnel. Standard and political implemented like in the control of dosimeter alarms, equipment condition, meetings pre-work, the practice of protection to the systems and the fuel, as well as the order and the cleaning have distinguished to the CNLV with other power stations. The sense of property of the personnel towards its work is fundamental for the achievement of results. It is reason for the present work to show since it has been gotten to obtain results directed to the excellence in the activities or of normal operation and recharge, where the security is the principle priority. (Author)

Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station; Analisis de eventos internos para la Unidad 1 de la Central Nucleolelectrica de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

1993-07-01

This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

Application of six sigma to reloads design of the Laguna Verde Central with length until 17 days; Aplicacion de seis sigma para disenar recargas de la Central Laguna Verde con duracion hasta de 17 dias

Energy Technology Data Exchange (ETDEWEB)

Espinosa G, J.M. [Comision Federal de Electricidad, Central Laguna Verde, Subgerencia General de Operacion, Planeacion, Veracruz (Mexico)]. e-mail: mespinos@cfe.gob.mx

2007-07-01

The more important value in the Laguna Verde Central it is the safety. The international experience it confirms us that the more safe plants its are those more productive, this conclusion and reasoning indicate to the power station that we are in the correct road, improving the acting we will obtain that greater interest for us in the Laguna Verde Central (to increase the safety) and as added value to be able to be one of the best business for the Federal Commission of Electricity. With a future vision and commitment of high acting was integrated in an external place to all the area headquarters: (Maintenance, Planning, Operation, Parts of Reserve, Finances, Contracts, Supplies, Warehouse, design Engineering, place Engineering, engineering of systems, radiological Protection, etc.) to carry out a combined work with the unique challenge of drifting with the biggest level detail the program of a recharge and certainly to get ready to achieve their execution (all this without omitting any consideration for smaller or simpler than it seemed), looking for high quality in the works, with and bigger level of safety, with the minimum possible dose, the more reasonable cost and considering a new concept of human character, to achieve the above-mentioned without the participant personnel's stress, with the premise that a good plan and commitment of all the only one that it can bring us as result it is the success of the whole organization. (Author)

Quality assurance evolution at Laguna Verde Nuclear Power Plant Unit 1 and 2, regulatory aspects

International Nuclear Information System (INIS)

Leon Martinez, Cenobia

1996-01-01

Quality Assurance (QA) in Mexico started with the construction of the Laguna Verde Nuclear Power Plant. The Nuclear Regulatory Body, based in the adopted regulation, required the use of Quality Assurance in the design, construction and operation of the Plant. This paper describes the evolution of QA from its beginnings, through its developing phase up to this time, and shows the role of the Regulatory Body, which has participated actively in the implantation of QA in a properly manner, enforcing the utility in avoiding deviations and non-compliancies with the established regulation. (author)

Turbine model for the Laguna Verde nucleo electric central based in the RELAP code

International Nuclear Information System (INIS)

Cortes M, F.S.; Ramos P, J.C.; Salazar S, E.; Chavez M, C.

2003-01-01

The Nuclear Power stations as Laguna Verde occupy at the present time a place every time but important as non pollutant alternative, economic and trusty to generate electricity. It is for it that the Group of Nuclear Engineering of the Engineering Faculty (GrlNFI) of the National Autonomous University of Mexico (UNAM) it develops investigation projects applied to Nuclear Centrals. One of the projects in process is the development of a Classroom simulator, which it can configures to consent to diverse models of nuclear systems with training purposes in normal operation, or, to consent to specialized nuclear codes for the analysis of transitory events and have a severe accident. This work describes the development, implementation and it proves of a simplified model of the Main turbine to be integrated to the group of models of the Classroom simulator. It is part of the current effort of GrlNFI guided to obtain a representation of all the dynamic models necessary to simulate the Plant Balance of the Laguna Verde Central. It is included the development of the unfolding graphic which represent the modeling of the Main turbine, and of the control interface that allows the user to manipulate in simple way, direct and interactive this device during the training or the analysis. With this work it is wanted to contribute to the training of new technicians and to support the operation personnel of the Centrals. Also, the developed infrastructure is guided to contribute in the design and analysis of new Nuclear Power stations with the contribution of new computational tools for the visualization, simulation and process control. (Author)

15 years of production of electric energy of the Laguna Verde power plant, its plans and future

International Nuclear Information System (INIS)

Rivera C, A.

2005-01-01

In the year 2005 Laguna Verde power plant reaches 15 years of producing electric power in Mexico arriving to but of 100 million Megawatts-hour from their beginning of commercial activities. The Unit 1 that entered at July 29, 1990 and the Unit 2 at April 10, 1995, obtaining the Disposability Factors from their origin is: 84.63% in Unit 1 and 83.67% in Unit 2. The march of the X XI century gives big challenges of competition to the Laguna Verde Central, with the possible opening of the electric market to private investment, for their Goals and Objectives of a world class company, taking the evaluation system and qualification of the World Association of Nuclear Operators (WANO) that promotes the Excellence in the operation of the nuclear power stations in all their partners. This Association supports the development of programs that allow the monitoring of the behavior in Safety Culture, Human fulfilment, Equipment reliability, Industrial Safety, Planning, Programming and Control, Personalized Systematic Training, and the use of the Operational experience in the daily tasks. The present work tries to explain the system of evaluation/qualification of WANO, the definition of Goals and Objectives to reach the excellence and of the programs, it will present the Program of the Reliability of Equipment with its main actions the productivity. (Author)

Analysis of the stability of events occurred in Laguna Verde; Analisis de estabilidad de eventos ocurridos en Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Castillo D, R.; Ortiz V, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Calleros M, G. [CFE, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km. 42.5, Alto Lucero, Veracruz (Mexico)

2005-07-01

The new fuel designs for operation cycles more long have regions of uncertainty bigger that those of the old fuels, and therefore, they can have oscillations of power when an event is presented that causes that the reactor operates to high power and low flow of coolant. During the start up of the reactor there are continued procedures that avoid that oscillations are presented with that which makes sure the stable behavior of the reactor. However, when the reactor is operating to nominal conditions and they are shot or they are transferred to low speed the recirculation pumps, it cannot make sure that the reactor doesn't present oscillations of power when entering to the restricted operation regions. The methods of stability analysis commonly use signs of neutronic noise that require to be stationary, but after a transitory one where they commonly get lost the recirculation pumps the signs they don't have the required characteristics, for what they are used with certain level of uncertainty by the limited validity of the models. In this work the Prony method is used to determine the reactor stability, starting from signs of transitory and it is compared with autoregressive models. Four events are analyzed happened in the Laguna Verde power plant where the reactor was in the area of high power and low flow of coolant, giving satisfactory results. (Author)

Participation of the research institutes in the safety aspects of the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Sanchez G, J.

1991-01-01

The main activities undertaken by two research institutes of Mexico, the Instituto de Investigaciones Electricas and the Instituto Nacional de Investigaciones Nucleares, related to the safety of the Laguna Verde Nuclear Power Plant, are described. Among these activities, the development of a system for data acquisition and analysis during pre-operational tests, the design and construction of a full-scope simulator, the in-core fuel management and the establishment of an equipment qualification laboratory, stand out. It is considered that there exists a large potential for further participation. (author)

Reproduction of the flow-power map of the Laguna Verde power plant; Reproduccion del mapa flujo-potencia de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Amador G, R; Gonzalez M, V M [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

1993-07-01

The National Commission of Nuclear Safety and Safeguards (CNSNS) requires to have calculation tools which allows it to make analysis independent of the behavior of the reactor core of Laguna Verde nuclear power plant (CNLV) with the purpose to support the evaluation and discharge activities of the fuel recharges licensing. The software package Fms (Fuel Management System) allows to carry out an analysis of the core of the BWR type reactors along the operation cycle to detect possible anomalies and/or helping in the fuel management. In this work it is reproduced the flow-power for the CNLV using the Presto code of the Fms software package. The comparison of results with the map used by the operators of CNLV shows good agreement between them. Another exercise carried out was the changes study that the axial and radial power outlines undergo as well as the thermohydraulic parameters (LHGR, APLHGR, CPR) when moving a control rod. The obtained results show that is had the experience to effect analysis of the reactor behavior using the Presto-Fms code therefore the study of the rest of the software package for the obtention of nuclear parameters used in this code is recommended. (Author)

Improvements to the RELAP/SCDAPSIM of Laguna Verde model for the analysis of transients and accidents; Mejoras al modelo de Laguna Verde de RELAP/SCDAPSIM para el analisis de transitorios y accidentes

Energy Technology Data Exchange (ETDEWEB)

Amador G, R.; Castillo D, R.; Ortiz V, J.; Araiza M, E.; Martinez C, E., E-mail: rogelio.castillo@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2016-09-15

This work presents the improvements to the integral model of the nuclear power plant of Laguna Verde for the RELAP/SCDAPSIM code, for the simulation of transients and severe accidents. The model includes a new detailed geometry of the steam lines, as well as improvements in the performance of the emergency systems. A primary containment model has also been created, which will be used to analyze the effect of safety valve and relief valve discharges to the wet well suppression pool and the effect of the rupture of a recirculation loop on the dry well. The simulations performed with the new model show that the changes made improve the prediction of the phenomenology involved during transients and accidents. (Author)

Early alert system for oscillations detection applied to the Central of Laguna Verde

International Nuclear Information System (INIS)

Calleros M, G.; Zapata Y, M.; Avila N, A.; Herrera H, S. F.

2011-11-01

The code Early Alert System developed by Engineering of the Reactor of the nuclear power plant of Laguna Verde is presented, showing its reliability like preventive and corrective instrument to external interferences to the reactor core, due to equipment malfunction associated to the typical systems of a nuclear power plant, as those that control the reactor pressure, those that feed water to the reactor, those that control the valves of the main turbine. With this purpose, real cases of application of the System are shown where the results are compared with the independent evaluations carried out by the supplier, observing compatibility in both results. The benefits of the logarithm are discussed in the nuclear industry as soon as in non nuclear ambits. (Author)

Perspectives of the central Laguna Verde after Fukushima for the period 2012 at the 2015 in operation and maintenance; Perspectivas de la central Laguna Verde despues de Fukushima para el periodo 2012 al 2015 en operacion y mantenimiento

Energy Technology Data Exchange (ETDEWEB)

Rivera C, A., E-mail: arr99999@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)

2012-10-15

The Nuclear Power Plants Management of the Federal Commission of Electricity in Mexico by means an internal analysis confronts the threat to the nuclear industry of the event of Fukushima that affected the public opinion, and the emission of new regulations. This situation demands to improve the results of the operation and maintenance of the nuclear power plant of Laguna Verde, to contribute value with their excellence in the acting to the nuclear option in Mexico. The internal analysis defined with clarity the perspectives based on weaknesses and strengths of the operation (monitoring and control of on-line parameters), and in the maintenance (sustained by the planning), enriched with the external experiences emitted by the institutes INPO and WANO for the nuclear industry, with all this strategic objectives 2012 to 2015 were presented and the initiatives as the extension of the useful life to 20 years more, as well as the focused actions to diminish the threat that the event of Fukushima influenced negatively in the public opinion, by means the diffusion of the good results that can be obtained in the nuclear power plant of Laguna Verde between 2012 and 2015, taking advantage of its modernized power of 810 MW-hour for each generating unit, doing visible that the Project of Extended Power Increase is a generation reality of 120% of the original value, to be able to enter at the excellence levels of the nuclear world. (Author)

Stress corrosion evaluation on stainless steel 304 pipes in Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Arganis J, C.R.

1996-01-01

Inside the frame of the project IAEA/MEX-41044 'Stress corrosion as a starting event of accidents in nuclear plants', and of the institutional project IA-252 under the same name, it was required from the Laguna Verde Nuclear Plant, material equivalent to the one employed in the piping of the primary recycling system. Laguna Verde Nuclear Plant granted two tracks of tubes, that could be used to substitute the ones that are in operation, as is the tube SA-358TP304 CL-QC with transversal welding, designated as ER-316-LQA. According to the report entitles 'Revision of the operational experience related to corrosion in the nuclear plants' it was found that the stress corrosion is the principal mechanism of corrosion present in the nuclear plants. Previous records indicate that sensitized stainless steels are resistant to stress corrosion in testings of constant loading in sea water (3.5% of chlorides approximately) to 80 Centigrade and to 80% of the limit of conveyance and that a solution of 22% of NaCl to 90 Centigrade, produces cracking due to stress corrosion in highly sensitized steels, in tests of speed of slow extension (SSRT), to a speed of 1x10 -6 s -1 . Daniels reports that there is a direct relation between the speed limit of detection of the SSRT test and the concentration of chlorides, for stainless steels tested to 100 Centigrade. The minimum detection speed of susceptibility to stress corrosion for solution to 20% of NaCl, is of 1x10 -7 s -1 . Taking into account these considerations, the employment of a solution with 22% of NaCl to 90 Centigrade to a speed of 1x10 -6 s -1 seems a good choice for the evaluation of stainless steel. (Author)

The National Institute of Nuclear Research (ININ) and its participation in the External Radiological Emergency Plans at Laguna Verde Power plant

International Nuclear Information System (INIS)

Suarez, G.

1998-01-01

In this article it is described the form in which the ININ participates in the External Radiological Emergency Plan at Laguna Verde Power plant. It is set the objective, mission and organization of this plan. The responsibilities and activities that plan has assigned are mentioned also the organization to fulfil them and the obtained results during 9 years of participation. (Author)

Application of six sigma to reloads design of the Laguna Verde Central with length until 17 days

International Nuclear Information System (INIS)

Espinosa G, J.M.

2007-01-01

The more important value in the Laguna Verde Central it is the safety. The international experience it confirms us that the more safe plants its are those more productive, this conclusion and reasoning indicate to the power station that we are in the correct road, improving the acting we will obtain that greater interest for us in the Laguna Verde Central (to increase the safety) and as added value to be able to be one of the best business for the Federal Commission of Electricity. With a future vision and commitment of high acting was integrated in an external place to all the area headquarters: (Maintenance, Planning, Operation, Parts of Reserve, Finances, Contracts, Supplies, Warehouse, design Engineering, place Engineering, engineering of systems, radiological Protection, etc.) to carry out a combined work with the unique challenge of drifting with the biggest level detail the program of a recharge and certainly to get ready to achieve their execution (all this without omitting any consideration for smaller or simpler than it seemed), looking for high quality in the works, with and bigger level of safety, with the minimum possible dose, the more reasonable cost and considering a new concept of human character, to achieve the above-mentioned without the participant personnel's stress, with the premise that a good plan and commitment of all the only one that it can bring us as result it is the success of the whole organization. (Author)

Current situation of spent fuel management in the Laguna Verde Nuclear Power Plant, Veracruz, Mexico

International Nuclear Information System (INIS)

Moreno, C.V.

1994-01-01

The Comision Federal de Electricidad (CFE), owner and operator of the Laguna Verde nuclear power plant (2 x 654 MWe BWR), has twice decided to increase the storage capacity of the spent fuel pools of the reactors. The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS), the national nuclear regulatory authority, approved the increase by a factor of 2.66 in the storage capacity proposal by CFE in 1989. Each reactor spent fuel pool can now hold 614 t HM. The reracking was done at a cost of about US $13 per kg U, which will add only 0.042 mills per kWh to the fuel cycle cost. (author)

Estimating of seismic return periods in Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Flores R, J.H.

1993-01-01

The study of seismic risk in the site of Laguna Verde Nuclear Power Plant and surroundings was made considering the different periods of seismic return and the probability of occurrence in distinct time intervals (50, 75, 100, 125, 150 years) starting with the distribution of first type of extreme values of Gumbel (G1), the value used for the assessment of lifetime of lump was 50 years, and the rest of the periods are used to evaluate temporary nuclear cemeteries, it is to say for reducing the radioactivity of burned fuel assemblies. The seismic data belongs to the seismicity catalog (1920-1982) elaborated around the site, which average magnitude was 5 in the Richter Scale and are considered as shallow and are located in the Continental crust of North American shelf, and are induced by the pressure of the cocos shelf, being 36 % of the seismic movements of intermediate value and two seismic movements of deep value. (Author)

Calculating of radiation doses in rutinary unloads of liquid wastes from Laguna Verde nuclear power plant.; Calculo de las dosis de radiacion debidas a las descargas rutinarias de desechos liquidos de la central nucleoelectrica de Laguna Verde.

Energy Technology Data Exchange (ETDEWEB)

Molina, G

1986-12-31

Utilization of nuclear energy to generate electricity is increasingly being used to replace fossil fuels. During operation of nuclear power plants, radioactive materials are produced, a small fraction of which are released to environment as liquid or gaseous effluents. Estimation of radiation doses caused by effluents release has three purposes. During design phase of a nuclear station it is useful to adapt the wastes treatment systems to acceptable limits. During licensing phase, the regulator organism verifies the design of nuclear station effectuating estimation of doses. Finally, during operation, before every unload of radioactive effluents, radiation doses should be evaluated in order to fulfill technical specifications limiting the release of radioactive materials to environment. 1. To perform calculations of individual doses due to liquid radioactive effluents unload in units 1 and 2 of Laguna Verde nuclear power plant (In licensing phase). 2. To perform a parametric study of the effect of unload recirculation over individual dose, since recirculation has two principal effects: thermodynamical effects in nuclear station and radioactivity concentration; the last can affect the fullfilment of dose limits. 3. To perform the calculation of collective doses causes by unloads of liquid effluents within a radius of 80 km of the plant caused by unload of liquid radioactive effluents during normal operation and does not include doses during accident conditions. In Mexico the organism in charge of regulation of peaceful uses of nuclear energy is Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) and for Laguna Verde licensing, the regulations of the country who manufactured the reactor (USA). In Appendix C, units are explained.

New recommendations of the ICRP and the ALARA program of the Nuclear power plant of Laguna Verde; Nuevas recomendaciones del ICRP y el programa ALARA de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Padilla C, I [Comision Federal de Electricidad, Central Laguna Verde (Mexico)

1991-07-01

In view of the events happened in it finishes it decade, in the nuclear environment, it is necessary that any he/she practices that it involves exhibition to the radiation, real or potential, be detailed and systematically analyzed by the light of the current knowledge, capitalizing the generated experience. They think about three fundamental aspects in the campaign of radiological cultivation: 1. New methods of evaluation of equivalent dose. 2. Limit of individual dose, base of the change and control implications, and 3. Analysis philosophies and the application of the system of dose limitation. The program ALARA of the Laguna Verde Central from its installation in 1987 observes and it implements actions trending to optimize it practice of situation of potential and planned exhibition with the purpose of fulfilling the commitment settled down in the declaration of political of this program.

Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station

International Nuclear Information System (INIS)

Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R.

1993-01-01

This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

Thermal limits validation of gamma thermometer power adaption in CFE Laguna Verde 2 reactor core

Energy Technology Data Exchange (ETDEWEB)

Cuevas V, G.; Banfield, J. [GE-Hitachi Nuclear Energy Americas LLC, Global Nuclear Fuel, Americas LLC, 3901 Castle Hayne Road, Wilmingtonm, North Carolina (United States); Avila N, A., E-mail: Gabriel.Cuevas-Vivas@ge.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

2016-09-15

This paper presents the status of GEH work on Gamma Thermometer (GT) validation using the signals of the instruments installed in the Laguna Verde Unit 2 reactor core. The long-standing technical collaboration between Comision Federal de Electricidad (CFE), Global Nuclear Fuel - Americas LLC (GNF) and GE-Hitachi Nuclear Energy Americas LLC (GEH) is moving forward with solid steps to a final implementation of GTs in a nuclear reactor core. Each GT is integrated into a slightly modified Local Power Range Monitor (LPRM) assembly. Six instrumentation strings are equipped with two gamma field detectors for a total of twenty-four bundles whose calculated powers are adapted to the instrumentation readings in addition to their use as calibration instruments for LPRMs. Since November 2007, the six GT instrumentation strings have been operable with almost no degradation by the strong neutron and gamma fluxes in the Laguna Verde Unit 2 reactor core. In this paper, the thermal limits, Critical Power Ratio (CPR) and maximum Linear Heat Generation Rate (LHGR), of bundles directly monitored by either Traverse In-core Probes (TIPs) or GTs are used to establish validation results that confirm the viability of TIP system replacement with automatic fixed in-core probes (AFIPs, GTs, in a Boiling Water Reactor. The new GNF steady-state reactor core simulator AETNA02 is used to obtain power and exposure distribution. Using this code with an updated methodology for GT power adaption, a reduced value of the GT interpolation uncertainty is obtained that is fed into the LHGR calculation. This new method achieves margin recovery for the adapted thermal limits for use in the Economic Simplified Boiling Water Reactor (ESBWR) or any other BWR in the future that employs a GT based AFIP system for local power measurements. (Author)

Thermal limits validation of gamma thermometer power adaption in CFE Laguna Verde 2 reactor core

International Nuclear Information System (INIS)

Cuevas V, G.; Banfield, J.; Avila N, A.

2016-09-01

This paper presents the status of GEH work on Gamma Thermometer (GT) validation using the signals of the instruments installed in the Laguna Verde Unit 2 reactor core. The long-standing technical collaboration between Comision Federal de Electricidad (CFE), Global Nuclear Fuel - Americas LLC (GNF) and GE-Hitachi Nuclear Energy Americas LLC (GEH) is moving forward with solid steps to a final implementation of GTs in a nuclear reactor core. Each GT is integrated into a slightly modified Local Power Range Monitor (LPRM) assembly. Six instrumentation strings are equipped with two gamma field detectors for a total of twenty-four bundles whose calculated powers are adapted to the instrumentation readings in addition to their use as calibration instruments for LPRMs. Since November 2007, the six GT instrumentation strings have been operable with almost no degradation by the strong neutron and gamma fluxes in the Laguna Verde Unit 2 reactor core. In this paper, the thermal limits, Critical Power Ratio (CPR) and maximum Linear Heat Generation Rate (LHGR), of bundles directly monitored by either Traverse In-core Probes (TIPs) or GTs are used to establish validation results that confirm the viability of TIP system replacement with automatic fixed in-core probes (AFIPs, GTs, in a Boiling Water Reactor. The new GNF steady-state reactor core simulator AETNA02 is used to obtain power and exposure distribution. Using this code with an updated methodology for GT power adaption, a reduced value of the GT interpolation uncertainty is obtained that is fed into the LHGR calculation. This new method achieves margin recovery for the adapted thermal limits for use in the Economic Simplified Boiling Water Reactor (ESBWR) or any other BWR in the future that employs a GT based AFIP system for local power measurements. (Author)

Economic analysis of extended cycles in the Laguna Verde nuclear power plant; Analisis economico de ciclos de extendidos en la Central Nucleoelectrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Hernandez N, H.; Hernandez M, J.L.; Francois L, J.L. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: hermilo@correo.unam.mx

2004-07-01

The present work presents a preliminary analysis of economic type of extended cycles of operation of the Unit One in the Laguna Verde nuclear power plant. It is analysed an equilibrium cycle of 18 months firstly, with base to the Plan of Use of Energy of the Federal Commission of Electricity, being evaluated the cost of the energy until the end of the useful life of the plant. Later on an alternative recharge scenario is presented with base to an equilibrium cycle of 24 months, implemented to the beginning of the cycle 11, without considering transition cycles. It is added in both cycles the cost of the substitution energy, considering the unitary cost of the fuel of a dual thermoelectric power station of 350 M We and evaluating in each operation cycle, in both scenarios, the value of the substitution energy. The results show that a reduction of the days of recharge in the cycle of 24 months could make this option but favorable economically. The duration of the period of recharge rebounds in considerable grade in the cost of energy generation for concept of fuel. (Author)

Development of an interactive model of the Laguna Verde nuclear power plant based on the RELAP/SCDAP code; Desarrollo del modelo interactivo de la central nucleoelectrica de Laguna Verde basado en el codigo RELAP/SCDAP

Energy Technology Data Exchange (ETDEWEB)

Salazar C, J.H.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [LAIRN, FI-UNAM, DEPFI Campus Morelos, Jiutepec, Morelos (Mexico)]. e-mail: cchavez2@cableonline.com.mx

2003-07-01

The present work describes the development of an interactive model of the Nuclear power plant of Laguna Verde (CNLV) based on the RELAP/SCDAP nuclear code, and it incorporation to a classroom simulator. The functional prototype it allows to make evaluations for operational transients and postulates accidents, with capacitation purposes, training, analysis and design. It emphasizes on the methodology used to establish the inter activity. Such methodology, is based on a modular structure in the one that multiple processes can be executed in an independent way and where the generated information is stored in segments of shared memory (characteristic that allows the UNIX operating system) and sent to the different processes by means of communication routines developed in C programming language. The utility of the system is demonstrated by means of the use of interactive display graphics (mimic diagrams, pictorials and tendency graphics) for the simultaneous dynamic visualization of the variables more significant that involve to the pattern of a transitory event type (for example failure of the controller of feeding water in a BWR reactor). Near with the interactive module, it was developed a model of the reactor of the CNLV for the code of better estimation RELAP/SCDAP. Finally the evaluation of the model is described, where it is interpreted in general form the behavior of those main variables that describe the stationary state, corroborating that follow the same tendency that those reported in the FSAR (Final Safety Analysis Report) of the Laguna Verde plant. The obtained results allow to conclude that the made development was satisfactory and that it presents enormous advantages regarding the capacity and time of analysis when using tools of visualization in real time of execution. (Author)

To report the obtained results in the simulation with the FCS-11 and Presto codes of the two first operation cycles of the Laguna Verde Unit 1 reactor; Reportar los resultados obtenidos en la simulacion con los codigos FCS-11 y PRESTO de los dos primeros ciclos de operacion del reactor Laguna Verde Unidad 1

Energy Technology Data Exchange (ETDEWEB)

Montes T, J.L.; Moran L, J.M.; Cortes C, C.C

1990-08-15

The objective of this work is to establish a preliminary methodology to carry out analysis of recharges for the reactor of the Laguna Verde U-1, by means of the evaluation of the state of the reactor core in its first two operation cycles using the FCS2 and Presto-B codes. (Author)

Rehabilitation and modernization project of units 1 and 2 of Laguna Verde Nuclear Power Plant. A strengthening project to 120%. (2nd phase)

International Nuclear Information System (INIS)

Liebana, B.; Merino, A.; Garcia, J. L.; Gomez, M.; Martinez, I.; Ruiz, L.

2010-01-01

The power increase of the Laguna Verde Nuclear Power Plant is a project for the rehabilitation and modernization of the turbo and associated equipment to get an increase of its power and of its service life. The project scope includes the design, the engineering, the equipment supply, the installation, the testing and the commissioning. This article presents the work of the second phase.

Upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Llado Castillo, R.; Aguilar Pacheco, R.

1998-01-01

The work shows the results obtained in the upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

Perspectives of the central Laguna Verde after Fukushima for the period 2012 at the 2015 in operation and maintenance

International Nuclear Information System (INIS)

Rivera C, A.

2012-10-01

The Nuclear Power Plants Management of the Federal Commission of Electricity in Mexico by means an internal analysis confronts the threat to the nuclear industry of the event of Fukushima that affected the public opinion, and the emission of new regulations. This situation demands to improve the results of the operation and maintenance of the nuclear power plant of Laguna Verde, to contribute value with their excellence in the acting to the nuclear option in Mexico. The internal analysis defined with clarity the perspectives based on weaknesses and strengths of the operation (monitoring and control of on-line parameters), and in the maintenance (sustained by the planning), enriched with the external experiences emitted by the institutes INPO and WANO for the nuclear industry, with all this strategic objectives 2012 to 2015 were presented and the initiatives as the extension of the useful life to 20 years more, as well as the focused actions to diminish the threat that the event of Fukushima influenced negatively in the public opinion, by means the diffusion of the good results that can be obtained in the nuclear power plant of Laguna Verde between 2012 and 2015, taking advantage of its modernized power of 810 MW-hour for each generating unit, doing visible that the Project of Extended Power Increase is a generation reality of 120% of the original value, to be able to enter at the excellence levels of the nuclear world. (Author)

Validation of a new software version for monitoring of the core of the Unit 2 of the Laguna Verde power plant with ARTS; Validacion de una nueva version del software para monitoreo del nucleo de la Unidad 2 de la Central Laguna Verde con ARTS

Energy Technology Data Exchange (ETDEWEB)

Calleros, G.; Riestra, M.; Ibanez, C.; Lopez, X.; Vargas, A.; Mendez, A.; Gomez, R. [CFE, Central Nucleoelectrica de Laguna Verde, Alto Lucero, Veracruz (Mexico)]. e-mail: gcm9acpp@cfe.gob.mx

2005-07-01

In this work it is intended a methodology to validate a new version of the software used for monitoring the reactor core, which requires of the evaluation of the thermal limits settled down in the Operation Technical Specifications, for the Unit 2 of Laguna Verde with ARTS (improvements to the APRMs, Rod Block Monitor and Technical specifications). According to the proposed methodology, those are shown differences found in the thermal limits determined with the new versions and previous of the core monitoring software. Author)

Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995; Informe de la Cuarta Recarga de Combustible. Central Laguna Verde. Unidad 1. Abril-Mayo 1995

Energy Technology Data Exchange (ETDEWEB)

Mendoza L, A; Flores C, E; Lopez G, C P.F.

1996-12-31

The fourth refueling of the Unit 1 of Laguna Verde Nuclear Central was executed in the period of April 17 to May 31 of 1995 with the participation of a task group of 358 persons, included technicians and radiation protection officials and auxiliaries.The radiation monitoring and radiological surveillance to the workers was present length ways the refueling process and always attached to the ALARA criteria. The check points for radiation levels were set at: primary container or dry well, reloading floor, decontamination room (level 10.5), turbine building and radioactive waste building. To take advantage of the refueling process, rooms 203 and 213 of the turbine buildings were subject to inspection and maintenance work in valves, heaters and drains of heaters. Management aspects as personnel selection and training, costs, and countable are also presented in this report. Owing to the high cost of man-hour of the members of the ININ staff, its participation in the refueling process was in smaller number than years before. (Author).

Participation of the ININ in the activities of radioactive waste management of the Laguna Verde Central; Participacion del ININ en las actividades de gestion de desechos radiactivos de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Medrano L, M.; Rodriguez C, C.; Linares R, D. [ININ, Gerencia Subsede Sureste (Mexico); Ramirez G, R.; Zarate M, N. [Central Laguna Verde, CFE (Mexico)]. e-mail: maam@nuclear.inin.mx

2006-07-01

From the beginning of the operation of the Laguna Verde Central (CLV) the National Institute of Nuclear Research (ININ) has come supporting the CLV in the activities of administration of the humid and dry radioactive waste generated by the operation of the two units of the CLV, from the elaboration of procedures to the temporary storage in site, the implementation of a program of minimization and segregation of dry solid wastes, until the classification of the lots of humid waste and bulk dry wastes. In this work the description of the management activities of radioactive wastes carried out by the ININ in the facilities of the CLV to the date is presented, as well as some actions that they are had drifted in the future near, among those that it stands out the determination of the total alpha activity in humid samples by means of scintillation analysis. (Author)

Estimation of seismic return periods in the Laguna Verde nuclear plant

International Nuclear Information System (INIS)

Flores R, J.H.

1992-01-01

The study of seismic risk in the area of the Laguna Verde Nucleo electric plant (PNLV) and its surroundings, one carries out estimating the different return periods and the occurrence probability in different intervals of time (5, 75, 100, 125, 150 years starting from the distribution of first type of Gumbel (G1) of extreme values (Burton, 1986), the value that was used to evaluate the useful life of the PNLV was of 50 years, the other periods will be occupy to evaluate 'temporal' nuclear cemeteries, that is to say for diminish the radioactive activity of the fuel assemblies already burned in the reactor pool or in a near place to the place. The seismic data that were used for the analysis were of the seismic catalog that it was elaborated from (1920-1982), around the place whose seismic half magnitude was of 5 grades Richter and a depth 65 km, these earthquakes are classified as shallow earthquakes, which are located in the continental plaque of North-America, these they are induced by the efforts of push of the plaque of Cocos, existing 36% of intermediate and 2 of deep earthquakes. (Author)

Proposal of the visual inspection of the integrity of the storage cells of spent fuel from the nuclear power plant of Laguna Verde; Propuesta para la inspeccion visual de la integridad de las celdas de almacenamiento de combustible gastado de la Central Laguna Verde (CLV)

Energy Technology Data Exchange (ETDEWEB)

Gonzalez M, J. L.; Rivero G, T.; Merino C, F. J. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Santander C, L. E., E-mail: francisco.merino@inin.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Veracruz-Medellin Km 7.5, Col. Dos Bocas, 94271 Medellin, Veracruz (Mexico)

2015-09-15

As part of the evaluation of the structural integrity of the components of nuclear plants, particularly those applying for life extension is necessary to carry out inspections and nondestructive testing to determine the state meet. In many cases these activities are carried out in areas with high levels of radiation and contamination difficult to access, so that are required to use equipment or robotic systems operated remotely. Among others, the frames and cells of the storage pools for spent fuel are structures subject to a program of tests and inspections, and become relevant because the nuclear power plant of Laguna Verde (NPP-LV) is processing the license to extend the operational life of its reactors. Of non-destructive testing can be used to verify the physical condition of the frames and storage cells, is the remote visual inspection which is a test that allows determine the physical integrity of the components by one or more video cameras designed to applications in underwater environments with radiation, and are used to identify and locate adverse conditions such as ampoules, protuberances, pitting, cracks, stains or buckling, which could affect the three main functions for which the store components are designed: to maintain the physical integrity of spent fuels, store them properly guaranteeing their free insertion and removal, and ensure that the store as a whole meets the criticality criteria that k{sub eff} is less than 0.95 throughout the life of the plant. This paper describes a proposal to carry out the visual inspection of the storage cells of spent fuel from the NPP-LV using a probe including one or more video cameras along with your recorder, and its corresponding control program. It is noted that due to the obtained results, the nuclear power plant personnel can make decisions regarding remedial actions or applying complementary methods to verify that the cells and frames have not lost their physical integrity, or in particular that the cover

Development of tools to manage the operational monitoring and pre-design of the NPP-LV cycle

International Nuclear Information System (INIS)

Perusquia, R.; Arredondo S, C.; Hernandez M, J. L.; Montes T, J. L.; Castillo M, A.; Ortiz S, J. J.

2015-09-01

This paper presents the development of tools to facilitate the management so much, the operational monitoring of boiling water reactors (BWR) of the nuclear power plant of Laguna Verde (NPP-LV) through independent codes, and how to carry out the static calculations corresponding to process of optimized pre-design of the reference cycle next to current cycle. The progress and preliminary results obtained with the program SACal, developed at Instituto Nacional de Investigaciones Nucleares (ININ), central tool to achieve provide a management platform of the operational monitoring and pre-design of NPP-LV cycle are also described. The reached preliminary advances directed to get an Analysis center and automated design of fuel assembly cells are also presented, which together with centers or similar modules related with the fuel reloads form the key part to meet the targets set for the realization of a Management Platform of Nuclear Fuel of the NPP-LV. (Author)

To report the obtained results in the simulation with the FCS-11 and Presto codes of the two first operation cycles of the Laguna Verde Unit 1 reactor

International Nuclear Information System (INIS)

Montes T, J.L.; Moran L, J.M.; Cortes C, C.C.

1990-08-01

The objective of this work is to establish a preliminary methodology to carry out analysis of recharges for the reactor of the Laguna Verde U-1, by means of the evaluation of the state of the reactor core in its first two operation cycles using the FCS2 and Presto-B codes. (Author)

Validation of a new version of software for monitoring the core of nuclear power plant of Laguna Verde Unit 2, at the end of Cycle 10; Validacion de una nueva version del software para monitoreo del nucleo de la Central Laguna Verde Unidad 2, al final del Ciclo 10

Energy Technology Data Exchange (ETDEWEB)

Hernandez, G.; Calleros, G.; Mata, F. [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)], e-mail: gabriel.hernandez05@cfe.gob.mx

2009-10-15

This work shows the differences observed in thermal limits established in the technical specifications of operation, among the new software, installed at the end of Cycle 10 of Unit 2 of nuclear power plant of Laguna Verde, and the old software that was installed from the beginning of the cycle. The methodology allowed to validate the new software during the coast down stage, before finishing the cycle, for what could be used as tool during the shutdown of Unit 2 at the end of Cycle 10. (Author)

Analysis of the stability of events occurred in Laguna Verde

International Nuclear Information System (INIS)

Castillo D, R.; Ortiz V, J.; Calleros M, G.

2005-01-01

The new fuel designs for operation cycles more long have regions of uncertainty bigger that those of the old fuels, and therefore, they can have oscillations of power when an event is presented that causes that the reactor operates to high power and low flow of coolant. During the start up of the reactor there are continued procedures that avoid that oscillations are presented with that which makes sure the stable behavior of the reactor. However, when the reactor is operating to nominal conditions and they are shot or they are transferred to low speed the recirculation pumps, it cannot make sure that the reactor doesn't present oscillations of power when entering to the restricted operation regions. The methods of stability analysis commonly use signs of neutronic noise that require to be stationary, but after a transitory one where they commonly get lost the recirculation pumps the signs they don't have the required characteristics, for what they are used with certain level of uncertainty by the limited validity of the models. In this work the Prony method is used to determine the reactor stability, starting from signs of transitory and it is compared with autoregressive models. Four events are analyzed happened in the Laguna Verde power plant where the reactor was in the area of high power and low flow of coolant, giving satisfactory results. (Author)

Development of an interactive model of the Laguna Verde nuclear power plant based on the RELAP/SCDAP code

International Nuclear Information System (INIS)

Salazar C, J.H.; Ramos P, J.C.; Salazar S, E.; Chavez M, C.

2003-01-01

The present work describes the development of an interactive model of the Nuclear power plant of Laguna Verde (CNLV) based on the RELAP/SCDAP nuclear code, and it incorporation to a classroom simulator. The functional prototype it allows to make evaluations for operational transients and postulates accidents, with capacitation purposes, training, analysis and design. It emphasizes on the methodology used to establish the inter activity. Such methodology, is based on a modular structure in the one that multiple processes can be executed in an independent way and where the generated information is stored in segments of shared memory (characteristic that allows the UNIX operating system) and sent to the different processes by means of communication routines developed in C programming language. The utility of the system is demonstrated by means of the use of interactive display graphics (mimic diagrams, pictorials and tendency graphics) for the simultaneous dynamic visualization of the variables more significant that involve to the pattern of a transitory event type (for example failure of the controller of feeding water in a BWR reactor). Near with the interactive module, it was developed a model of the reactor of the CNLV for the code of better estimation RELAP/SCDAP. Finally the evaluation of the model is described, where it is interpreted in general form the behavior of those main variables that describe the stationary state, corroborating that follow the same tendency that those reported in the FSAR (Final Safety Analysis Report) of the Laguna Verde plant. The obtained results allow to conclude that the made development was satisfactory and that it presents enormous advantages regarding the capacity and time of analysis when using tools of visualization in real time of execution. (Author)

Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant

International Nuclear Information System (INIS)

Zamora R, L.; Medina F, A.

1999-01-01

The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

Reproduction of the flow-power map of the Laguna Verde power plant

International Nuclear Information System (INIS)

Amador G, R.; Gonzalez M, V.M.

1993-01-01

The National Commission of Nuclear Safety and Safeguards (CNSNS) requires to have calculation tools which allows it to make analysis independent of the behavior of the reactor core of Laguna Verde nuclear power plant (CNLV) with the purpose to support the evaluation and discharge activities of the fuel recharges licensing. The software package Fms (Fuel Management System) allows to carry out an analysis of the core of the BWR type reactors along the operation cycle to detect possible anomalies and/or helping in the fuel management. In this work it is reproduced the flow-power for the CNLV using the Presto code of the Fms software package. The comparison of results with the map used by the operators of CNLV shows good agreement between them. Another exercise carried out was the changes study that the axial and radial power outlines undergo as well as the thermohydraulic parameters (LHGR, APLHGR, CPR) when moving a control rod. The obtained results show that is had the experience to effect analysis of the reactor behavior using the Presto-Fms code therefore the study of the rest of the software package for the obtention of nuclear parameters used in this code is recommended. (Author)

Economic analysis of extended cycles in the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Hernandez N, H.; Hernandez M, J.L.; Francois L, J.L.

2004-01-01

The present work presents a preliminary analysis of economic type of extended cycles of operation of the Unit One in the Laguna Verde nuclear power plant. It is analysed an equilibrium cycle of 18 months firstly, with base to the Plan of Use of Energy of the Federal Commission of Electricity, being evaluated the cost of the energy until the end of the useful life of the plant. Later on an alternative recharge scenario is presented with base to an equilibrium cycle of 24 months, implemented to the beginning of the cycle 11, without considering transition cycles. It is added in both cycles the cost of the substitution energy, considering the unitary cost of the fuel of a dual thermoelectric power station of 350 M We and evaluating in each operation cycle, in both scenarios, the value of the substitution energy. The results show that a reduction of the days of recharge in the cycle of 24 months could make this option but favorable economically. The duration of the period of recharge rebounds in considerable grade in the cost of energy generation for concept of fuel. (Author)

Estimation of requirements of eolic energy equivalent to the electric generation of the Laguna Verde nuclear power plant; Estimacion de requerimientos de energia eolica equivalente a la generacion electrica de la Central Nucleoelectrica de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Garcia V, M.A.; Hernandez M, I.A. [Facultad de Ingenieria, Division de Ingenieria Electrica, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: maiki27@yahoo.com; Martin del Campo M, C. [Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

2004-07-01

The advantages are presented that have the nuclear and eolic energy as for their low environmental impact and to the human health. An exercise is presented in the one that is supposed that the electric power generated by the Laguna Verde Nuclear Power plant (CNLV), with capacity of 1365 M W, it should be produced by eolic energy when in the years 2020 and 2025 the units 1 and 2 of the CNLV reach its useful life and be moved away. It is calculated the number of aero generators that would produce the electric power average yearly of the CNLV, that which is equal to install eolic parks with capacity of 2758 M W, without considering that it will also be invested in systems of back generation to produce electricity when the aero generators stops for lack of wind. (Author)

Applications of the monitor of loose parts in the cycle 6 of the Laguna Verde Unit 2 power plant; Aplicaciones del monitor de partes sueltas en el ciclo 6 de la Unidad 2 de la central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Calleros, G.; Mendez, A.; Gomez, R.A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Veracruz (Mexico); Castillo, R.; Bravo, J.M. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)]. E-mail: gcm9acpp@cfe.gob.mx

2004-07-01

The monitor of loose parts (Loose Parts Monitoring System) installed in the Unit 2 of the Laguna Verde Central is a tool to detect strange objects or parts loose in the system of refrigeration of the reactor that could be impacted in the walls of the recirculation knots or in the internal of the reactor. In this work two applications are shown carried out with the Monitor of Loose Parts, determining the characteristics of the stable nominal conditions, those which when changing, they are used to diagnose during the Cycle 6 of the Unit 2, failures in the components of the the recirculation circuits or to identify mechanical vibrations of the recirculation knots induced by a flow of recirculation bistable associated to operative conditions of the reactor. (Author)

Application of new control technology during the maintenance of equipment in the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Ojeda R, M. A.

2008-01-01

In the nuclear power plant of Laguna Verde, in normal operation and recharges are carried out activities of preventive maintenance and corrective to different equipment, due to the one displacement of radioactive materials from the vessel of the reactor until the one system of vapor, different radiation levels are generated (from low until very high) in the circuits of vapor and water, the particles can be incrusted on those interior surfaces of the pipes and equipment, creating this way a potential risk of contamination and exhibition during the maintenance of equipment. To help to optimize the dose to the personnel the use of new technology the has been implemented which besides contributing an absolute control of the work, it offers bigger comfort to the one worker during the development of their work, also contributing a supervision more effective of the same one. Using the captured and processed information of the work developed you can use for the personnel's capacitation and feedback of the work for the continuous improvement of the same one. During a reduction of programmed power and normal operation are carried out maintenance correctives and specific works to preserve the readiness and ability of the equipment and with this to maintain the security of the nuclear power plant. The development of the theme it is showing the advances and commitments of personnel to take to excellence to the nuclear power plant of Laguna Verde showing to the obtained results of the dose and benefits of 2 works carried out in the nuclear power plant where tools ALARA were applied as well as the use of the new technology (Video Equipment of Tele dosimetry and Audio 'VETA') in works carried out in the building of purification level 10.15, change and cuts of filter of the prefilters of system G16, as well as,the retirement and transfer for its decay of High Integrity Container (HIC) of the building of purification level -0.55 to the Temporary Warehouse in Site. Works of high

Validation of a new software version for monitoring of the core of the Unit 2 of the Laguna Verde power plant with ARTS

International Nuclear Information System (INIS)

Calleros, G.; Riestra, M.; Ibanez, C.; Lopez, X.; Vargas, A.; Mendez, A.; Gomez, R.

2005-01-01

In this work it is intended a methodology to validate a new version of the software used for monitoring the reactor core, which requires of the evaluation of the thermal limits settled down in the Operation Technical Specifications, for the Unit 2 of Laguna Verde with ARTS (improvements to the APRMs, Rod Block Monitor and Technical specifications). According to the proposed methodology, those are shown differences found in the thermal limits determined with the new versions and previous of the core monitoring software. Author)

Evaluation of the integrity and duration of the Laguna Verde nuclear power plant life- Plant Life Management program (PLIM). TC MEX 04/53 Technical Cooperation Project

International Nuclear Information System (INIS)

Arganis J, C.R.; Diaz S, A.; Aguilar T, J.A.

2006-01-01

As part of the IAEA TC MEX 04/53 Project 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Handling Program of plant' whose objective is the one of beginning the actions to apply the methodology of Handling of plant life in the Unit 1 of the Laguna Verde Nucleo electric Central for to obtain the Renovation of License in 2020 the ININ, through the Department of Synthesis and Characterization of materials has carried out more of 20 analysis of susceptibility to the intergranular cracking for corrosion under effort in interns so much of the reactor of the unit 1 like of the unit 2 documenting the current state of components based on the type or types of materials that conform them, to it thermomechanical history, operational and of production, as well as of the particularities associated to its use and operation. For the application of the methodology of life handling of plant 5 structure systems or pilot components were selected, to carry out the programs of handling of the aging and handling of plant life: The encircling of the reactor core (Core Shroud), the reactor pressure vessel (Reactor Pressure Vessel), the primary container (Primary Containment), the recirculation system of feeding water (Reactor Feed Water) and cables. (Author)

Report on the Fourth Reactor Refueling. Laguna Verde Nuclear Central. Unit 1. April-May 1995

International Nuclear Information System (INIS)

Mendoza L, A.; Flores C, E.; Lopez G, C.P.F.

1995-01-01

The fourth refueling of the Unit 1 of Laguna Verde Nuclear Central was executed in the period of April 17 to May 31 of 1995 with the participation of a task group of 358 persons, included technicians and radiation protection officials and auxiliaries.The radiation monitoring and radiological surveillance to the workers was present length ways the refueling process and always attached to the ALARA criteria. The check points for radiation levels were set at: primary container or dry well, reloading floor, decontamination room (level 10.5), turbine building and radioactive waste building. To take advantage of the refueling process, rooms 203 and 213 of the turbine buildings were subject to inspection and maintenance work in valves, heaters and drains of heaters. Management aspects as personnel selection and training, costs, and countable are also presented in this report. Owing to the high cost of man-hour of the members of the ININ staff, its participation in the refueling process was in smaller number than years before. (Author)

Analysis of the Power oscillations event in Laguna Verde Nuclear Power Plant. Preliminary Report

International Nuclear Information System (INIS)

Gonzalez M, V.M.; Amador G, R.; Castillo, R.; Hernandez, J.L.

1995-01-01

The event occurred at Unit 1 of Laguna Verde Nuclear Power Plant in January 24, 1995, is analyzed using the Ramona 3 B code. During this event, Unit 1 suffered power oscillation when operating previous to the transfer at high speed recirculating pumps. This phenomenon was timely detected by reactor operator who put the reactor in shut-down doing a manual Scram. Oscillations reached a maximum extent of 10.5% of nominal power from peak to peak with a frequency of 0.5 Hz. Preliminary evaluations show that the event did not endangered the fuel integrity. The results of simulating the reactor core with Ramona 3 B code show that this code is capable to moderate reactor oscillations. Nevertheless it will be necessary to perform a more detailed simulation of the event in order to prove that the code can predict the beginning of oscillations. It will be need an additional analysis which permit the identification of factors that influence the reactor stability in order to express recommendations and in this way avoid the recurrence of this kind of events. (Author)

Participation of the ININ in the activities of radioactive waste management of the Laguna Verde Central

International Nuclear Information System (INIS)

Medrano L, M.; Rodriguez C, C.; Linares R, D.; Ramirez G, R.; Zarate M, N.

2006-01-01

From the beginning of the operation of the Laguna Verde Central (CLV) the National Institute of Nuclear Research (ININ) has come supporting the CLV in the activities of administration of the humid and dry radioactive waste generated by the operation of the two units of the CLV, from the elaboration of procedures to the temporary storage in site, the implementation of a program of minimization and segregation of dry solid wastes, until the classification of the lots of humid waste and bulk dry wastes. In this work the description of the management activities of radioactive wastes carried out by the ININ in the facilities of the CLV to the date is presented, as well as some actions that they are had drifted in the future near, among those that it stands out the determination of the total alpha activity in humid samples by means of scintillation analysis. (Author)

Results of Cable Aging Management Tests for Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Garcia Hernandez, E.E.; Vazquez Cervantes, R.M.; Bonifacio M, J.; Garcia Garcia, J.

2012-01-01

Laguna Verde Nuclear Power Plant (LVNPP) located in Veracruz, Mexico is a BWR plant, two Units with 810 MWe each one, Unit 1 (1989) and Unit 2 (1990). The Equipment Qualification (EQ) Group at the Nuclear Research National Institute (ININ) has been working with the plant on tasks to develop the LVNPP cables Aging Management Program (AMP), as part of the technical basis to extend the operational life of the plant through license renewal up to 60 years. LVNPP cables are qualified for 40 years plus a LOCA DBA in accordance with 10.CFR 50.49 and the IEEE Std-323 and IEEE St. 383. The first studies for cables AMP have been performed with samples of safety related I and C cables taken from the LVNPP warehouse, similar brands and models as installed at the plant. ININ applied the condition monitoring techniques to these samples to identify predictive degradation and to establish the methodology for cables AMP, focused to the LVNPP license renewal. Cable tests program has been running at the EQ Lab in ININ, performing accelerated aging by steps up to 60 years and to 40 years plus a LOCA test. Determination for Activation Energy (Ea) and Oxidation Induction Time (OIT) methods were developed applying a DSC/TGA calorimeter. (author)

Arrangement and statistics of storage containers of spent fuel for assemblies of the SFP of NPP-L V, Unit 1; Arreglo y estadistica de contenedores de almacenamiento de combustible gastado para los ensambles de la ACG de la Unidad 1 de la Central Nucleoelectrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Mijangos D, Z. E.; Vargas A, A. F.; Amador C, C., E-mail: zoedelfin@gmail.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Km 44.5 Carretera Cardel-Nautla, 91476 Laguna Verde, Alto Lucero, Veracruz (Mexico)

2014-10-15

This work presents the determination of assemblies of the spent fuel pool (SFP) of the nuclear power plant of Laguna Verde (NPP-L V) which are candidates to be assigned to storage containers of independent spent fuel, with the objective of liberating decay heat and to have more space in the SFP, for the store of retired assemblies of the reactors in future reloads of NPP-L V, besides that the removed assemblies of the SFP should be stored in specific containers to guarantee the physical safety of them, as well as the radiological protection to the population and the environment. The design of the containers considered in this work is to store a maximum of 69 assemblies; it has a thermal capacity of 26 kilowatts and allows storing assemblies with a minimum of 5 years of have been extracted of the reactor core. Is considered that in 2016 start the storage of the spent assemblies on the containers, the candidates assemblies to store cover from the first reload in 1991, until the assemblies deposited in the SFP in the 14 reload in 2010; therefore in 2016, such assemblies will have fulfilled with the criteria of 5 years of have been removed of the Reactor, also the 69 assemblies assigned to each container will have a resulting decay heat that does not exceed the thermal capacity of the container, but that in great percentage approximates to the same one, and this way to take full advantage of their storage capacity and thermal capacity for each container. This work also contains the arrangement to accommodate the assemblies in the containers; such arrangement is constituted by areas according to the decay heat of each assembly. (Author)

Closure simulation of the MSIV of Unit 1 of the Laguna Verde nuclear power plant using the Simulate 3K code; Simulacion del cierre de las MSIV de la Unidad 1 de la central nuclear Laguna Verde empleando el codigo Simulate-3K

Energy Technology Data Exchange (ETDEWEB)

Alegria A, A., E-mail: aalegria@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

2015-09-15

In this paper the simulation of closure transient of all main steam isolation valves (MSIV) was performed with the Simulate-3K (S-3K) code for the Unit 1 of the Laguna Verde nuclear power plant (NPP-LV), which operates to thermal power of 2317 MWt, corresponding to the cycle 15 of operation. The set points for the performance of systems correspond to those set out in transient analysis: 3 seconds for the closure of all MSIV; the start of Scram when 121% of the neutron flux is reached, respect from baseline before the transient; the opening by peer of safety relief valves (SRV) in relief mode when the set point of the pressure is reached, the shoot of the feedwater flow seconds after the start of closing of the MSIV and the shoot of the recirculation water pumps when the pressure is reached in the dome of 1048 psig. The simulation time was of 57 seconds, with the top 50 to reach the steady state, from which the closure of all MSIV starts. In this paper the behavior of the pressure in the dome are analyzed, thermal power, neutron flux, the collapsed water level, the flow at the entrance of core, the steam flow coming out of vessel and the flow through of the SRV; the fuel temperature, the minimal critical power ratio, the readings in the instrumentation systems and reactivities. Instrumentation systems were implemented to analyze the neutron flux, these consist of 96 local power range monitors (LPRM) located in different radial and axial positions of the core and 4 channels of average power range monitors, which grouped at 24 LPRM each one. LPRM response to the change of neutron flux in the center of the core, at different axial positions is also shown. Finally, the results show that the safety limit MCPR is not exceeded. (Author)

Out of operation in simultaneous way of the two reactors of nucleoelectric central of Laguna Verde(Mexico)

International Nuclear Information System (INIS)

Mar, Bernardo Salas

2013-01-01

The two nuclear reactors that Mexico has in the Laguna Verde Nuclear Power Plant, were out of operation simultaneously in September 2012. First it was reported that one of the reactors had problems with the diesel generator, while the other had problems with the nuclear fuel reloading. The day after it was reported a problem related to sediment in the Obra de Toma, place the plant feeds seawater to cool the condenser the depth to which it must operate is 6 meters, with the current level of 1.5 meters, causing a lack of cooling water. Finally it was reported the cause of the suspension of operations, the cracks in jet pumps in both reactors. It is described a brief analysis of these opinions. The reactors are of cooling water of General Electric (BWR-5) and generate 1640 MWe each one

New recommendations of the ICRP and the ALARA program of the Nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Padilla C, I.

1991-01-01

In view of the events happened in it finishes it decade, in the nuclear environment, it is necessary that any he/she practices that it involves exhibition to the radiation, real or potential, be detailed and systematically analyzed by the light of the current knowledge, capitalizing the generated experience. They think about three fundamental aspects in the campaign of radiological cultivation: 1. New methods of evaluation of equivalent dose. 2. Limit of individual dose, base of the change and control implications, and 3. Analysis philosophies and the application of the system of dose limitation. The program ALARA of the Laguna Verde Central from its installation in 1987 observes and it implements actions trending to optimize it practice of situation of potential and planned exhibition with the purpose of fulfilling the commitment settled down in the declaration of political of this program

Technical assistance in relationship with the reloading analysis of the Laguna Verde Unit 2 reactor. Executive abstract; Asistencia tecnica en relacion con el analisis de recargas de la CNLV U-2

Energy Technology Data Exchange (ETDEWEB)

Alonso V, G.; Castro B, M.; Gallegos E, R.; Hernandez L, H.; Montes T, J.L.; Ortiz S, J. J.; Perusquia C, R. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1993-11-15

The objective of the report was to carry out a comparative analysis of costs of energy generation among the designs GE9B of General Electric, 9X9-IX of SIEMENS and SVEA-96 of ABB ATOM, proposed to be used as recharge fuel in the Unit 2 of the Laguna Verde Nuclear Power station. (Author)

Evaluation of the integrity and duration of the Laguna Verde nuclear power plant life- Plant Life Management program (PLIM). TC MEX 04/53 Technical Cooperation Project; Evaluacion de la integridad y extension de vida de la planta de potencia nuclear Laguna Verde- Programa de manejo de vida de planta (PLIM). Proyecto de cooperacion tecnica TC MEX 04/53

Energy Technology Data Exchange (ETDEWEB)

Arganis J, C.R.; Diaz S, A.; Aguilar T, J.A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2006-07-01

As part of the IAEA TC MEX 04/53 Project 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Handling Program of plant' whose objective is the one of beginning the actions to apply the methodology of Handling of plant life in the Unit 1 of the Laguna Verde Nucleo electric Central for to obtain the Renovation of License in 2020 the ININ, through the Department of Synthesis and Characterization of materials has carried out more of 20 analysis of susceptibility to the intergranular cracking for corrosion under effort in interns so much of the reactor of the unit 1 like of the unit 2 documenting the current state of components based on the type or types of materials that conform them, to it thermomechanical history, operational and of production, as well as of the particularities associated to its use and operation. For the application of the methodology of life handling of plant 5 structure systems or pilot components were selected, to carry out the programs of handling of the aging and handling of plant life: The encircling of the reactor core (Core Shroud), the reactor pressure vessel (Reactor Pressure Vessel), the primary container (Primary Containment), the recirculation system of feeding water (Reactor Feed Water) and cables. (Author)

Proposal of the visual inspection of the integrity of the storage cells of spent fuel from the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Gonzalez M, J. L.; Rivero G, T.; Merino C, F. J.; Santander C, L. E.

2015-09-01

As part of the evaluation of the structural integrity of the components of nuclear plants, particularly those applying for life extension is necessary to carry out inspections and nondestructive testing to determine the state meet. In many cases these activities are carried out in areas with high levels of radiation and contamination difficult to access, so that are required to use equipment or robotic systems operated remotely. Among others, the frames and cells of the storage pools for spent fuel are structures subject to a program of tests and inspections, and become relevant because the nuclear power plant of Laguna Verde (NPP-LV) is processing the license to extend the operational life of its reactors. Of non-destructive testing can be used to verify the physical condition of the frames and storage cells, is the remote visual inspection which is a test that allows determine the physical integrity of the components by one or more video cameras designed to applications in underwater environments with radiation, and are used to identify and locate adverse conditions such as ampoules, protuberances, pitting, cracks, stains or buckling, which could affect the three main functions for which the store components are designed: to maintain the physical integrity of spent fuels, store them properly guaranteeing their free insertion and removal, and ensure that the store as a whole meets the criticality criteria that k eff is less than 0.95 throughout the life of the plant. This paper describes a proposal to carry out the visual inspection of the storage cells of spent fuel from the NPP-LV using a probe including one or more video cameras along with your recorder, and its corresponding control program. It is noted that due to the obtained results, the nuclear power plant personnel can make decisions regarding remedial actions or applying complementary methods to verify that the cells and frames have not lost their physical integrity, or in particular that the cover

Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde; Implementacion del proyecto de confiabilidad de equipo en la Central Nucleoelectrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Rios O, J. E.; Martinez L, A. G. [CFE, Central Laguna Verde, Subgerencia General de Operacion, Veracruz (Mexico)]. e-mail: jrios@cfe.gob.mx

2008-07-01

A equipment is reliable if it fulfills the function for which was designed and when it is required. To implement a project of reliability in a nuclear power plant this associate to a process of continuous analysis of the operation, of the conditions and faults of the equipment. The analysis of the operation of a system, of the equipment of the same faults and the parts that integrate to equipment take to identify the potential causes of faults. The predictive analysis on components and equipment allow to rectify and to establish guides to optimize the maintenance and to guarantee the reliability and function of the same ones. The reliability in the equipment is without place to doubts a wide project that embraces from the more small component of the equipment going by the proof of the parts of reserve, the operation conditions until the operative techniques of analysis. Without place of doubt for a nuclear power plant the taking of decisions based on the reliability of their systems and equipment will be the appropriate for to assure the operation and reliability of the same one. In this work would appear the project of reliability its processes, criteria, indicators action of improvement and the interaction of the different disciplines from the Nuclear Power Plant of Laguna Verde like a fundamental point for it put in operation. (Author)

Estimation of requirements of eolic energy equivalent to the electric generation of the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Garcia V, M.A.; Hernandez M, I.A.; Martin del Campo M, C.

2004-01-01

The advantages are presented that have the nuclear and eolic energy as for their low environmental impact and to the human health. An exercise is presented in the one that is supposed that the electric power generated by the Laguna Verde Nuclear Power plant (CNLV), with capacity of 1365 M W, it should be produced by eolic energy when in the years 2020 and 2025 the units 1 and 2 of the CNLV reach its useful life and be moved away. It is calculated the number of aero generators that would produce the electric power average yearly of the CNLV, that which is equal to install eolic parks with capacity of 2758 M W, without considering that it will also be invested in systems of back generation to produce electricity when the aero generators stops for lack of wind. (Author)

Applications of the monitor of loose parts in the cycle 6 of the Laguna Verde Unit 2 power plant

International Nuclear Information System (INIS)

Calleros, G.; Mendez, A.; Gomez, R.A.; Castillo, R.; Bravo, J.M.

2004-01-01

The monitor of loose parts (Loose Parts Monitoring System) installed in the Unit 2 of the Laguna Verde Central is a tool to detect strange objects or parts loose in the system of refrigeration of the reactor that could be impacted in the walls of the recirculation knots or in the internal of the reactor. In this work two applications are shown carried out with the Monitor of Loose Parts, determining the characteristics of the stable nominal conditions, those which when changing, they are used to diagnose during the Cycle 6 of the Unit 2, failures in the components of the the recirculation circuits or to identify mechanical vibrations of the recirculation knots induced by a flow of recirculation bistable associated to operative conditions of the reactor. (Author)

Options for the ultimate storage of low and medium level radioactive wastes produced at Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Emeterio, Miguel

1991-01-01

The devoted time and still to be expend in prepare, execute and teach permanent and safe solutions to the problem of the evaluation of radioactive wastes reflects the political, economic and environmental importance with respect to public health and safety invested in this task, as well as, its technological challenges. In the case of Laguna Verde nuclear power plant, its low and medium level radioactive wastes are stored in the beginning in a temporal store with a capacity of 2000 m 3 sufficient to four years of normal operation; according to what it is necessary to select one of different ways of waste storage. Different technologies has been evaluated and the preliminary conclusion is that for Mexico the more feasible way to store radioactive wastes is in tumulus (Author)

Calculating of radiation doses in rutinary unloads of liquid wastes from Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Molina, G.

1985-01-01

Utilization of nuclear energy to produce or generate electricity is a growing practice in the world, since it represent an economic and safe option to replace fossil fuels. During operation of nuclear power plants, radioactive materials are produced. A small fraction of these material are released to environment in the form of liquid or gaseous effluents. Estimation of radiation doses causing by effluents release has three purposes. During design phase of a nuclear station it is useful to adapt the wastes treatment systems to acceptable limits. During licensing phase, the regulator organism verifies the design of nuclear station effectuating estimation of doses. Finally, during operation of a nuclear station, before every unload of radioactive effluents, radiation doses should be evaluate in order to fulfill technical specifications, which limit the release of radioactive materials to environment. 1. To perform calculations of individual doses due to liquid radioactive effluents unload in units 1 and 2 of Laguna Verde nuclear power plant (In licensing phase). 2. To perform a parametric study of the effect of unload recirculation over individual dose, since recirculation has two principal effects: thermodynamical effects in nuclear station and radioactivity concentration, the last can affect the fullfilment of dose limits. 3. To perform the calculation of collective doses causes by unloads of liquid effluents within a radius of 80 Kms. of nuclear station caused by unload of liquid radioactive effluents during normal operation of nuclear power plant and does not include doses caused during accident conditions. In Mexico the organism in charge of regulation of peaceful uses of nuclear energy is Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) and for Laguna Verde licensing, the regulations of country who manufactured the reactor was adopted, it is to say United States of America. In Appendix 'C' units used along this work are explained. Unless another

Validation of a new version of software for monitoring the core of nuclear power plant of Laguna Verde Unit 2, at the end of Cycle 10

International Nuclear Information System (INIS)

Hernandez, G.; Calleros, G.; Mata, F.

2009-10-01

This work shows the differences observed in thermal limits established in the technical specifications of operation, among the new software, installed at the end of Cycle 10 of Unit 2 of nuclear power plant of Laguna Verde, and the old software that was installed from the beginning of the cycle. The methodology allowed to validate the new software during the coast down stage, before finishing the cycle, for what could be used as tool during the shutdown of Unit 2 at the end of Cycle 10. (Author)

The Laguna Verde Central by it results in maintenance and operation consolidates it position of world class enterprise; La central Laguna Verde por sus resultados en mantenimiento y operacion consolida su posicion de empresa de clase mundial

Energy Technology Data Exchange (ETDEWEB)

Rivera C, A. [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel- Nautla, Veracruz (Mexico)

2008-07-01

This work has the objective of showing the results of the Laguna VerdeCentral in the maintenance and the operation that in the short term the generation of electricity in Mexico by nuclear means is a viable option, in virtue of their positioning like Company of World Class, when winning March 25, 2008 the National Prize of Quality with the more high qualification in the history of this prize, same that allows us to be very optimistic in increasing the possibility to that the Nuclear Industry in Mexico grows. The focus of the comparative graphs, with official data of the Comision Federal de Electricidad (CFE), it is so that it is observed that the Laguna Verde Central is above those the other types of generation like they are the Coal power stations, Thermoelectric, Hydroelectric, likewise they can see that we are for up of the Independent Producers of Energy. The information of the electric power generation is presented by reactors nuclear at world level that is growing, in having 31 Generating Units in the construction process that favors the decisions making in the Government federal, likewise contributed data of the increment projected for 2016 in the country of 380,102 GWh that equivalent to 63% of growth, where it exists without place to doubts a good opportunity for the nucleoelectricity. The Investment Works Program of Public Sector (POISE), it shows the information that 6,178 Mwe will be installed settled of a Non-defined Technology in Mexico, information that specifies the opportunity to be a viable option, because the one Plant Factor, the Production of Electric power, and the Variable Cost of Production, the energy generation by nuclear means is the more competitiveness. Finally this work stood out the effort that communitary works are developed to benefit to the society and the environment to be one Viable option not only for their high performance, or competitive for those more low costs, but also to improve the public opinion with the sustainable

Planning of activities in the Laguna Verde Central planning at 12 weeks; Planeacion de Actividades en la Central Laguna Verde planeacion a doce semanas

Energy Technology Data Exchange (ETDEWEB)

Chimalpopoca, C. [Comision Federal de Electricidad, Central Laguna Verde, Subgerencia General de Operacion y Planeacion, Veracruz (Mexico)]. e-mail: carlos.chimalpopoca@cfe.gob.mx

2007-07-01

The universe of works that are carried out in a nuclear facility to maintain effective the structures, systems and components require of a continuous analysis, in the order of the maintenance frequencies that can be of the preventive, predictive or corrective type. Each component is associated to reserve parts, readiness of systems, in fulfillment to the operation technical specifications, to the environment of the one work; each component requires of a planning level, where it is distinguished with clarity when they are executed, in the operation stage, stop or recharge. This work has as end to show like the activities are planned during the operation, using planning methods to twelve weeks, where the reach of the task is conceptualized, operative requirements, of reserve parts, of the work environment analysis, of those radiological conditions, of the authorizations for their execution, the same execution and the evaluation post work like a technique to maintain in continuous improvement the tasks of the maintenance of the Units of the Power station. A motor valve to be worked in its internals requires access to the work point, it requires bill of the system, electric disconnection, maneuvers to disassemble actuators and retirement of thermal isolation if it applies, reserve parts of the caps joints, control mechanisms, personal, tools, radiological control. The success of the continuous operation of a power station is in the planning quality, the attention of each one of the details to assure that the components, structures and components stay effective to make their function when they are demanded. The planning task requires of experience and knowledge of each some of the components, the task of planning of activities and its execution is multidisciplinary This work has that purpose, to show the planning tools in the Laguna Verde Nuclear Power station, under the concept of twelve weeks. (Author)

Experiences with the technical cooperation project TC MEX 04/53. Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant. Management program of the plant life (PLIM); Experiencias con el proyecto de cooperacion tecnica TC MEX 04/53. Evaluacion de la integridad y extension de vida de la planta de potencia nuclear Laguna Verde. Programa de Manejo de vida de planta (PLIM)

Energy Technology Data Exchange (ETDEWEB)

Arganis J, C.R.; Aguilar T, J.A. [ININ, 52750 Ocoyoacac, Estado de Mexico (Mexico); Guevara M, A.; Garcia M, C.; Martinez G, R.R.; Griz C, M.M.; Sanchez M, M.A.; Diaz O, R.C. [CFE, Subgerencia de Ingenieria, Carretera Veracruz-Medellin, Km. 7.5 Veracruz (Mexico)]. e-mail: craj@nuclear.inin.mx

2006-07-01

In the biennium 2005-2006 the project of technical cooperation with the International Atomic Energy Agency OIEA TC MEX 04/53 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Plant life handling program (PLIM)' was approved, which has as objective the one to begin the actions to apply the methodology of Handling of life of Plant (PLIM) in the Unit I (Ul) of the Laguna Verde Nucleo electric Central (CNLV), in order to obtain the Renovation of License (LR), in a long term (2020). To apply this methodology 5 systems they were selected, structures or components (SEC) to carry out the handling programs of the one aging (AMP), and PLIM which are: The encircling of the reactor core (Core Shroud), the pressure vessel of the reactor (Reactor Pressure Vessel), the one primary container (Primary Containment), the system of feeding water (Reactor Feed Water) and cables, which were not in this work to be of another nature. The report presents the more important aspects considered in these systems for their programs of AMP and PLIM, as like a revision of those selection processes and evaluation (screening and scoping) for the application of PLIM in the systems of the Ul of the CNLV. (Author)

Impact of flow induced vibration acoustic loads on the design of the Laguna Verde Unit 2 steam dryer

International Nuclear Information System (INIS)

Forsyth, D. R.; Wellstein, L. F.; Theuret, R. C.; Han, Y.; Rajakumar, C.; Amador C, C.; Sosa F, W.

2015-09-01

Industry experience with Boiling Water Reactors (BWRs) has shown that increasing the steam flow through the main steam lines (MSLs) to implement an extended power up rate (EPU) may lead to amplified acoustic loads on the steam dryer, which may negatively affect the structural integrity of the component. The source of these acoustic loads has been found to be acoustic resonance of the side branches on the MSLs, specifically, coupling of the vortex shedding frequency and natural acoustic frequency of safety relief valves (SRVs). The resonance that results from this coupling can contribute significant acoustic energy into the MSL system, which may propagate upstream into the reactor pressure vessel steam dome and drive structural vibration of steam dryer components. This can lead to high-cycle fatigue issues. Lock-in between the vortex shedding frequency and SRV natural frequency, as well as the ability for acoustic energy to propagate into the MSL system, are a function of many things, including the plant operating conditions, geometry of the MSL/SRV junction, and placement of SRVs with respect to each other on the MSLs. Comision Federal de Electricidad and Westinghouse designed, fabricated, and installed acoustic side branches (ASBs) on the MSLs which effectively act in the system as an energy absorber, where the acoustic standing wave generated in the side-branch is absorbed and dissipated inside the ASB. These ASBs have been very successful in reducing the amount of acoustic energy which propagates into the steam dome. In addition, modifications to the Laguna Verde Nuclear Power Plant Unit 2 steam dryer have been completed to reduce the stress levels in critical locations in the dryer. The objective of this paper is to describe the acoustic side branch concept and the design iterative processes that were undertaken at Laguna Verde Unit 2 to achieve a steam dryer design that meets the guidelines of the American Society of Mechanical Engineers, Boiler and Pressure

Impact of flow induced vibration acoustic loads on the design of the Laguna Verde Unit 2 steam dryer

Energy Technology Data Exchange (ETDEWEB)

Forsyth, D. R.; Wellstein, L. F.; Theuret, R. C.; Han, Y.; Rajakumar, C. [Westinghouse Electric Company LLC, Cranberry Township, PA 16066 (United States); Amador C, C.; Sosa F, W., E-mail: forsytdr@westinghouse.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km 42.5 Carretera Cardel-Nautla, 91680 Alto Lucero, Veracruz (Mexico)

2015-09-15

Industry experience with Boiling Water Reactors (BWRs) has shown that increasing the steam flow through the main steam lines (MSLs) to implement an extended power up rate (EPU) may lead to amplified acoustic loads on the steam dryer, which may negatively affect the structural integrity of the component. The source of these acoustic loads has been found to be acoustic resonance of the side branches on the MSLs, specifically, coupling of the vortex shedding frequency and natural acoustic frequency of safety relief valves (SRVs). The resonance that results from this coupling can contribute significant acoustic energy into the MSL system, which may propagate upstream into the reactor pressure vessel steam dome and drive structural vibration of steam dryer components. This can lead to high-cycle fatigue issues. Lock-in between the vortex shedding frequency and SRV natural frequency, as well as the ability for acoustic energy to propagate into the MSL system, are a function of many things, including the plant operating conditions, geometry of the MSL/SRV junction, and placement of SRVs with respect to each other on the MSLs. Comision Federal de Electricidad and Westinghouse designed, fabricated, and installed acoustic side branches (ASBs) on the MSLs which effectively act in the system as an energy absorber, where the acoustic standing wave generated in the side-branch is absorbed and dissipated inside the ASB. These ASBs have been very successful in reducing the amount of acoustic energy which propagates into the steam dome. In addition, modifications to the Laguna Verde Nuclear Power Plant Unit 2 steam dryer have been completed to reduce the stress levels in critical locations in the dryer. The objective of this paper is to describe the acoustic side branch concept and the design iterative processes that were undertaken at Laguna Verde Unit 2 to achieve a steam dryer design that meets the guidelines of the American Society of Mechanical Engineers, Boiler and Pressure

Simulation of the steady state of the Laguna Verde Nuclear power station at full power (1931 MWt and 2027 Mwt) with the SCDAPSIM code; Simulacion del estado estacionario de la Central Nucleoelectrica de Laguna Verde a plena potencia (1931 MWt y 2027 MWt) con el codigo SCDAPSIM

Energy Technology Data Exchange (ETDEWEB)

Amador G, R.; Nunez C, A.; Mateos, E. del A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico)

2001-07-01

This document describes two models developed for the Laguna Verde Nuclear Power Station (LVNPP) using SCDAPSIM computer code. These models represent the LVNPP in normal operation with a nominal power of 1931 MWt and power uprate conditions of 2027 MWt. The steady states obtained by means of these models comply with the criteria established by the ANSI/ANS-3.5-1985 for nuclear power plant simulators. This criteria has been applied to the models of the LVNPP developed by CNSNS in want of some international accepted criteria for ''Best Estimation'' computer codes. These models will be the bases to carry out studies of validation of the own models as well as the analysis of diverse scenarios that evolve to a severe accident. (Author)

Study and characterization of noble metal deposits on similar rusty surfaces to those of the reactor U-1 type BWR of nuclear power station of Laguna Verde; Estudio y caracterizacion de depositos de metales nobles sobre superficies oxidadas similares a las del reactor de la Central de Laguna Verde (CNLV) U1 del tipo BWR

Energy Technology Data Exchange (ETDEWEB)

Flores S, V. H.

2011-07-01

In the present investigation work, were determined the parameters to simulate the conditions of internal oxidation reactor circulation pipes of the nuclear power plant of Laguna Verde in Veracruz. We used 304l stainless steel cylinders with two faces prepared with abrasive paper of No. 600, with the finality to obtain similar surface to the internal circulation piping nuclear reactor. Oxides was formed within an autoclave (Autoclave MEX-02 unit B), which is a device that simulates the working conditions of the nuclear reactor, but without radiation generated by the fission reaction within the reactor. The oxidation conditions were a temperature of 280 C and pressure of 8 MPa, similar conditions to the reactor operating in nuclear power plant of Laguna Verde in Veracruz, Mexico (BWR conditions), with an average conductivity of 4.58 ms / cm and 2352 ppb oxygen to simulate normal water chemistry NWC. Were obtained deposits of noble metal oxides formed on 304l stainless steel samples, in a 250 ml autoclave at a temperature range of 180 to 200 C. The elements that were used to deposit platinum-rhodium (Pt-Rh) with aqueous Na{sub 2}Pt (OH){sub 6} and Na{sub 3}Rh (NO{sub 2}){sub 6}, Silver (Ag) with an aqueous solution of AgNO{sub 3}, zirconium (Zr) with aqueous Zr O (NO{sub 3}) and ZrO{sub 2}, and zinc (Zn) in aqueous solution of Zn (NO{sub 3}){sub 2} under conditions of normal water chemistry. Also there was the oxidation of 304l stainless steel specimens in normal water chemistry with a solution of Zinc (Zn) (NWC + Zn). Oxidation of the specimens in water chemistry with a solution of zinc (Zn + NWC) was prepared in two ways: within the MEX-02 autoclave unit A in a solution of zinc and a flask at constant temperature in zinc solution. The oxides formed and deposits were characterized by scanning electron microscopy, energy dispersive X-ray analysis, elemental field analysis and X-ray diffraction. By other hand was evaluated the electrochemical behavior of the oxides

Closure simulation of the MSIV of Unit 1 of the Laguna Verde nuclear power plant using the Simulate 3K code

International Nuclear Information System (INIS)

Alegria A, A.

2015-09-01

In this paper the simulation of closure transient of all main steam isolation valves (MSIV) was performed with the Simulate-3K (S-3K) code for the Unit 1 of the Laguna Verde nuclear power plant (NPP-LV), which operates to thermal power of 2317 MWt, corresponding to the cycle 15 of operation. The set points for the performance of systems correspond to those set out in transient analysis: 3 seconds for the closure of all MSIV; the start of Scram when 121% of the neutron flux is reached, respect from baseline before the transient; the opening by peer of safety relief valves (SRV) in relief mode when the set point of the pressure is reached, the shoot of the feedwater flow seconds after the start of closing of the MSIV and the shoot of the recirculation water pumps when the pressure is reached in the dome of 1048 psig. The simulation time was of 57 seconds, with the top 50 to reach the steady state, from which the closure of all MSIV starts. In this paper the behavior of the pressure in the dome are analyzed, thermal power, neutron flux, the collapsed water level, the flow at the entrance of core, the steam flow coming out of vessel and the flow through of the SRV; the fuel temperature, the minimal critical power ratio, the readings in the instrumentation systems and reactivities. Instrumentation systems were implemented to analyze the neutron flux, these consist of 96 local power range monitors (LPRM) located in different radial and axial positions of the core and 4 channels of average power range monitors, which grouped at 24 LPRM each one. LPRM response to the change of neutron flux in the center of the core, at different axial positions is also shown. Finally, the results show that the safety limit MCPR is not exceeded. (Author)

Relative frequencies of deletereo genes in populations of droshopila Melanogaster from Laguna Verde, Veracruz; Frecuencias relativas de genes deletereos en poblaciones de Drosophila melanogaster originarias de Laguna Verde, Veracruz

Energy Technology Data Exchange (ETDEWEB)

Salceda, V. M. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: vmss@nuclear.inin.mx

2008-07-01

In order to obtain data about the possible changes and/or damages that could cause the operation of the reactors of the nuclear power plant of Laguna Verde to the populations of drosophila Melanogaster that lives in the zone, one carried out one series of biannual collections (summer and winter) during the years 1991-1992 and 1996-1998 to obtain individuals of this species and to subject them to a battery of tests. The flies of this species that it was possible to capture were transported to the Biology Laboratory of the National Institute of Nuclear Research, where they were put under in individual form a series of you cross they allowed that us in the third generation to detect the presence of deletereo genes that following their viability were catalogued like normal, lethal or less lethal according to the methodology of Wallace. This way a total of 933 second chromosomes was analyzed to leave of them the relative frequencies were calculated of each one of the categories, for each sample station. The result of the applied statistical test indicates us that not significant difference exists among the populations and that the differences of having them must only to the environment changes something that usually happen in all the population. For what we can point out that the presence of the reactors does not seem to influence negatively in the behavior of the population that lives in the zone. (Author)

Actinides inventory of the nuclear power plant of Laguna Verde Unit 1; Inventario de actinidos de la Central Nuclear Laguna Verde Unidad 1

Energy Technology Data Exchange (ETDEWEB)

Martinez C, E.; Ramirez S, J. R. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Alonso V, G., E-mail: eduardo.martinez@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U. P. Adolfo Lopez Mateos, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico)

2013-10-15

At the present time 435 nuclear power reactors exist for the electricity generation operating in the world and 63 in construction. Mexico has two reactors type BWR in the nuclear power plant of Laguna Verde. The nuclear fuel that is used in the nuclear reactors is retired of the reactor core when the energy that this contained has been extracted. This used fuel is known as spent nuclear fuel, the problem with this fuel is that was irradiated inside the reactor and continuous emitting a high radiation, as well as a significant heat quantity when being extracted, for what is necessary to maintain it in cooling and with some shielding to be protected of the radiation that emits. This objective is achieved confining the fuel in the spent nuclear fuel pool, where it is cooled and the same pool provides the necessary shielding to maintain the surroundings in safety radiation levels for the personnel that work in the power plant. An inconvenience of the pools is its limited storage capacity and that after certain time is necessary to remove the fuel, according to the established regulation to continue operating. To correct this inconvenience, two alternatives of spent fuel disposition exist, 1) the final disposition in deep geologic repositories and 2) the reprocessing and recycled of spent fuel. Each alternative presents its particularities and specific problems; however taking many years to be able to implement anyone of them. To carry out the second option, is indispensable to estimate the total mass of actinides generated in the spent nuclear fuel, that which represents to develop a methodology for it, this action is the main purpose of the present work. Inside our calculation method was necessary to appeal to diverse computation tools as the codes Origin-S and Keno V.a. Later on the obtained were compared with a problem type Benchmark, being obtained a smaller absolute error to 1.0%. (Author)

Evaluation of radwaste minimization program of dry and wet active waste in the Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Luna-Garza, Hector

2001-01-01

A growing rate of radwaste volume production combined with an increase of both, costs and associated dose involved in its treatment and disposition processes have created a serious problem to the Laguna Verde Nuclear Power Plant (BWR, two Units, 682 Mwe each) in Mexico. Due the lack of a Final Repository in the country, the solution in the short or long terms relies on the success of a continuous and aggressive minimization program mainly based on modifications and upgrades applied to these processes. Technical and administrative strategies adopted by LVNPP for the reduction of Liquid Effluents and Dry and Wet Active Waste in the next three years are described. Based on the results of the LVNPP current radwaste process systems, an estimated accumulation of 11,502 m 3 by the year 2035 will exceed the actual on-site storage capacity. If the strategies succeed, this production would fall to an expected manageable volume of 4067 m 3 . (author)

Experiences with the technical cooperation project TC MEX 04/53. Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant. Management program of the plant life (PLIM)

International Nuclear Information System (INIS)

Arganis J, C.R.; Aguilar T, J.A.; Guevara M, A.; Garcia M, C.; Martinez G, R.R.; Griz C, M.M.; Sanchez M, M.A.; Diaz O, R.C.

2006-01-01

In the biennium 2005-2006 the project of technical cooperation with the International Atomic Energy Agency OIEA TC MEX 04/53 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Plant life handling program (PLIM)' was approved, which has as objective the one to begin the actions to apply the methodology of Handling of life of Plant (PLIM) in the Unit I (Ul) of the Laguna Verde Nucleo electric Central (CNLV), in order to obtain the Renovation of License (LR), in a long term (2020). To apply this methodology 5 systems they were selected, structures or components (SEC) to carry out the handling programs of the one aging (AMP), and PLIM which are: The encircling of the reactor core (Core Shroud), the pressure vessel of the reactor (Reactor Pressure Vessel), the one primary container (Primary Containment), the system of feeding water (Reactor Feed Water) and cables, which were not in this work to be of another nature. The report presents the more important aspects considered in these systems for their programs of AMP and PLIM, as like a revision of those selection processes and evaluation (screening and scoping) for the application of PLIM in the systems of the Ul of the CNLV. (Author)

Optimization of reloading Laguna Verde Central U1/U2, Federal Electricity Commission; Optimizacion de recargas Central Laguna Verde U1/U2, Comision Federal de Electricidad

Energy Technology Data Exchange (ETDEWEB)

Espinosa G, J.M. [Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km. 45.5, Municipio de Alto Lucero, Veracruz (Mexico)

2006-07-01

The Laguna Verde Central from the beginning of the commercial operation settled down as maximum priority 'the total safety in its operation' taking in consideration the so much experience of the good operation and of multiple recharges made in a sure and reliable way, and without separate us of the safety mystic of the CLV, but looking for to be better every day a new challenge it settled down 'to compare us with the best plants in the world' and certainly to work to classify us like one of them. For this we established a 4.0 year old plan (2003/2006) for the effectiveness all the processes in the power station that allowed us to measure our acting with the same parameters that settle down at international level (nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station, attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect, summing up means to be good in all the aspects). All the above mentioned would allow us to qualify us as level 1 of WANO (world proprietors association of nuclear centrals) at the end of the year 2006 and to pass to be part of this select group. After analyzing the acting record of the power station, evaluating our technical and economic capacity, the location of the installation besides revising the international experiences was defined that one of the concepts that impact considerably so much to the capacity factors and availability besides the dose and production cost is the duration of the recharge periods, for this reason the present work is elaborated. (Author)

Analysis of the preliminary trajectory of emergency venting of the nuclear power plant of Laguna Verde using RELAP5; Analisis de la trayectoria preliminar del venteo de emergencia de la Central Laguna Verde mediante RELAP5

Energy Technology Data Exchange (ETDEWEB)

Cecenas F, M.; Jimenez S, R.; Ovando C, R. [Instituto Nacional de Electricidad y Energias Limpias, Reforma No. 113, Col. Palmira, 42490 Cuernavaca, Morelos (Mexico); Tijerina S, F.; Tapia M, R. N., E-mail: mcf@iie.org.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, 94271 Veracruz (Mexico)

2016-09-15

For a commercial nuclear plant, the availability of a vent line to the atmosphere is an improvement to achieve the prevention and mitigation of the consequences of a severe accident. The importance of this system received greater attention after the Fukushima accident in 2011. Subsequently, in 2012 and 2013, the United States Nuclear Regulatory Commission issued documents stating that the venting must be able to dislodge 1% of the rated thermal power of the core without over pressurizing the primary container. To analyze the venting of the nuclear power plant of Laguna Verde, the line and the primary container are modeled using the thermo-hydraulic code RELAP5, simulating a release of 1% of the nominal licensed power to the container in the form of saturated steam. The vent has no problem to evacuate the energy and manages to keep the container without exceeding its design limit, and the highest percentage of thermal power that can channel the vent to the outside is approximately 3%. A sensitivity analysis increasing the diameter of the line to 14 inches allows increasing in 10% the percentage of power that can be vented to the outside without problem for the containment. (Author)

A mathematical model; Un modelo matematico para el comportamiento de la radiosensibilidad medida con la viabilidad huevo-adulto de Drosophila melanogaster y D. simulans de Laguna Verde, Veracruz

Energy Technology Data Exchange (ETDEWEB)

Castillo M, J.A.; Pimentel P, A.E. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2000-07-01

This work presents the results to define the adult egg viability behavior (VHA) of two species, Drosophila melanogaster and D. simulans obtained with the mathematical model proposed, as well as the respective curves. The data are the VHA result of both species coming from the vicinity of the Laguna Verde Nuclear Power plant (CNLV) comprise a 10 years collect period starting from 1987 until 1997. Each collect includes four series of data which are the VHA result obtained after treatment with 0, 4, 6 and 8 Gy of gamma rays. (Author)

Development of tools to manage the operational monitoring and pre-design of the NPP-LV cycle; Desarrollo de herramientas para administrar el seguimiento operativo y el pre-diseno del ciclo de la CLV

Energy Technology Data Exchange (ETDEWEB)

Perusquia, R.; Arredondo S, C.; Hernandez M, J. L.; Montes T, J. L.; Castillo M, A.; Ortiz S, J. J., E-mail: raul.perusquia@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2015-09-15

This paper presents the development of tools to facilitate the management so much, the operational monitoring of boiling water reactors (BWR) of the nuclear power plant of Laguna Verde (NPP-LV) through independent codes, and how to carry out the static calculations corresponding to process of optimized pre-design of the reference cycle next to current cycle. The progress and preliminary results obtained with the program SACal, developed at Instituto Nacional de Investigaciones Nucleares (ININ), central tool to achieve provide a management platform of the operational monitoring and pre-design of NPP-LV cycle are also described. The reached preliminary advances directed to get an Analysis center and automated design of fuel assembly cells are also presented, which together with centers or similar modules related with the fuel reloads form the key part to meet the targets set for the realization of a Management Platform of Nuclear Fuel of the NPP-LV. (Author)

The Laguna Verde Central by it results in maintenance and operation consolidates it position of world class enterprise

International Nuclear Information System (INIS)

Rivera C, A.

2008-01-01

This work has the objective of showing the results of the Laguna VerdeCentral in the maintenance and the operation that in the short term the generation of electricity in Mexico by nuclear means is a viable option, in virtue of their positioning like Company of World Class, when winning March 25, 2008 the National Prize of Quality with the more high qualification in the history of this prize, same that allows us to be very optimistic in increasing the possibility to that the Nuclear Industry in Mexico grows. The focus of the comparative graphs, with official data of the Comision Federal de Electricidad (CFE), it is so that it is observed that the Laguna Verde Central is above those the other types of generation like they are the Coal power stations, Thermoelectric, Hydroelectric, likewise they can see that we are for up of the Independent Producers of Energy. The information of the electric power generation is presented by reactors nuclear at world level that is growing, in having 31 Generating Units in the construction process that favors the decisions making in the Government federal, likewise contributed data of the increment projected for 2016 in the country of 380,102 GWh that equivalent to 63% of growth, where it exists without place to doubts a good opportunity for the nucleoelectricity. The Investment Works Program of Public Sector (POISE), it shows the information that 6,178 Mwe will be installed settled of a Non-defined Technology in Mexico, information that specifies the opportunity to be a viable option, because the one Plant Factor, the Production of Electric power, and the Variable Cost of Production, the energy generation by nuclear means is the more competitiveness. Finally this work stood out the effort that communitary works are developed to benefit to the society and the environment to be one Viable option not only for their high performance, or competitive for those more low costs, but also to improve the public opinion with the sustainable

Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II; Revision de documentos guia para obtener la renovacion de licencia de la Central Nuclear Laguna Verde Unidades 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Jarvio C, G. [ININ 52750 La Marquesa, Estado de Mexico (Mexico); Fernandez S, G. [CFE, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin s/n (Km. 7.5), Dos Bocas, 54270 Veracruz (Mexico)]. e-mail: giarvio@yahoo.com.mx

2008-07-01

Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

Methodology of aging management in structures, systems and components of a nuclear power plant and its application to a pilot program in Laguna Verde

International Nuclear Information System (INIS)

Jarvio C, G.; Fernandez S, G.

2009-10-01

From its origin the nuclear power plants confront the effects of time and of environment, giving as result the aging of its structures, systems and components. In this document the general process is described for the establishment of Aging Management Program developed by IAEA. Following the program methodology is guaranteed that a nuclear power plant manages the aging effects appropriately and to make decisions for its solution, assuring the characteristic functions of structures, systems and components of same nuclear power plant. On the other hand, the implantation of an aging management program constitutes the base for development of a licence renovation program, like it can be the specific case of the Central Laguna Verde Units 1 and 2. (Author)

Study and characterization of noble metal deposits on similar rusty surfaces to those of the reactor U-1 type BWR of nuclear power station of Laguna Verde

International Nuclear Information System (INIS)

Flores S, V. H.

2011-01-01

In the present investigation work, were determined the parameters to simulate the conditions of internal oxidation reactor circulation pipes of the nuclear power plant of Laguna Verde in Veracruz. We used 304l stainless steel cylinders with two faces prepared with abrasive paper of No. 600, with the finality to obtain similar surface to the internal circulation piping nuclear reactor. Oxides was formed within an autoclave (Autoclave MEX-02 unit B), which is a device that simulates the working conditions of the nuclear reactor, but without radiation generated by the fission reaction within the reactor. The oxidation conditions were a temperature of 280 C and pressure of 8 MPa, similar conditions to the reactor operating in nuclear power plant of Laguna Verde in Veracruz, Mexico (BWR conditions), with an average conductivity of 4.58 ms / cm and 2352 ppb oxygen to simulate normal water chemistry NWC. Were obtained deposits of noble metal oxides formed on 304l stainless steel samples, in a 250 ml autoclave at a temperature range of 180 to 200 C. The elements that were used to deposit platinum-rhodium (Pt-Rh) with aqueous Na 2 Pt (OH) 6 and Na 3 Rh (NO 2 ) 6 , Silver (Ag) with an aqueous solution of AgNO 3 , zirconium (Zr) with aqueous Zr O (NO 3 ) and ZrO 2 , and zinc (Zn) in aqueous solution of Zn (NO 3 ) 2 under conditions of normal water chemistry. Also there was the oxidation of 304l stainless steel specimens in normal water chemistry with a solution of Zinc (Zn) (NWC + Zn). Oxidation of the specimens in water chemistry with a solution of zinc (Zn + NWC) was prepared in two ways: within the MEX-02 autoclave unit A in a solution of zinc and a flask at constant temperature in zinc solution. The oxides formed and deposits were characterized by scanning electron microscopy, energy dispersive X-ray analysis, elemental field analysis and X-ray diffraction. By other hand was evaluated the electrochemical behavior of the oxides formed on the surface of 304l stainless steel

Licensing process of the digital application: Nuclear measurement analysis and control power range neutron monitor (NUMAC-PRNM) system for their implementation in the Laguna Verde NPP unit 2

International Nuclear Information System (INIS)

Ledesma-Carrion, R.; Hernandez-Cortes, A.

1998-01-01

This paper describe the licensing process performed by the Mexican Regulatory Commission (CNSNS) for the NUclear Measurement Analysis and Control-Power Range Neutron Monitor (NUMAC-PRNM) system, which sends trip signals to the Reactor Protection System (RPS), and has been implemented in the Laguna Verde Nuclear Power Plant Unit (LVNPP-U2) before its first fuel loading. The review and approval process was performed with the advise role of the United States of America Nuclear Regulatory Commission (USNRC): the regulatory frame applied includes the Code of Federal Regulation, some Regulatory Guides and some Industrial Standards. The evaluation covered topics related with the software, hardware and firmware specifications, design, tests, training, maintenance and operational experience. After the revision of these topics, the NUMAC-PRNM was approved through the CNSNS Safety Evaluation Report (SER) and then installed in the LVNPP-U2. This paper include a description of the regulatory requirements to this digital application, the safety concerns involved, the compliance to these requirements by the utility and the results of the CNSNS evaluation, mentioning the experience acquired during the process and the method used to perform the evaluation. Additionally, the interface between the designer-vendor, the utility and the regulatory body during the licensing process is commented. Finally, the conclusion is presented, taking into account the operational experience of the NUMAC applications implemented in the LVNPP. It also gives the future regulatory tasks related to the assessment of digital performance equipment and upgrades. (author)

Simulation of the steady state of the Laguna Verde Nuclear power station at full power (1931 MWt and 2027 Mwt) with the SCDAPSIM code

International Nuclear Information System (INIS)

Amador G, R.; Nunez C, A.; Mateos, E. del A.

2001-01-01

This document describes two models developed for the Laguna Verde Nuclear Power Station (LVNPP) using SCDAPSIM computer code. These models represent the LVNPP in normal operation with a nominal power of 1931 MWt and power uprate conditions of 2027 MWt. The steady states obtained by means of these models comply with the criteria established by the ANSI/ANS-3.5-1985 for nuclear power plant simulators. This criteria has been applied to the models of the LVNPP developed by CNSNS in want of some international accepted criteria for ''Best Estimation'' computer codes. These models will be the bases to carry out studies of validation of the own models as well as the analysis of diverse scenarios that evolve to a severe accident. (Author)

Genetic structure of populations of Drosophila melanogaster natives from Laguna Verde, Veracruz; Estructura genetica de poblaciones de Drosophila melanogaster originarias de Laguna Verde, Veracruz

Energy Technology Data Exchange (ETDEWEB)

Salceda, V M [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2005-07-01

The genetic variability hidden present in natural populations of Drosophila melanogaster, it has been broadly analyzed, and it is a tool that allows to detect differences among the different populations of this species, so much of natural nature as experimental. In this occasion we use it to see if differences exist in two neighboring populations inside the Laguna Verde nuclear power plant, Veracruz, and this way to suggest, of having differences in the mount of the relative frequencies of lethal genes, semi lethals and normal, be due to the radioactive emanations product of the reactors operation of the plant. Its were took samples of flies in both towns during three successive seasons and they were transported to the laboratory of the ININ where they were carried out the tests to determine the frequency of the different types of genes. This was made by means of the denominated technique C y L / Pm that allows by means of a cross series with a stump marker to obtain, in the third generation, in isolated form the different types of genes and this way to calculate their relative frequencies. The study understands the analysis of 299 chromosomes extracted from the populations, of those that 95 correspond at the control population and 204 to the experimental one. As a result of the analysis we find that 30.52 percent of the genes of the population witness contains detrimental genes (sum of the lethal plus the semi lethal genes) as long as in the experimental population this value corresponds to 23.03 percent. In accordance with this information was not significant difference among the studied populations. A similar analysis, but now comparing the seasons, (summer against winter), it showed significant difference to 5% with regard to the lethal genes frequency only in the population witness. These results indicate the absence of damage, however it is necessary to consider that this can be due to that indeed there is not him or that the investigation protocol is not

Implementation of the project of equipment reliability in the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Rios O, J. E.; Martinez L, A. G.

2008-01-01

A equipment is reliable if it fulfills the function for which was designed and when it is required. To implement a project of reliability in a nuclear power plant this associate to a process of continuous analysis of the operation, of the conditions and faults of the equipment. The analysis of the operation of a system, of the equipment of the same faults and the parts that integrate to equipment take to identify the potential causes of faults. The predictive analysis on components and equipment allow to rectify and to establish guides to optimize the maintenance and to guarantee the reliability and function of the same ones. The reliability in the equipment is without place to doubts a wide project that embraces from the more small component of the equipment going by the proof of the parts of reserve, the operation conditions until the operative techniques of analysis. Without place of doubt for a nuclear power plant the taking of decisions based on the reliability of their systems and equipment will be the appropriate for to assure the operation and reliability of the same one. In this work would appear the project of reliability its processes, criteria, indicators action of improvement and the interaction of the different disciplines from the Nuclear Power Plant of Laguna Verde like a fundamental point for it put in operation. (Author)

Fuel management inside the reactor. Report of generation of the nuclear bank for the fuel of the initial load of the Laguna Verde U-1 reactor with the FMS codes; Administracion de combustible dentro del reactor. Reporte de generacion del banco nuclear para el combustible de la carga inicial del reactor de Laguna Verde U-1 con los codigos del FMS

Energy Technology Data Exchange (ETDEWEB)

Alonso V, G. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Torres A, C. [CFE, Veracruz (Mexico)

1991-06-15

In this work in a general way the form in that it was generated the database of the initial fuel load of the Laguna Verde Unit 1 reactor is described. The initial load is formed with fuel of the GE6 type. The obtained results during the formation of the database in as much as to the behavior of the different cell parameters regarding the one burnt of the fuel and the variation of vacuums in the coolant channel its are compared very favorably with those reported by the General Electric fuel supplier and reported in the design documents of the same one. (Author)

Planning of activities in the Laguna Verde Central planning at 12 weeks

International Nuclear Information System (INIS)

Chimalpopoca, C.

2007-01-01

The universe of works that are carried out in a nuclear facility to maintain effective the structures, systems and components require of a continuous analysis, in the order of the maintenance frequencies that can be of the preventive, predictive or corrective type. Each component is associated to reserve parts, readiness of systems, in fulfillment to the operation technical specifications, to the environment of the one work; each component requires of a planning level, where it is distinguished with clarity when they are executed, in the operation stage, stop or recharge. This work has as end to show like the activities are planned during the operation, using planning methods to twelve weeks, where the reach of the task is conceptualized, operative requirements, of reserve parts, of the work environment analysis, of those radiological conditions, of the authorizations for their execution, the same execution and the evaluation post work like a technique to maintain in continuous improvement the tasks of the maintenance of the Units of the Power station. A motor valve to be worked in its internals requires access to the work point, it requires bill of the system, electric disconnection, maneuvers to disassemble actuators and retirement of thermal isolation if it applies, reserve parts of the caps joints, control mechanisms, personal, tools, radiological control. The success of the continuous operation of a power station is in the planning quality, the attention of each one of the details to assure that the components, structures and components stay effective to make their function when they are demanded. The planning task requires of experience and knowledge of each some of the components, the task of planning of activities and its execution is multidisciplinary This work has that purpose, to show the planning tools in the Laguna Verde Nuclear Power station, under the concept of twelve weeks. (Author)

Analysis of the evolution of reactivity of the event at 24/01/1995 of the BWR U-1 of Laguna Verde; Analisis de la evolucion de la reactividad del evento del 24/01/1995 del BWR U-1 de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Ruiz E, J.A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Blazquez M, J. [CIEMAT, 28040 Madrid (Spain)]. e-mail: jare@nuclear.inin.mx

2003-07-01

In this work it is looked for, to calculate the reactivity starting from the measures of the one nuclear detection system denominated by their initials in English 'APRM' (Average Power Range Monitor) of the oscillatory event of the unit 1 of the nuclear power station of Laguna Verde happened the 24/01/1995. The reference signal consists of 3589 points taken every 0.2 seconds before the reactor operator carried out the cut of the same one. It is tried to give answer to queries like: When the event really began?, How distinguishing the stable part of the unstable? Which could be the way of predicting it?. The analysis is developed applying the call 'inverse method', with the purpose of interpreting the power response, having a mean of obtaining the information about the changes of reactivity that were given in the transitory one and to look their relationship with the actions taken by the operator. A comparison of the variation of the signal of reactivity with basic statistical variables with the purpose of trying of to find a mechanism for early detection of the instability is included. (Author)

Analysis of a natural draught tower in the circulation seawater system of nuclear power plant of Laguna Verde; Analisis de una torre de tiro natural en el sistema de agua de circulacion de mar de la central nucleoelectrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

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

2009-10-15

The analysis of a natural draught tower in open circuit for the cooling system of seawater circulation on the nuclear power plant of Laguna Verde, it is based on conditions of 2027 MWt and 2317 MWt, where the flows of circulation water system hardly vary and whose purpose will be, to cool the seawater circulation. The circulation water system is used as heat drain in main condenser of turbo generator to condense the nuclear vapor. The annual average temperature in the seawater at present is of 26 C to the entrance to circulation water system and it is vary in accordance with the time of year. The mean temperature of leaving of circulation water system to the sea is of 41 C. Having a cooling tower to reduce the entrance temperature to the circulation water system, it improves the efficiency of thermal transfer in condenser, it improves the vacuum in condenser giving more operative margin to avoid condenser losses by air entrances and nuclear power plant shutdowns, as well as for to improve the efficiency of operative balance of nuclear power plant, also it prevents the impact in thermal transfer efficiency in condenser by the climatic change. (Author)

Optimization of reloading Laguna Verde Central U1/U2, Federal Electricity Commission

International Nuclear Information System (INIS)

Espinosa G, J.M.

2006-01-01

The Laguna Verde Central from the beginning of the commercial operation settled down as maximum priority 'the total safety in its operation' taking in consideration the so much experience of the good operation and of multiple recharges made in a sure and reliable way, and without separate us of the safety mystic of the CLV, but looking for to be better every day a new challenge it settled down 'to compare us with the best plants in the world' and certainly to work to classify us like one of them. For this we established a 4.0 year old plan (2003/2006) for the effectiveness all the processes in the power station that allowed us to measure our acting with the same parameters that settle down at international level (nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station, attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect, summing up means to be good in all the aspects). All the above mentioned would allow us to qualify us as level 1 of WANO (world proprietors association of nuclear centrals) at the end of the year 2006 and to pass to be part of this select group. After analyzing the acting record of the power station, evaluating our technical and economic capacity, the location of the installation besides revising the international experiences was defined that one of the concepts that impact considerably so much to the capacity factors and availability besides the dose and production cost is the duration of the recharge periods, for this reason the present work is elaborated. (Author)

Preliminary evaluation of the profitability indexes of the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Villanueva M, C.

2010-10-01

The Laguna Verde nuclear power plant of the Federal Commission of Electricity has an installed capacity of 1,350 MW and unit 1 started commercial operation in 1990 and unit 2 in 1995. This paper is a synthesis of the results of a preliminary evaluation of the expected profitability indexes of the power plant during an economic lifetime of 40 years. The following data was used as input to the evaluation model prescribed by the Finance and Public Credit Secretary for public investment projects. Unit investment cost: 3,500 US D/k W; Fixed operation and maintenance cost: 54. 45 US D/year-k W; Variable operation and maintenance cost: 0. 38 US D/M Wh; Nuclear fuel cycle cost: 10. 28 US D/M Wh; Lifetime capacity factor: 85%; Discount rate: 12.0% per year; Sale price of electricity to the interconnected electric system: 80. 75 US D/M Wh. The output of the evaluation model is the following: Cost of electricity generated: 60. 2 1 US D/M Wh; fixed cost 49. 55 US D/M Wh; variable cost 10. 66 US D/M Wh; Internal rate of return (Irr): 18.0%; Benefit to cost quotient (B/C): 1.341. A very systematic sensitivity analysis was done, that shows that the cost is very sensitive to the capacity factor and to the investment cost, but is very insensitive to the fixed operation and maintenance cost and to the nuclear fuel cost. Finally, a comparison was made to the evaluation of the profitability indexes of a natural gas fired combined cycle power plant. (Author)

Analysis of a natural draught tower in the circulation seawater system of nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Tijerina S, F.; Vargas A, A.

2009-10-01

The analysis of a natural draught tower in open circuit for the cooling system of seawater circulation on the nuclear power plant of Laguna Verde, it is based on conditions of 2027 MWt and 2317 MWt, where the flows of circulation water system hardly vary and whose purpose will be, to cool the seawater circulation. The circulation water system is used as heat drain in main condenser of turbo generator to condense the nuclear vapor. The annual average temperature in the seawater at present is of 26 C to the entrance to circulation water system and it is vary in accordance with the time of year. The mean temperature of leaving of circulation water system to the sea is of 41 C. Having a cooling tower to reduce the entrance temperature to the circulation water system, it improves the efficiency of thermal transfer in condenser, it improves the vacuum in condenser giving more operative margin to avoid condenser losses by air entrances and nuclear power plant shutdowns, as well as for to improve the efficiency of operative balance of nuclear power plant, also it prevents the impact in thermal transfer efficiency in condenser by the climatic change. (Author)

HVAC system modernization and implementation of a new chilled water system; Modernizacion del Sistema de HVAC e implantacion de un nuevo Sistema de Agua Enfriada de CNLV

Energy Technology Data Exchange (ETDEWEB)

Jodlowiec, D.; Perez-Guilarte Moreno, C.

2011-07-01

Iberdrola Engineering and Construction managed the implementation of a new ventilation system and cooling in the turbine building at the Laguna Verde NPP, fundamental systems to maintain optimum environmental conditions within the same, to improve and ensure the smooth operation of all electrical equipment, contributing to the achievement of increased power to 120%.

HVAC system modernization and implementation of a new chilled water system

International Nuclear Information System (INIS)

Jodlowiec, D.; Perez-Guilarte Moreno, C.

2011-01-01

Iberdrola Engineering and Construction managed the implementation of a new ventilation system and cooling in the turbine building at the Laguna Verde NPP, fundamental systems to maintain optimum environmental conditions within the same, to improve and ensure the smooth operation of all electrical equipment, contributing to the achievement of increased power to 120%.

Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II

International Nuclear Information System (INIS)

Jarvio C, G.; Fernandez S, G.

2008-01-01

Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

Analysis of the micro-structural damages by neutronic irradiation of the steel of reactor vessels of the nuclear power plant of Laguna Verde. Characterization of the design steel; Analisis de los danos micro-estructurales por irradiacion neutronica del acero de la vasija de los reactores de la Central Nuclear de Laguna Verde. Caracterizacion del acero de diseno

Energy Technology Data Exchange (ETDEWEB)

Moranchel y Rodriguez, M.; Garcia B, A. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Fisica, Av. Luis Enrique Erro s/n, Unidad Profesional Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: mmoranchel@ipn.m [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2010-09-15

The vessel of a nuclear reactor is one of the safety barriers more important in the design, construction and operation of the reactor. If the vessel results affected to the grade of to have fracture and/or cracks it is very probable the conclusion of their useful life in order to guarantee the nuclear safety and the radiological protection of the exposure occupational personnel, of the public and the environment avoiding the exposition to radioactive sources. The materials of the vessel of a nuclear reactor are exposed continually to the neutronic irradiation that generates the same nuclear reactor. The neutrons that impact to the vessel have the sufficient energy to penetrate certain depth in function of the energy of the incident neutron until reaching the repose or to be absorbed by some nucleus. In the course of their penetration, the neutrons interact with the nuclei, atoms, molecules and with the same crystalline nets of the vessel material producing vacuums, interstitial, precipitate and segregations among other defects that can modify the mechanical properties of the steel. The steel A533-B is the material with which is manufactured the vessel of the nuclear reactors of nuclear power plant of Laguna Verde, is an alloy that, among other components, it contains atoms of Ni that if they are segregated by the neutrons impact this would favor to the cracking of the same vessel. This work is part of an investigation to analyze the micro-structural damages of the reactor vessels of the nuclear power plant of Laguna Verde due to the neutronic irradiation which is exposed in a continuous way. We will show the characterization of the design steel of the vessel, what offers a comprehension about their chemical composition, the superficial topography and the crystalline nets of the steel A533-B. It will also allow analyze the existence of precipitates, segregates, the type of crystalline net and the distances inter-plains of the design steel of the vessel. (Author)

Multivariate analysis in the frequency mastery applied to the Laguna Verde Central; Analisis multivariable en el dominio de la frecuencia aplicado a la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Castillo D, R.; Ortiz V, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Calleros M, G. [CFE, Central Nucleoelectrica de Laguna Verde, carretera Nautla-Cardel Km. 42.5, Alto Lucero, Veracruz (Mexico)]. e-mail: rcd@nuclear.inin.mx

2006-07-01

The noise analysis is an auxiliary tool in the detection of abnormal operation conditions of equipment, instruments or systems that affect to the dynamic behavior of the reactor. The spectral density of normalized power has usually been used (NPSD, by its initials in English), to watch over the behavior of some components of the reactor, for example, the jet pumps, the recirculation pumps, valves of flow control in the recirculation knots, etc. The behavior change is determined by individual analysis of the NPSD of the signals of the components in study. An alternative analysis that can allow to obtain major information on the component under surveillance is the multivariate autoregressive analysis (MAR, by its initials in English), which allows to know the relationship that exists among diverse signals of the reactor systems, in the time domain. In the space of the frequency, the relative contribution of power (RPC for their initials in English) it quantifies the influence of the variables of the systems on a variable of interest. The RPC allows, therefore that for a peak shown in the NPSD of a variable, it can be determine the influence from other variables to that frequency of interest. This facilitates, in principle, the pursuit of the important physical parameters during an event, and to study their interrelation. In this work, by way of example of the application of the RPC, two events happened in the Laguna Verde Central are analyzed: the rods blockade alarms by high scale in the monitors of average power, in which it was presents a power peak of 12% of width peak to peak, and the power oscillations event. The main obtained result of the analysis of the control rods blockade alarm event was that it was detected that the power peak observed in the signals of the average power monitors was caused by the movement of the valve of flow control of recirculation of the knot B. In the other oscillation event the results its show the mechanism of the oscillation of

Fuel management inside the reactor. Report of generation of the nuclear bank for the fuel of the initial load of the Laguna Verde U-1 reactor with the FMS codes

International Nuclear Information System (INIS)

Alonso V, G.; Torres A, C.

1991-06-01

In this work in a general way the form in that it was generated the database of the initial fuel load of the Laguna Verde Unit 1 reactor is described. The initial load is formed with fuel of the GE6 type. The obtained results during the formation of the database in as much as to the behavior of the different cell parameters regarding the one burnt of the fuel and the variation of vacuums in the coolant channel its are compared very favorably with those reported by the General Electric fuel supplier and reported in the design documents of the same one. (Author)

Analysis of the preliminary trajectory of emergency venting of the nuclear power plant of Laguna Verde using RELAP5

International Nuclear Information System (INIS)

Cecenas F, M.; Jimenez S, R.; Ovando C, R.; Tijerina S, F.; Tapia M, R. N.

2016-09-01

For a commercial nuclear plant, the availability of a vent line to the atmosphere is an improvement to achieve the prevention and mitigation of the consequences of a severe accident. The importance of this system received greater attention after the Fukushima accident in 2011. Subsequently, in 2012 and 2013, the United States Nuclear Regulatory Commission issued documents stating that the venting must be able to dislodge 1% of the rated thermal power of the core without over pressurizing the primary container. To analyze the venting of the nuclear power plant of Laguna Verde, the line and the primary container are modeled using the thermo-hydraulic code RELAP5, simulating a release of 1% of the nominal licensed power to the container in the form of saturated steam. The vent has no problem to evacuate the energy and manages to keep the container without exceeding its design limit, and the highest percentage of thermal power that can channel the vent to the outside is approximately 3%. A sensitivity analysis increasing the diameter of the line to 14 inches allows increasing in 10% the percentage of power that can be vented to the outside without problem for the containment. (Author)

Actinides inventory of the nuclear power plant of Laguna Verde Unit 1

International Nuclear Information System (INIS)

Martinez C, E.; Ramirez S, J. R.; Alonso V, G.

2013-10-01

At the present time 435 nuclear power reactors exist for the electricity generation operating in the world and 63 in construction. Mexico has two reactors type BWR in the nuclear power plant of Laguna Verde. The nuclear fuel that is used in the nuclear reactors is retired of the reactor core when the energy that this contained has been extracted. This used fuel is known as spent nuclear fuel, the problem with this fuel is that was irradiated inside the reactor and continuous emitting a high radiation, as well as a significant heat quantity when being extracted, for what is necessary to maintain it in cooling and with some shielding to be protected of the radiation that emits. This objective is achieved confining the fuel in the spent nuclear fuel pool, where it is cooled and the same pool provides the necessary shielding to maintain the surroundings in safety radiation levels for the personnel that work in the power plant. An inconvenience of the pools is its limited storage capacity and that after certain time is necessary to remove the fuel, according to the established regulation to continue operating. To correct this inconvenience, two alternatives of spent fuel disposition exist, 1) the final disposition in deep geologic repositories and 2) the reprocessing and recycled of spent fuel. Each alternative presents its particularities and specific problems; however taking many years to be able to implement anyone of them. To carry out the second option, is indispensable to estimate the total mass of actinides generated in the spent nuclear fuel, that which represents to develop a methodology for it, this action is the main purpose of the present work. Inside our calculation method was necessary to appeal to diverse computation tools as the codes Origin-S and Keno V.a. Later on the obtained were compared with a problem type Benchmark, being obtained a smaller absolute error to 1.0%. (Author)

Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde; Estudio de ruido ambiental en una planta BWR como la Central Nuclear Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Tijerina S, F.; Cruz G, M.; Amador C, C., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Cardel-Nautla Km. 42.5, Alto Lucero, Veracruz (Mexico)

2013-10-15

In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

Development of a methodology for the economical analysis of fuel cycles, application to the Laguna Verde central; Desarrollo de una metodologia para el analisis economico de ciclos de combustible, aplicacion a la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Malfavon, S.M.; Trejo, M.G.; Hernandez, H. [FI-UNAM, 04500 Mexico D.F. (Mexico); Francois, J.L.; Ortega, R.F. [FI-UNAM, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)

2003-07-01

In this work a methodology developed to carry out the economical analysis of the fuel cycle of a nuclear reactor is presented. The methodology was applied to the Laguna Verde Nuclear Power Station (CNLV). The design of the reload scenarios of the CNLV are made with the Core Master Presto code (CM-Presto), three-dimensional simulator of the reactor core, the launched data by this, as well as the information of the Energy use plan (PUE), it allowed us to obtain reliable results through the fitness of an algorithm of economic calculation that considers all the components of the fuel cycle to present worth. With the application of the methodology it was obtained the generated energy, as well as their respective cost of each sub lot type of assemblies by operation cycle, from the start-up of the CNLV until September 13, 2002. Using the present worth method its were moved all the values at November 5, 1988, date of operation beginning. To the final of the analysis an even cost of 6.188 mills/kWh was obtained for those first 9 cycles of the Unit 1 of the CNLV, being observed that the costs of those first 3 operation cycles are the more elevated. Considering only the values starting from the cycle 4, the levelled cost turns out to be of 5.96 mills/kWh. It was also obtained the cost by fuel lot to evaluate the performance of assemble with the same physical composition. (Author)

Rehabilitation and modernization project of units 1 and 2 of Laguna Verde Nuclear Power Plant. A strengthening project to 120%. (2nd phase); Proyecto de rehabilitacion y modernizacion de las Unidades 1and 2 de la CNLV. Un proyecto de reponteciacion al 120% (2ª Fase)

Energy Technology Data Exchange (ETDEWEB)

Liebana, B.; Merino, A.; Garcia, J. L.; Gomez, M.; Martinez, I.; Ruiz, L.

2010-07-01

The power increase of the Laguna Verde Nuclear Power Plant is a project for the rehabilitation and modernization of the turbo and associated equipment to get an increase of its power and of its service life. The project scope includes the design, the engineering, the equipment supply, the installation, the testing and the commissioning. This article presents the work of the second phase.

Estimation of seismic return periods in the Laguna Verde nuclear plant; Estimacion de periodos de retorno sismico en la PNLV

Energy Technology Data Exchange (ETDEWEB)

Flores R, J.H

1992-01-15

The study of seismic risk in the area of the Laguna Verde Nucleo electric plant (PNLV) and its surroundings, one carries out estimating the different return periods and the occurrence probability in different intervals of time (5, 75, 100, 125, 150 years starting from the distribution of first type of Gumbel (G1) of extreme values (Burton, 1986), the value that was used to evaluate the useful life of the PNLV was of 50 years, the other periods will be occupy to evaluate 'temporal' nuclear cemeteries, that is to say for diminish the radioactive activity of the fuel assemblies already burned in the reactor pool or in a near place to the place. The seismic data that were used for the analysis were of the seismic catalog that it was elaborated from (1920-1982), around the place whose seismic half magnitude was of 5 grades Richter and a depth 65 km, these earthquakes are classified as shallow earthquakes, which are located in the continental plaque of North-America, these they are induced by the efforts of push of the plaque of Cocos, existing 36% of intermediate and 2 of deep earthquakes. (Author)

Estimation of seismic return periods in the Laguna Verde nuclear plant; Estimacion de periodos de retorno sismico en la PNLV

Energy Technology Data Exchange (ETDEWEB)

Flores R, J H

1992-01-15

The study of seismic risk in the area of the Laguna Verde Nucleo electric plant (PNLV) and its surroundings, one carries out estimating the different return periods and the occurrence probability in different intervals of time (5, 75, 100, 125, 150 years starting from the distribution of first type of Gumbel (G1) of extreme values (Burton, 1986), the value that was used to evaluate the useful life of the PNLV was of 50 years, the other periods will be occupy to evaluate 'temporal' nuclear cemeteries, that is to say for diminish the radioactive activity of the fuel assemblies already burned in the reactor pool or in a near place to the place. The seismic data that were used for the analysis were of the seismic catalog that it was elaborated from (1920-1982), around the place whose seismic half magnitude was of 5 grades Richter and a depth 65 km, these earthquakes are classified as shallow earthquakes, which are located in the continental plaque of North-America, these they are induced by the efforts of push of the plaque of Cocos, existing 36% of intermediate and 2 of deep earthquakes. (Author)

NucleoRed - Computerized system for increasing the effectiveness of the technical administrative conduct of the Laguna Verde Central; NucleoRed - Sistema computarizado para incrementar la efectividad de la gestion tecnico-administrativa de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Luna D, J. [Central Nucleoelectrica Laguna Verde, Carretera cardel-Nautla Km. 42.5 Veracruz (Mexico)]. e-mail: jluna@cfe.gob.mx

2003-07-01

The on-line systems for the management of the Laguna Verde Central (CLV) have had the challenge to evolve from the PC's of first generation until emigrate to the new Internet technologies, so that they allow to the diverse work groups to have the computer tool that allows them to gather the necessary data and to carry out efficiently the analysis of their results. To confront the previous challenge, in the CLV it has been developed and implemented the Nucleo Red that is an on-line system with the objective of providing in it lines strategic information for the Technician-administrative management of the plant in the nuclear context. The Nucleo Red is the computational tool that reflects the technical administrative processes implemented by personnel of the different Operative departments, it seeks to cooperate to the reliable and efficient operation of the first nucleo electric central of Mexico, with technology and Mexican personnel the one which already it had received international recognitions. The perspective of this computer system is to continue inside the process of continuous improvement and that although it was designed for a nucleo electric plant it can also be taken to the conventional plants of generation of electric power, so that this technology can be taken advantage of in other non nuclear facilities. The objective of the present work, is to show the new modules that have been developed in the Nucleo Red, its operation in general, and the benefits that it presents its use. (Author)

Analysis of the micro-structural damages by neutronic irradiation of the steel of reactor vessels of the nuclear power plant of Laguna Verde. Characterization of the design steel

International Nuclear Information System (INIS)

Moranchel y Rodriguez, M.; Garcia B, A.; Longoria G, L. C.

2010-09-01

The vessel of a nuclear reactor is one of the safety barriers more important in the design, construction and operation of the reactor. If the vessel results affected to the grade of to have fracture and/or cracks it is very probable the conclusion of their useful life in order to guarantee the nuclear safety and the radiological protection of the exposure occupational personnel, of the public and the environment avoiding the exposition to radioactive sources. The materials of the vessel of a nuclear reactor are exposed continually to the neutronic irradiation that generates the same nuclear reactor. The neutrons that impact to the vessel have the sufficient energy to penetrate certain depth in function of the energy of the incident neutron until reaching the repose or to be absorbed by some nucleus. In the course of their penetration, the neutrons interact with the nuclei, atoms, molecules and with the same crystalline nets of the vessel material producing vacuums, interstitial, precipitate and segregations among other defects that can modify the mechanical properties of the steel. The steel A533-B is the material with which is manufactured the vessel of the nuclear reactors of nuclear power plant of Laguna Verde, is an alloy that, among other components, it contains atoms of Ni that if they are segregated by the neutrons impact this would favor to the cracking of the same vessel. This work is part of an investigation to analyze the micro-structural damages of the reactor vessels of the nuclear power plant of Laguna Verde due to the neutronic irradiation which is exposed in a continuous way. We will show the characterization of the design steel of the vessel, what offers a comprehension about their chemical composition, the superficial topography and the crystalline nets of the steel A533-B. It will also allow analyze the existence of precipitates, segregates, the type of crystalline net and the distances inter-plains of the design steel of the vessel. (Author)

Four stops of fuel reloading with duration of less of 30 days in the Laguna Verde Central; Cuatro paradas de recarga de combustible con duracion de menos de 30 dias en la central laguna verde

Energy Technology Data Exchange (ETDEWEB)

Lozano L, A. [CFE, Central Laguna Verde, Planeacion, Veracruz (Mexico)]. e-mail: agustin.lozano@cfe.gob.mx

2008-07-01

The Laguna Verde Central having established as mission 'With maximum priority in the safety, to generate electricity by nuclear means with competitive quality and cost, sustained in our personnel's continuous overcoming and deep respect to the environment' and respecting our values (safety, responsibility by results, professional integrity, continuous improvement, team work, excellence in the performance, quality of service, protection to the environment its thought about our strategic objectives of the power station being born by this way one of them that it is the improvement program 'reduction of reloading times' looking for to be improves every day comparing us with the best plants of the world effectiveness all the processes in the power station that allowed us to measure our performance with the same parameters that settle down at international level as its are nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect. After analyzing the performance record of the power station, evaluating our technical, economic capacity, the location of the installation besides revising the international experiences was defined that one of the concepts that impact considerably so much to the capacity factors and readiness besides the dose and production cost is the duration of the reloading periods, for this reason work strategies were elaborated to be able to reach our goals of reloading days in less than 30 days, here are formed the carried out actions that they made us complete the four last reloading in less than 30 days. (Author)

Technological evaluation for the extension of the operation license to the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Arganis J, C. R.; Medina A, A. L.

2010-01-01

At the present time one of the tendencies in the nuclear industry is the renovation of operation licenses of the nuclear power plants, with the purpose of prolonging their operation 20 years more than the time settled down in their original license, which is of 30 years for the case of the nuclear power plant of Laguna Verde. This allows the electric power generation for a major period of time and to a relatively low price, giving this way a bigger competitiveness to the power stations of nuclear power. However, to request the license extension of the nuclear power plant requires to get ready the documentation and necessary studies for: to maintain a high level of security, to optimize the operation, maintenance and service life of the structures, systems and components, to maintain an acceptable level of performance, to maximize the recovery of the investment about the service of the nuclear power plant and to preserve the sure conditions for a major operation period at the license time. This paper describes the studies conducted by the Materials Technology Department of the Instituto Nacional de Investigaciones Nucleares (ININ) to substantiate the required documentation for obtaining the extension of operating license of the nuclear power plant. These studies are focused mainly in the reactor pressure vessels of both units, as well as in the deposit of noble metals and the influence of the sludges (crud s) in this deposit. (Author)

Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model; Analisis de viabilidad en la propuesta de expansion de la central nucleoelectrica Laguna Verde: aplicacion de opciones reales, modelo binomial

Energy Technology Data Exchange (ETDEWEB)

Hernandez I, S.; Ortiz C, E.; Chavez M, C., E-mail: lunitza@gmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

2011-11-15

At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

Analysis of the evolution of reactivity of the event at 24/01/1995 of the BWR U-1 of Laguna Verde

International Nuclear Information System (INIS)

Ruiz E, J.A.; Blazquez M, J.

2003-01-01

In this work it is looked for, to calculate the reactivity starting from the measures of the one nuclear detection system denominated by their initials in English 'APRM' (Average Power Range Monitor) of the oscillatory event of the unit 1 of the nuclear power station of Laguna Verde happened the 24/01/1995. The reference signal consists of 3589 points taken every 0.2 seconds before the reactor operator carried out the cut of the same one. It is tried to give answer to queries like: When the event really began?, How distinguishing the stable part of the unstable? Which could be the way of predicting it?. The analysis is developed applying the call 'inverse method', with the purpose of interpreting the power response, having a mean of obtaining the information about the changes of reactivity that were given in the transitory one and to look their relationship with the actions taken by the operator. A comparison of the variation of the signal of reactivity with basic statistical variables with the purpose of trying of to find a mechanism for early detection of the instability is included. (Author)

Multivariate analysis in the frequency mastery applied to the Laguna Verde Central

International Nuclear Information System (INIS)

Castillo D, R.; Ortiz V, J.; Calleros M, G.

2006-01-01

The noise analysis is an auxiliary tool in the detection of abnormal operation conditions of equipment, instruments or systems that affect to the dynamic behavior of the reactor. The spectral density of normalized power has usually been used (NPSD, by its initials in English), to watch over the behavior of some components of the reactor, for example, the jet pumps, the recirculation pumps, valves of flow control in the recirculation knots, etc. The behavior change is determined by individual analysis of the NPSD of the signals of the components in study. An alternative analysis that can allow to obtain major information on the component under surveillance is the multivariate autoregressive analysis (MAR, by its initials in English), which allows to know the relationship that exists among diverse signals of the reactor systems, in the time domain. In the space of the frequency, the relative contribution of power (RPC for their initials in English) it quantifies the influence of the variables of the systems on a variable of interest. The RPC allows, therefore that for a peak shown in the NPSD of a variable, it can be determine the influence from other variables to that frequency of interest. This facilitates, in principle, the pursuit of the important physical parameters during an event, and to study their interrelation. In this work, by way of example of the application of the RPC, two events happened in the Laguna Verde Central are analyzed: the rods blockade alarms by high scale in the monitors of average power, in which it was presents a power peak of 12% of width peak to peak, and the power oscillations event. The main obtained result of the analysis of the control rods blockade alarm event was that it was detected that the power peak observed in the signals of the average power monitors was caused by the movement of the valve of flow control of recirculation of the knot B. In the other oscillation event the results its show the mechanism of the oscillation of

Genetic structure of populations of Drosophila melanogaster natives from Laguna Verde, Veracruz

International Nuclear Information System (INIS)

Salceda, V.M.

2005-01-01

The genetic variability hidden present in natural populations of Drosophila melanogaster, it has been broadly analyzed, and it is a tool that allows to detect differences among the different populations of this species, so much of natural nature as experimental. In this occasion we use it to see if differences exist in two neighboring populations inside the Laguna Verde nuclear power plant, Veracruz, and this way to suggest, of having differences in the mount of the relative frequencies of lethal genes, semi lethals and normal, be due to the radioactive emanations product of the reactors operation of the plant. Its were took samples of flies in both towns during three successive seasons and they were transported to the laboratory of the ININ where they were carried out the tests to determine the frequency of the different types of genes. This was made by means of the denominated technique C y L / Pm that allows by means of a cross series with a stump marker to obtain, in the third generation, in isolated form the different types of genes and this way to calculate their relative frequencies. The study understands the analysis of 299 chromosomes extracted from the populations, of those that 95 correspond at the control population and 204 to the experimental one. As a result of the analysis we find that 30.52 percent of the genes of the population witness contains detrimental genes (sum of the lethal plus the semi lethal genes) as long as in the experimental population this value corresponds to 23.03 percent. In accordance with this information was not significant difference among the studied populations. A similar analysis, but now comparing the seasons, (summer against winter), it showed significant difference to 5% with regard to the lethal genes frequency only in the population witness. These results indicate the absence of damage, however it is necessary to consider that this can be due to that indeed there is not him or that the investigation protocol is not

Preliminary analysis of an hydrogen generator system based on nuclear energy in the Laguna Verde site; Analisis preliminar de un sistema generador de hidrogeno basado en energia nuclear en el sitio de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Flores y Flores, A [FI-UNAM, 04500 Mexico D.F. (Mexico); Francois L, J L [FI-UNAM, Jiutepec, Morelos (Mexico)

2003-07-01

The shortage of fossil fuels in the next future, as well as the growing one demand of energetics and the high cost of the production of alternating fuels, it forces us to take advantage of to the maximum the fossil fuel with the one which we count and to look for the form of producing alternating fuels at a low cost and better even if these supply sources are reliable and non pollutants. It is intended a solution to the shortage of fuel; to use the thermal energy liberated of some appropriate nuclear reactor to be able to obtain a fuel but clean and relatively cheap as it is the hydrogen. In the first place the methods were looked for to produce hydrogen using thermal energy, later it was analyzed the temperature liberated by the existent nuclear reactors as well as the advanced designs, according to this liberated temperature settled down that the methods but feasible to produce hydrogen its were the one of reformed with water stream of the natural gas (methane) and the other one of the S-I thermochemical cycle, and the nuclear reactors that give the thermal energy for this production they are those of gas of high temperature. Once established the processes and the appropriate reactors, it was analyzed the site of Laguna Verde, with relationship to the free space to be able to place the reactor and the plant producer of hydrogen, as well as the direction in which blow the dominant winds and the near towns to the place, it was carried out an analysis of some explosion of tanks that could store hydrogen and the damage that its could to cause depending from the distance to which its were of the fire. Finally it was carried out an evaluation of capital and of operation costs for those two methods of hydrogen production. (Author)

Three stops of fuel reloading with length of less 30 days in the Laguna Verde Central; Tres paradas de recarga de combustible con duracion de menos de 30 dias en la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Lozano L, A. [Comision Federal de Electricidad, Central Laguna Verde, Subgerencia General de Operacion Planeacion, Veracruz (Mexico)]. e-mail: agustin.lozano@cfe.gob.mx

2007-07-01

The Laguna Verde Central having established as mission 'With maximum priority in the safety, to generate electricity by nuclear means with quality and cost competitive, sustained in our personnel's continuous overcoming and deep respect to the environment' and respecting our values (safety, responsibility by results, professional integrity, continuous improving, team working, excellence in the acting, quality of service, protection to the environment) they thought about our strategic objectives of the power station being born this way one of them that it is the program of improvement 'Reduction of reload times' looking for to be improves every day comparing us with the best plants in the world efficient all the processes in the power station that allowed us to measure our acting with the same parameters that settle down at international level like they are nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect. After analyzing the acting record of the power station, evaluating our technical capacity, economic, the location of the installation besides revising the international experiences it was defined that one of the concepts that impact considerably so much to the capacity and readiness factors besides the dose and production cost is the duration of the reload periods, for this reason they were elaborated work strategies to be able to reach our goal of reload days considered in being able to carry out them in less than 30 days, here the actions carried out that they made us complete the three last reloads in less than 30 days are captured. (Author)

Scenarios simulation of severe accident type small loss of coolant (Loca), with the code MELCOR version 2.1 for the nuclear power plant of Laguna Verde; Simulacion de escenarios de accidente severo tipo perdida de refrigerante (Loca) pequeno, con el codigo MELCOR version 2.1 para la central nucleo-electrica de Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Cardenas V, J.; Mugica R, C. A.; Godinez S, V., E-mail: Jaime.cardenas@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2013-10-15

In this work was carried out the analysis of two scenarios of the accident type with loss of coolant in a recirculation loop for a break with smaller ares to 0.1 ft{sup 2} (4.6 cm{sup 2}), which is classified according to their size like small Loca. The first simulated scenario was a small Loca without action of the emergency coolant injection systems, and the second was a small Loca with only the available system LPCS. This design base accident was taken into account for its relevance with regard to the damage to the core and the hydrogen generation. Was also observed and analyzed the response of the action of the ECCS that depend of the loss of coolant reason and this in turn depends of the size and type of the pipe break. The specified scenarios were simulated by means of the use of MELCOR model for the nuclear power plant of Laguna Verde that has the Comision Nacional de Seguridad Nuclear y Salvaguardias. (Author)

Three stops of fuel reloading with length of less 30 days in the Laguna Verde Central

International Nuclear Information System (INIS)

Lozano L, A.

2007-01-01

The Laguna Verde Central having established as mission 'With maximum priority in the safety, to generate electricity by nuclear means with quality and cost competitive, sustained in our personnel's continuous overcoming and deep respect to the environment' and respecting our values (safety, responsibility by results, professional integrity, continuous improving, team working, excellence in the acting, quality of service, protection to the environment) they thought about our strategic objectives of the power station being born this way one of them that it is the program of improvement 'Reduction of reload times' looking for to be improves every day comparing us with the best plants in the world efficient all the processes in the power station that allowed us to measure our acting with the same parameters that settle down at international level like they are nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect. After analyzing the acting record of the power station, evaluating our technical capacity, economic, the location of the installation besides revising the international experiences it was defined that one of the concepts that impact considerably so much to the capacity and readiness factors besides the dose and production cost is the duration of the reload periods, for this reason they were elaborated work strategies to be able to reach our goal of reload days considered in being able to carry out them in less than 30 days, here the actions carried out that they made us complete the three last reloads in less than 30 days are captured. (Author)

Development of a methodology for the economical analysis of fuel cycles, application to the Laguna Verde central

International Nuclear Information System (INIS)

Malfavon, S.M.; Trejo, M.G.; Hernandez, H.; Francois, J.L.; Ortega, R.F.

2003-01-01

In this work a methodology developed to carry out the economical analysis of the fuel cycle of a nuclear reactor is presented. The methodology was applied to the Laguna Verde Nuclear Power Station (CNLV). The design of the reload scenarios of the CNLV are made with the Core Master Presto code (CM-Presto), three-dimensional simulator of the reactor core, the launched data by this, as well as the information of the Energy use plan (PUE), it allowed us to obtain reliable results through the fitness of an algorithm of economic calculation that considers all the components of the fuel cycle to present worth. With the application of the methodology it was obtained the generated energy, as well as their respective cost of each sub lot type of assemblies by operation cycle, from the start-up of the CNLV until September 13, 2002. Using the present worth method its were moved all the values at November 5, 1988, date of operation beginning. To the final of the analysis an even cost of 6.188 mills/kWh was obtained for those first 9 cycles of the Unit 1 of the CNLV, being observed that the costs of those first 3 operation cycles are the more elevated. Considering only the values starting from the cycle 4, the levelled cost turns out to be of 5.96 mills/kWh. It was also obtained the cost by fuel lot to evaluate the performance of assemble with the same physical composition. (Author)

Scenarios simulation of severe accident type small loss of coolant (Loca), with the code MELCOR version 2.1 for the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Cardenas V, J.; Mugica R, C. A.; Godinez S, V.

2013-10-01

In this work was carried out the analysis of two scenarios of the accident type with loss of coolant in a recirculation loop for a break with smaller ares to 0.1 ft 2 (4.6 cm 2 ), which is classified according to their size like small Loca. The first simulated scenario was a small Loca without action of the emergency coolant injection systems, and the second was a small Loca with only the available system LPCS. This design base accident was taken into account for its relevance with regard to the damage to the core and the hydrogen generation. Was also observed and analyzed the response of the action of the ECCS that depend of the loss of coolant reason and this in turn depends of the size and type of the pipe break. The specified scenarios were simulated by means of the use of MELCOR model for the nuclear power plant of Laguna Verde that has the Comision Nacional de Seguridad Nuclear y Salvaguardias. (Author)

Application of new control technology during the maintenance of equipment in the Laguna Verde nuclear power plant; Aplicacion de nueva tecnologia de control durante el mantenimiento de equipos en la CLV

Energy Technology Data Exchange (ETDEWEB)

Ojeda R, M. A. [CFE, Central Laguna Verde, Subgerencia General de Operacion, Veracruz (Mexico)]. e-mail: mario.ojeda@cfe.gob.mx

2008-07-01

In the nuclear power plant of Laguna Verde, in normal operation and recharges are carried out activities of preventive maintenance and corrective to different equipment, due to the one displacement of radioactive materials from the vessel of the reactor until the one system of vapor, different radiation levels are generated (from low until very high) in the circuits of vapor and water, the particles can be incrusted on those interior surfaces of the pipes and equipment, creating this way a potential risk of contamination and exhibition during the maintenance of equipment. To help to optimize the dose to the personnel the use of new technology the has been implemented which besides contributing an absolute control of the work, it offers bigger comfort to the one worker during the development of their work, also contributing a supervision more effective of the same one. Using the captured and processed information of the work developed you can use for the personnel's capacitation and feedback of the work for the continuous improvement of the same one. During a reduction of programmed power and normal operation are carried out maintenance correctives and specific works to preserve the readiness and ability of the equipment and with this to maintain the security of the nuclear power plant. The development of the theme it is showing the advances and commitments of personnel to take to excellence to the nuclear power plant of Laguna Verde showing to the obtained results of the dose and benefits of 2 works carried out in the nuclear power plant where tools ALARA were applied as well as the use of the new technology (Video Equipment of Tele dosimetry and Audio 'VETA') in works carried out in the building of purification level 10.15, change and cuts of filter of the prefilters of system G16, as well as,the retirement and transfer for its decay of High Integrity Container (HIC) of the building of purification level -0.55 to the Temporary Warehouse in Site

Calculations of hydrogen transport for the simulation of a Sbo in the NPP-L V using the code CFD GASFLOW

International Nuclear Information System (INIS)

Gomez T, A. M.; Xolocostli M, V.; Lopez M, R.; Filio L, C.; Mugica R, C. A.; Royl, P.

2013-10-01

The scenario of electric power total loss in the nuclear power plant of Laguna Verde (NPP-L V) has been analyzed using the code MELCOR previously, until reaching fault conditions of the primary container. A mitigation measure to avoid the loss of the primary contention is the realization of a venting toward the secondary contention (reactor building), however this measure bears the potential explosions occurrence risk when the hydrogen accumulated in the primary container with the oxygen of the reactor building atmosphere reacting. In this work a scenario has been supposed that considers the mentioned venting when the pressure of 4.5 kg/cm 2 is reached in the primary container. The information for the hydrogen like an entrance fact is obtained of the MELCOR results and the hydrogen transport in both contentions is analyzed with the code CFD GASFLOW that allows predicting the detailed distribution of the hydrogen volumetric concentration and the possible detonation of flammability conditions in the reactor building. The results show that the venting will produce detonation conditions in the venting level (level 33) and flammability in the level of the recharge floor. The methodology here described constitutes the base of a detailed calculation system of this type of phenomena that can use to make safety evaluations in the NPP-L V on scenarios that include gases transport. (Author)

Preliminary analysis of an hydrogen generator system based on nuclear energy in the Laguna Verde site

International Nuclear Information System (INIS)

Flores y Flores, A.; Francois L, J.L.

2003-01-01

The shortage of fossil fuels in the next future, as well as the growing one demand of energetics and the high cost of the production of alternating fuels, it forces us to take advantage of to the maximum the fossil fuel with the one which we count and to look for the form of producing alternating fuels at a low cost and better even if these supply sources are reliable and non pollutants. It is intended a solution to the shortage of fuel; to use the thermal energy liberated of some appropriate nuclear reactor to be able to obtain a fuel but clean and relatively cheap as it is the hydrogen. In the first place the methods were looked for to produce hydrogen using thermal energy, later it was analyzed the temperature liberated by the existent nuclear reactors as well as the advanced designs, according to this liberated temperature settled down that the methods but feasible to produce hydrogen its were the one of reformed with water stream of the natural gas (methane) and the other one of the S-I thermochemical cycle, and the nuclear reactors that give the thermal energy for this production they are those of gas of high temperature. Once established the processes and the appropriate reactors, it was analyzed the site of Laguna Verde, with relationship to the free space to be able to place the reactor and the plant producer of hydrogen, as well as the direction in which blow the dominant winds and the near towns to the place, it was carried out an analysis of some explosion of tanks that could store hydrogen and the damage that its could to cause depending from the distance to which its were of the fire. Finally it was carried out an evaluation of capital and of operation costs for those two methods of hydrogen production. (Author)

Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model

International Nuclear Information System (INIS)

Hernandez I, S.; Ortiz C, E.; Chavez M, C.

2011-11-01

At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

Four stops of fuel reloading with duration of less of 30 days in the Laguna Verde Central

International Nuclear Information System (INIS)

Lozano L, A.

2008-01-01

The Laguna Verde Central having established as mission 'With maximum priority in the safety, to generate electricity by nuclear means with competitive quality and cost, sustained in our personnel's continuous overcoming and deep respect to the environment' and respecting our values (safety, responsibility by results, professional integrity, continuous improvement, team work, excellence in the performance, quality of service, protection to the environment its thought about our strategic objectives of the power station being born by this way one of them that it is the improvement program 'reduction of reloading times' looking for to be improves every day comparing us with the best plants of the world effectiveness all the processes in the power station that allowed us to measure our performance with the same parameters that settle down at international level as its are nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect. After analyzing the performance record of the power station, evaluating our technical, economic capacity, the location of the installation besides revising the international experiences was defined that one of the concepts that impact considerably so much to the capacity factors and readiness besides the dose and production cost is the duration of the reloading periods, for this reason work strategies were elaborated to be able to reach our goals of reloading days in less than 30 days, here are formed the carried out actions that they made us complete the four last reloading in less than 30 days. (Author)

NucleoRed - Computerized system for increasing the effectiveness of the technical administrative conduct of the Laguna Verde Central

International Nuclear Information System (INIS)

Luna D, J.

2003-01-01

The on-line systems for the management of the Laguna Verde Central (CLV) have had the challenge to evolve from the PC's of first generation until emigrate to the new Internet technologies, so that they allow to the diverse work groups to have the computer tool that allows them to gather the necessary data and to carry out efficiently the analysis of their results. To confront the previous challenge, in the CLV it has been developed and implemented the Nucleo Red that is an on-line system with the objective of providing in it lines strategic information for the Technician-administrative management of the plant in the nuclear context. The Nucleo Red is the computational tool that reflects the technical administrative processes implemented by personnel of the different Operative departments, it seeks to cooperate to the reliable and efficient operation of the first nucleo electric central of Mexico, with technology and Mexican personnel the one which already it had received international recognitions. The perspective of this computer system is to continue inside the process of continuous improvement and that although it was designed for a nucleo electric plant it can also be taken to the conventional plants of generation of electric power, so that this technology can be taken advantage of in other non nuclear facilities. The objective of the present work, is to show the new modules that have been developed in the Nucleo Red, its operation in general, and the benefits that it presents its use. (Author)

Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant; Analisis de documentos de los materiales de la envolvente del nucleo del reactor nuclear de la CLV U-1

Energy Technology Data Exchange (ETDEWEB)

Zamora R, L.; Medina F, A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

1999-07-01

The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

CARACTERIZACIÓN ESTRUCTURAL DEL MANGLAR EN EL ESTERO PALO VERDE, LAGUNA DE CUYUTLÁN, COLIMA

Directory of Open Access Journals (Sweden)

Citlalli P. Téllez-García

2012-01-01

Full Text Available En el Estero Palo Verde, ubicado en el vaso IV de la Laguna de Cuyutlán, estado de Colima, se establecieron 48 unidades de muestreo (UM en tres rodales de mangle: 10 UM en rodal monoespecífico de Laguncularia racemosa, 25 UM en rodal monoespecífico de Rhizophora mangle y 13 UM en rodal mixto de L. racemosa-R. mangle. Se registró altura del dosel, diámetro del tronco, densidad de adultos y de repoblación, también se calculó área basal y volumen de madera. Los resultados indicaron que la densidad, área basal y volumen, para la categoría diamétrica (CD de 5 cm fueron significativamente diferentes (P < 0.05 entre los rodales monoespecíficos de R. mangle (2,500 árboles•ha-1, 4.2 m2•ha-1 y 22 m3•ha-1, respectivamente y L. racemosa (700 árboles•ha-1, 1.9 m2•ha-1 y 10 m3•ha-1, respectivamente. En las CD de 20 a 30 cm, el área basal fue significativamente mayor (P < 0.05 en el rodal monoespecífico de L. racemosa (1.6 - 3.8 m2•ha-1 que en el mixto de L. racemosa-R. mangle (0.5 - 2.5 m2•ha-1. La repoblación natural fue más abundante en el rodal de R. mangle (138 a 270 individuos•ha-1 que en el de L. racemosa (70 a 80 individuos•ha-1. Los valores estructurales mayores se alcanzaron para altura del dosel (10 m en el rodal de L. racemosa; para diámetro (40 cm y área basal (14.1 m2•ha-1 en el rodal de L. racemosa-R. mangle; y para repoblación natural (624 individuos•ha-1 en el rodal de R. mangle.

Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde

International Nuclear Information System (INIS)

Tijerina S, F.; Cruz G, M.; Amador C, C.

2013-10-01

In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

Simulation of the turbine trip of Unit 1 of the Laguna Verde nuclear power plant using the code Simulate-3K; Simulacion del disparo de turbina de la Unidad 1 de la central nuclear Laguna Verde empleando el codigo Simulate-3K

Energy Technology Data Exchange (ETDEWEB)

Alegria A, A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico); Filio L, C. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico); Ortiz V, J., E-mail: aalegria@cnsns.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2017-09-15

In order to compare the results obtained from the model developed in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) with the code Simulate-3K (S3K) with respect to those reported by the process computer of the Central (SIIP), the simulation of the turbine trip transient was carried out, caused by the firing of the main generator, the low differential pressure of oil of its seals and the automatic Scram of Unit 1 of the Laguna Verde nuclear power plant, at 87% of power nominal during the operation cycle 16. Since the reactor was brought to a safe stop due to Scram, was enough to simulate 20 seconds to observe the maximum increase in pressure with S3K. In this work, the following parameters are shown and compared: the neutron flux, the thermal power, the pressure in the dome, the flow at the entrance to the core, the steam flow that leaves the vessel and the minimal critical power ratio (MCPR). The neutron flux of the average power range monitors of the nuclear power plant was compared with the S3K detectors model. Finally, the MCPR was calculated with a different correlation to that of the fuel supplier and its deviation from its safety limit was determined. In conclusion, the results obtained show the current state of the model for the simulation of reactivity transients and the opportunity areas to consolidate this tool in support of the process of licensing refueling in the CNSNS. (Author)

Changes in reactivity and in the margins to thermal limits by the inclusion of control rods of advanced type in the Laguna Verde Power plant; Cambios en la reactividad y en los margenes a limites termicos por la inclusion de barras de control de tipo avanzado en la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Hernandez, J.L.; Perusquia, R.; Montes, J.L.; Ortiz, J.J.; Ramirez, J.R. [ININ, Depto. de Sistemas Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)]. E-mail: jlhm@nuclear.inin.mx

2004-07-01

The obtained results are presented when simulating with CM-PRESTO code the cycle 10 of the unit 1 of the Laguna Verde Central, using two advanced types of control bars, besides the originally loaded ones. The two advanced types, to those that are denominated 1AV and 2AV in this work, are of different design, however both have in some place of the bar, a section with hafnium like neutron absorber material. They thought about three different scenarios, in the first one, used as reference, is simulated the cycle 10 using the original control bars, while in the other two cases the advanced types are used. The values of the reactivity were compared and of some margins to the thermal limits obtained when using the bars of advanced type, with those obtained in the case in that alone they are considered those original bars. It was found that in condition of power both advanced types present bigger absorber power of neutrons that the original bars, being quantified in average this bigger power in 0.22 pcm/notch for the type 1AV and in 0.51 pcm/notch for the type 2AV. The affectation of the margins to the observed thermal limits is minimum. (Author)

Simulation of the turbine discharge transient with the code Trace; Simulacion del transitorio disparo de turbina con el codigo TRACE

Energy Technology Data Exchange (ETDEWEB)

Mejia S, D. M.; Filio L, C., E-mail: dulcemaria.mejia@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2014-10-15

In this paper the results of the simulation of the turbine discharge transient are shown, occurred in Unit 1 of nuclear power plant of Laguna Verde (NPP-L V), carried out with the model of this unit for the best estimate code Trace. The results obtained by the code Trace are compared with those obtained from the Process Information Integral System (PIIS) of the NPP-L V. The reactor pressure, level behavior in the down-comer, steam flow and flow rate through the recirculation circuits are compared. The results of the simulation for the operation power of 2027 MWt, show concordance with the system PIIS. (Author)

Simulation of the turbine discharge transient with the code Trace

International Nuclear Information System (INIS)

Mejia S, D. M.; Filio L, C.

2014-10-01

In this paper the results of the simulation of the turbine discharge transient are shown, occurred in Unit 1 of nuclear power plant of Laguna Verde (NPP-L V), carried out with the model of this unit for the best estimate code Trace. The results obtained by the code Trace are compared with those obtained from the Process Information Integral System (PIIS) of the NPP-L V. The reactor pressure, level behavior in the down-comer, steam flow and flow rate through the recirculation circuits are compared. The results of the simulation for the operation power of 2027 MWt, show concordance with the system PIIS. (Author)

Application of the source term code package to obtain a specific source term for the Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Souto, F.J.

1991-06-01

The main objective of the project was to use the Source Term Code Package (STCP) to obtain a specific source term for those accident sequences deemed dominant as a result of probabilistic safety analyses (PSA) for the Laguna Verde Nuclear Power Plant (CNLV). The following programme has been carried out to meet this objective: (a) implementation of the STCP, (b) acquisition of specific data for CNLV to execute the STCP, and (c) calculations of specific source terms for accident sequences at CNLV. The STCP has been implemented and validated on CDC 170/815 and CDC 180/860 main frames as well as on a Micro VAX 3800 system. In order to get a plant-specific source term, data on the CNLV including initial core inventory, burn-up, primary containment structures, and materials used for the calculations have been obtained. Because STCP does not explicitly model containment failure, dry well failure in the form of a catastrophic rupture has been assumed. One of the most significant sequences from the point of view of possible off-site risk is the loss of off-site power with failure of the diesel generators and simultaneous loss of high pressure core spray and reactor core isolation cooling systems. The probability for that event is approximately 4.5 x 10 -6 . This sequence has been analysed in detail and the release fractions of radioisotope groups are given in the full report. 18 refs, 4 figs, 3 tabs

Core reactor simulation of the Central Laguna Verde (CLV) reactor in stationary state and an example of the application in the recharge options analysis of cycle 3; Simulacion del nucleo del reactor de la Central Laguna Verde (CLV) en estado estacionario y ejemplo de aplicacion en el analisis de alternativas de recarga del ciclo 3

Energy Technology Data Exchange (ETDEWEB)

Ocampo Mansilla, Hector; Francois Lacouture, Juan Luis; Blanco Lara, Jesus; Cortes Campos, Carlos Cristobal; Esquivias Montoya, Jesus; Esquivel Torres, Jose Luis; Martin del Campo Marquez, Cecilia [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico); Sanchez Herrera, Luciano; Torres Alvarez, Carlos [Comision Federal de Electricidad (CFE), Mexico, D. F. (Mexico)

1991-12-31

The results are presented of a study requested by Comision Federal de Electricidad (CFE) for the analysis of Cycle 3, of Unit No. 1 of the Laguna Verde Nuclear Power Station (CLNV) and determine the burning effect impact, carried out with the starting tests and the operation of Cycles 1 and 2 on base of the cycle extension known as coastdown. The calculations were realized with the Code Package FMS for fuel managing, using the Code PRESTO-B that analyzes the reactor in detailed form in three dimensions an in stationary state. In the study the schemes of fraction of recharge proposed by General Electric (GE) were analyzed with the effect of cycle extension. The initial design value of 100 assemblies for Cycle 3, GE proposes to increase such fraction from 112 to 120 assemblies. This impacts the cost of the second recharge and the purpose of this investigation is to analyze options with higher fuel enrichment in U-235 to minimize the number of assemblies in this recharge. The analyses effected show that the designs proposed by GE do not fulfill the required energy proposed for the cycle, even using in the recharge only fuel with 3.03% of enrichment. It is proposed, likewise, the fuel enrichment up to 3.25% to satisfy the energy demand with a minimum of assemblies. [Espanol] Se presentan los resultados de un estudio solicitado por la Comision Federal de Electricidad (CFE) para analizar el ciclo 3, de la unidad 1 de la Central Laguna Verde (CLV), y determinar el impacto del efecto de quemado llevado a cabo con las pruebas de arranque y por la operacion de los ciclos 1 y 2 con base en la tecnica de alargamiento del ciclo conocida como coastdown1. Los calculos se realizaron con el paquete de codigos FMS para la administracion de combustible, usando el codigo PRESTO-B que analiza el reactor en forma detallada en tres dimensiones y en estado estacionario. Se analizaron en el estudio los esquemas de fraccion de recarga propuesta por la General Electric (GE) con el efecto de

Core reactor simulation of the Central Laguna Verde (CLV) reactor in stationary state and an example of the application in the recharge options analysis of cycle 3; Simulacion del nucleo del reactor de la Central Laguna Verde (CLV) en estado estacionario y ejemplo de aplicacion en el analisis de alternativas de recarga del ciclo 3

Energy Technology Data Exchange (ETDEWEB)

Ocampo Mansilla, Hector; Francois Lacouture, Juan Luis; Blanco Lara, Jesus; Cortes Campos, Carlos Cristobal; Esquivias Montoya, Jesus; Esquivel Torres, Jose Luis; Martin del Campo Marquez, Cecilia [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico); Sanchez Herrera, Luciano; Torres Alvarez, Carlos [Comision Federal de Electricidad (CFE), Mexico, D. F. (Mexico)

1992-12-31

The results are presented of a study requested by Comision Federal de Electricidad (CFE) for the analysis of Cycle 3, of Unit No. 1 of the Laguna Verde Nuclear Power Station (CLNV) and determine the burning effect impact, carried out with the starting tests and the operation of Cycles 1 and 2 on base of the cycle extension known as coastdown. The calculations were realized with the Code Package FMS for fuel managing, using the Code PRESTO-B that analyzes the reactor in detailed form in three dimensions an in stationary state. In the study the schemes of fraction of recharge proposed by General Electric (GE) were analyzed with the effect of cycle extension. The initial design value of 100 assemblies for Cycle 3, GE proposes to increase such fraction from 112 to 120 assemblies. This impacts the cost of the second recharge and the purpose of this investigation is to analyze options with higher fuel enrichment in U-235 to minimize the number of assemblies in this recharge. The analyses effected show that the designs proposed by GE do not fulfill the required energy proposed for the cycle, even using in the recharge only fuel with 3.03% of enrichment. It is proposed, likewise, the fuel enrichment up to 3.25% to satisfy the energy demand with a minimum of assemblies. [Espanol] Se presentan los resultados de un estudio solicitado por la Comision Federal de Electricidad (CFE) para analizar el ciclo 3, de la unidad 1 de la Central Laguna Verde (CLV), y determinar el impacto del efecto de quemado llevado a cabo con las pruebas de arranque y por la operacion de los ciclos 1 y 2 con base en la tecnica de alargamiento del ciclo conocida como coastdown1. Los calculos se realizaron con el paquete de codigos FMS para la administracion de combustible, usando el codigo PRESTO-B que analiza el reactor en forma detallada en tres dimensiones y en estado estacionario. Se analizaron en el estudio los esquemas de fraccion de recarga propuesta por la General Electric (GE) con el efecto de

Análisis prospectivo del conflicto político ambiental, sobre el uso del espacio público Parque La Laguna, localizado en la Urbanización Nueva Casarapa, Estado Miranda.Venezuela

Directory of Open Access Journals (Sweden)

Mildred Zerpa

2013-06-01

Full Text Available Nueva Casarapa, es un complejo urbanístico integral concebido bajo el concepto de ciudad. Posee espacios abiertos, centros comerciales, espacios verdes y públicos cuidados por los propios habitantes y un parque central conocido como La Laguna. En 2009 comenzó una polémica que podría convertirse en conflicto socio natural con implicaciones en la gestión integral de riesgo del Municipio Plaza, por la incertidumbre acerca de cuál grupo es el más indicado para administrar y gestionar el parque La Laguna.

Range of the radiation monitor for the rigid vent of primary containment during normal and emergency operation for a BWR-5 in Laguna Verde; Rango del monitor de radiacion para el venteo rigido de la contencion primaria durante operacion normal y emergencia para un reactor BWR-5 en Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Tijerina S, F.; Pozos S, A. M.; Cabrera U, S.; Mata A, J. A.; Sandoval V, S.; Ovando C, R.; Vargas A, A.; Gallardo R, I.; Cruz G, M.; Amador C, C., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Km 44.5 Carretera Cardel-Nautla, 91476 Laguna Verde, Alto Lucero, Veracruz (Mexico)

2014-10-15

The earthquake followed by a tsunami, happened in March, 2011 in the coasts of oriental Japan, caused damages in the nuclear power plants 1 at 4 of Fukushima Daiichi leading to damage of the fuel in three of the reactors and to the radiation liberation to the exterior. As consequence of those events, the regulations requires that the power plants with Primary Containment type Mark I and II evaluate to have a system of rigid vent with a monitoring equipment of radiation effluents. The present work covers the rigid vent of diameter 12 of the Primary Containment, type Mark-II, of nuclear power plant of Laguna Verde in conditions of severe accident and normal operation, low regime of Extended Power Up rate (EPU - 2317 MWt), using the codes MAAP3B, MICROSHILED 5.05 and the Bardach Black Boxes methodology. As a result the measurement range of the radiation monitor that is required for monitoring the gassy liberation to the atmosphere was determined. The conclusion is that the superior limit of the range of the radiation meter during a Severe Accident is of 8.55 E + 05 R/h (8.55 E + 08 m R/h) and the superior limit in normal operation of 1.412 E-11 at 2.540 E-7 R/h (1.412 E-14 at 2.540 E-10 m R/h). (Author)

Recent nuclear technology advances of GE-H and GNF in partnership with CFE's Laguna Verde 2

International Nuclear Information System (INIS)

Cuevas V, G.; Iwamoto, T.; Banfield, J.; Calleros M, G.

2015-09-01

This paper is presented based on work stemming from the long-standing technical partnership between Comision Federal de Electricidad (CFE) and Global Nuclear Fuel - Americas LLC (GNF), and this paper's purpose is to provide valuable information for the nuclear industry. First, a one-to-one comparison of measurements from Gamma Thermometers (G Ts) installed in Laguna Verde 2 (LV-2) core against axially corresponding Traverse In-core Probe (Tip) measurements is remarkably close. This longest running G T plant validation for the Economic Simplified Boiling Water Reactor (ESBWR) power monitoring devices is also proving that the devices have the potential to simplify power measurements in Boiling Water Reactors (BWRs). Second, code validation results show remarkable reduction of radial power uncertainty with respect to current technology when new GNF codes for three-dimensional core simulations are compared to Tip power measurements. The LV-2 core is of paramount importance for BWR data analysis since the core has been loaded from the start of operation with different GNF fuel bundle types, fuel management has been designed with GNF codes and on-line core monitoring has been performed with GNF's 3-Dimensional Monicore system. This validation is also reliable since gamma Tips are used for local power measurements rather than thermal neutron Tips, which are more sensitive to local turbulence and positional changes. A nuclear/thermal-hydraulic core simulation of GNF fuel is undertaken from the beginning of operation of LV-2 (cycle 1) through the range of different power scenarios including low power, original licensed thermal power, power up rate and extended power up rate. Results confirm the conclusions from previous validations in different BWRs and support GNF efforts for licensing the new generation of nuclear engineering codes. (Author)

Recent nuclear technology advances of GE-H and GNF in partnership with CFE's Laguna Verde 2

Energy Technology Data Exchange (ETDEWEB)

Cuevas V, G.; Iwamoto, T.; Banfield, J. [GE-Hitachi Nuclear Energy Americas LLC, Global Nuclear Fuel - Americas LLC, 3901 Castle Hayne Road, Wilmington, 28401 North Carolina (United States); Calleros M, G., E-mail: Gabriel.Cuevas-Vivas@age.com [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Veracruz-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

2015-09-15

This paper is presented based on work stemming from the long-standing technical partnership between Comision Federal de Electricidad (CFE) and Global Nuclear Fuel - Americas LLC (GNF), and this paper's purpose is to provide valuable information for the nuclear industry. First, a one-to-one comparison of measurements from Gamma Thermometers (G Ts) installed in Laguna Verde 2 (LV-2) core against axially corresponding Traverse In-core Probe (Tip) measurements is remarkably close. This longest running G T plant validation for the Economic Simplified Boiling Water Reactor (ESBWR) power monitoring devices is also proving that the devices have the potential to simplify power measurements in Boiling Water Reactors (BWRs). Second, code validation results show remarkable reduction of radial power uncertainty with respect to current technology when new GNF codes for three-dimensional core simulations are compared to Tip power measurements. The LV-2 core is of paramount importance for BWR data analysis since the core has been loaded from the start of operation with different GNF fuel bundle types, fuel management has been designed with GNF codes and on-line core monitoring has been performed with GNF's 3-Dimensional Monicore system. This validation is also reliable since gamma Tips are used for local power measurements rather than thermal neutron Tips, which are more sensitive to local turbulence and positional changes. A nuclear/thermal-hydraulic core simulation of GNF fuel is undertaken from the beginning of operation of LV-2 (cycle 1) through the range of different power scenarios including low power, original licensed thermal power, power up rate and extended power up rate. Results confirm the conclusions from previous validations in different BWRs and support GNF efforts for licensing the new generation of nuclear engineering codes. (Author)

Effects evaluation of artificial aging by temperature and gamma radiation on cables for Laguna Verde nuclear power plant (LVNPP)

Energy Technology Data Exchange (ETDEWEB)

Vazquez C, R. M.; Bonifacio M, J.; Garcia H, E. E.; Loperena Z, J. A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Garcia M, C., E-mail: raulmario.vazquez@inin.gob.m [CFE, Central Nuclear Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

2010-10-15

A set of tests has been carried out at the Equipment Qualification Laboratory at National Institute of Nuclear Research to perform accelerated aging up to 60 years under temperature and gamma radiation environment for electrical cables. The results obtained from such tests are the base line data for comparison to with the current cable conditions at the plant. This work is intended for establishing the cable aging management program for the Laguna Verde nuclear power plant (LVNPP). For such purpose, the Institute has prepared methodologies and procedures to apply condition monitoring techniques in accelerated aging tests on samples of new cables drawn from the LVNPP warehouse. The condition indicators of the material selected for condition monitoring and the aging management process of cables were: Elongation at Break (EAB) and Oxidation Induction Time (OIT). A cable aging management program includes activities for cable selection, determination of condition indicators of the cable materials (EAB, OIT, Ind enter), accelerated aging of cable samples at the laboratory, analysis of maintenance history, operational experience of the plant and analysis of the environmental and service conditions (temperature and gamma radiation), as well as the establishment of a condition monitoring plan for cables in the plant. Two cable model samples were thermally aged and gamma irradiated with doses corresponding to differential operational periods. EAB and OIT values of cable insulating material (ethylene propylene and cross linked polyethylene) were obtained. It was found that the EAB and OIT data correlation is very closed, and it could be applied to infer values that are not possible to measure directly at the plant and be used for cable aging evaluation and remaining life time determination. (Author)

Innovation, creative ideas to attend the challenges of the Central Laguna Verde for the period 2011-2015 due to new 100% of power; Innovacion, ideas creativas para atender los retos y desafios del periodo de la Central Laguna Verde en 2011-2015 por el nuevo 100% de potencia

Energy Technology Data Exchange (ETDEWEB)

Rivera C, A., E-mail: arr99999@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Veracruz (Mexico)

2011-11-15

For the nuclear power plant of Laguna Verde (CLV) is an opportunity to present to the nuclear community in Mexico the improvement areas and challenges for the period 2011-2015, now that has been concluded the phase of starting tests of the CLV modernization, with an increment of power of 20% that represents a new generation of electrical power of 815 M We per hour in the 2 Units, with these new challenges the strategic planning 2011 at 2015 take relevance to give guide to the innovation, with new ideas of improvement to the processes, human resources and leadership, with the purpose of maintaining reliable all the equipment s and process systems by means of the use of strengths, opportunities, vulnerabilities and threats analysis, in order to make strategies that aid to generate competitive advantages for the production of electric power in Mexico, using privileged information that contain the database of the improvement systems, like are the programs of corrective action, of human acting, of external operational experience, of auto-evaluation and of benchmarking that is the referential comparison with other similar power stations. At present, in the general management of operation exist the training by coaching to grow in the formation of the half commands and line supervisors, reinforcing the wanted behaviors, the abilities of the technicians, and the orientation in deficient performances in the search of the operational excellence. (Author)

Impact on the bar value in hot by the introduction of advanced control bars in the Unit 1 of the Laguna Verde Nuclear power plant

International Nuclear Information System (INIS)

Montes, J.L.; Perusquia, R.; Ortiz, J.J.; Hernandez, J.L.; Ramirez, J.R.

2004-01-01

In recent dates the Laguna Verde Nuclear Power station (CNLV) has acquired new designs of control bars, this new type of bars presents modifications important in their design. For what is important to analyze their performance inside those reactors of this nuclear power station. Presently work is shown the behavior of the nucleus of the reactor in hot condition (HFP) when three different types of control bar are used. The first of them corresponds the one that initially has been used in this power station and that we will call original. The second type of control bars, it corresponds to an advanced type and it is the first design different from the original and it corresponds to a bar design that it includes Hafnium (Hf) like one of their neutronic absorption characteristics. The third, denoted as 2AV, include besides the material of the second type new design characteristics, and it is the last finish bar type that it has been introduced in the operation of the reactors of the CNLV. With base in the studied cases is found that the bars 2AV have a total power value, 7.6 % bigger respect the bars 1AV; and in turn the bars 1AV, 6.1 % bigger with respect the ORG control bars. (Author)

Changes in reactivity and in the margins to thermal limits by the inclusion of control rods of advanced type in the Laguna Verde Power plant

International Nuclear Information System (INIS)

Hernandez, J.L.; Perusquia, R.; Montes, J.L.; Ortiz, J.J.; Ramirez, J.R.

2004-01-01

The obtained results are presented when simulating with CM-PRESTO code the cycle 10 of the unit 1 of the Laguna Verde Central, using two advanced types of control bars, besides the originally loaded ones. The two advanced types, to those that are denominated 1AV and 2AV in this work, are of different design, however both have in some place of the bar, a section with hafnium like neutron absorber material. They thought about three different scenarios, in the first one, used as reference, is simulated the cycle 10 using the original control bars, while in the other two cases the advanced types are used. The values of the reactivity were compared and of some margins to the thermal limits obtained when using the bars of advanced type, with those obtained in the case in that alone they are considered those original bars. It was found that in condition of power both advanced types present bigger absorber power of neutrons that the original bars, being quantified in average this bigger power in 0.22 pcm/notch for the type 1AV and in 0.51 pcm/notch for the type 2AV. The affectation of the margins to the observed thermal limits is minimum. (Author)

Quality studies of the energy in the electric net of the gathering warehouse of reusable parts and contaminate oils of the nuclear power plant Laguna Verde; Estudios de calidad de la energia en la red electrica del almacen de acopio de partes reusables y aceites contaminados (CCAC) de la Central Nuclear 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 Cardel-Nautla Km 42.5, Veracruz (Mexico)

2012-10-15

In the industry exist the high costs by faults of electronic and electric equipment s, due to during the design process, installation, tests and operation of these equipment s, is not had appropriate detection equipment to carry out quality studies of the energy. These studies give an important support to know that occurs in an electric net, the cause of the anomalous behavior of the equipment s and this way to avoid the expensive faults carrying out necessary engineering adaptations in an electric net. The elements of the electricity that are determined are the tension, current and frequency that are inside acceptable operational parameters that facilitate the operation and constant operation of the equipment s, free of interruptions and failures. The application of the quality studies of the energy is growing little by little in Mexico for the problems solution in the equipment s. This field is also developing new techniques and technologies integrated in the equipment s for its monitoring detection and protection. The present work offers the results of the first Quality Study of the Energy in the nuclear power plant of Laguna Verde to solve the problem in the gathering warehouse of reusable parts and contaminate oils, in which the failure of the two radiation monitors of the gassy effluent of ventilation HVAC of the warehouse took place. (Author)

Simulation of the turbine trip of Unit 1 of the Laguna Verde nuclear power plant using the code Simulate-3K

International Nuclear Information System (INIS)

Alegria A, A.; Filio L, C.; Ortiz V, J.

2017-09-01

In order to compare the results obtained from the model developed in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) with the code Simulate-3K (S3K) with respect to those reported by the process computer of the Central (SIIP), the simulation of the turbine trip transient was carried out, caused by the firing of the main generator, the low differential pressure of oil of its seals and the automatic Scram of Unit 1 of the Laguna Verde nuclear power plant, at 87% of power nominal during the operation cycle 16. Since the reactor was brought to a safe stop due to Scram, was enough to simulate 20 seconds to observe the maximum increase in pressure with S3K. In this work, the following parameters are shown and compared: the neutron flux, the thermal power, the pressure in the dome, the flow at the entrance to the core, the steam flow that leaves the vessel and the minimal critical power ratio (MCPR). The neutron flux of the average power range monitors of the nuclear power plant was compared with the S3K detectors model. Finally, the MCPR was calculated with a different correlation to that of the fuel supplier and its deviation from its safety limit was determined. In conclusion, the results obtained show the current state of the model for the simulation of reactivity transients and the opportunity areas to consolidate this tool in support of the process of licensing refueling in the CNSNS. (Author)

Laguna Verde: a 120% extended power up-rate project developed by Iberdrola

International Nuclear Information System (INIS)

Merino Teillet, A.; Garcia-Serrano Tapia, J. L.; Ruiz Gutierrez, L.

2010-01-01

The experience which this document wants to present, describes the work being developed by IBERDROLA Ingenieria y Construccion, for the Laguna Verde plant in Mexico, owned by the Federal Electricity Commission (CFE). This generation plant consists of two light boiling water type units (BWR) design by General Electric in the 80's. The objective of this project is to perform the modifications on the thermal cycle of the plant required by an Extended Power Up-rate, to achieve a safe and reliable operation of the plant at 120% of its original thermal power, whilst upgrading and renovating plant equipment and installations to achieve a license renewal from 40 to 60 years of operation The consortium formed in 97% by IBERDROLA Ingenieria y Construccion SAU and in 3% by ALSTOM Mexicana, S.A. de CV, was awarded the contract in an international bid, competing against General Electric and Siemens. The project began in March 2007 and is scheduled to finalize in December 2010. At this point the work carried out include modifications of the main condenser replacement, moisture separator reheaters (MSR's) and feedwater heaters no. 5 and 6 in the two units, therefore having executed two out of four scheduled outages. The scope, development and organization of this project, whose basic elements include the design, engineering, training, supply of equipment, dismantling, installation, testing, commissioning, treatment and delivery of radioactive waste generated during the project implementation to CFE, is aimed to ensure a safe and reliable operation of the plant under the new conditions of increased thermal power of the reactor, with a thermal cycle optimized so that the gross power of the generator increase from the current 686.7 MWe to a value of 817.1 MWe in both units. An Extended Power Up-rate means an opportunity to modernize equipments, to improve maintenance, to get a better plant knowledge and to motivate the employees facing a challenging project. This project, being the

Range of the radiation monitor for the rigid vent of primary containment during normal and emergency operation for a BWR-5 in Laguna Verde

International Nuclear Information System (INIS)

Tijerina S, F.; Pozos S, A. M.; Cabrera U, S.; Mata A, J. A.; Sandoval V, S.; Ovando C, R.; Vargas A, A.; Gallardo R, I.; Cruz G, M.; Amador C, C.

2014-10-01

The earthquake followed by a tsunami, happened in March, 2011 in the coasts of oriental Japan, caused damages in the nuclear power plants 1 at 4 of Fukushima Daiichi leading to damage of the fuel in three of the reactors and to the radiation liberation to the exterior. As consequence of those events, the regulations requires that the power plants with Primary Containment type Mark I and II evaluate to have a system of rigid vent with a monitoring equipment of radiation effluents. The present work covers the rigid vent of diameter 12 of the Primary Containment, type Mark-II, of nuclear power plant of Laguna Verde in conditions of severe accident and normal operation, low regime of Extended Power Up rate (EPU - 2317 MWt), using the codes MAAP3B, MICROSHILED 5.05 and the Bardach Black Boxes methodology. As a result the measurement range of the radiation monitor that is required for monitoring the gassy liberation to the atmosphere was determined. The conclusion is that the superior limit of the range of the radiation meter during a Severe Accident is of 8.55 E + 05 R/h (8.55 E + 08 m R/h) and the superior limit in normal operation of 1.412 E-11 at 2.540 E-7 R/h (1.412 E-14 at 2.540 E-10 m R/h). (Author)

Innovation, creative ideas to attend the challenges of the Central Laguna Verde for the period 2011-2015 due to new 100% of power

International Nuclear Information System (INIS)

Rivera C, A.

2011-11-01

For the nuclear power plant of Laguna Verde (CLV) is an opportunity to present to the nuclear community in Mexico the improvement areas and challenges for the period 2011-2015, now that has been concluded the phase of starting tests of the CLV modernization, with an increment of power of 20% that represents a new generation of electrical power of 815 M We per hour in the 2 Units, with these new challenges the strategic planning 2011 at 2015 take relevance to give guide to the innovation, with new ideas of improvement to the processes, human resources and leadership, with the purpose of maintaining reliable all the equipment s and process systems by means of the use of strengths, opportunities, vulnerabilities and threats analysis, in order to make strategies that aid to generate competitive advantages for the production of electric power in Mexico, using privileged information that contain the database of the improvement systems, like are the programs of corrective action, of human acting, of external operational experience, of auto-evaluation and of benchmarking that is the referential comparison with other similar power stations. At present, in the general management of operation exist the training by coaching to grow in the formation of the half commands and line supervisors, reinforcing the wanted behaviors, the abilities of the technicians, and the orientation in deficient performances in the search of the operational excellence. (Author)

Simulations of the design basis accident at conditions of power increase and the o transient of MSIV at overpressure conditions of the Laguna Verde Power Station; Simulaciones del accidente base de diseno a condiciones de aumento de potencia y del transitorio de cierre de MSIV a condiciones de sobrepresion de la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Araiza M, E.; Nunez C, A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

2001-07-01

This document presents the analysis of the simulation of the loss of coolant accident at uprate power conditions, that is 2027 MWt (105% of the current rated power of 1931MWt). This power was reached allowing an increase in the turbine steam flow rate without changing the steam dome pressure value at its rated conditions (1020 psiaJ. There are also presented the results of the simulation of the main steam isolation va/ve transient at overpressure conditions 1065 psia and 1067 MWt), for Laguna Verde Nuclear Power Station. Both simulations were performed with the best estimate computer code TRA C BF1. The results obtained in the loss of coolant accident show that the emergency core coolant systems can recover the water level in the core before fuel temperature increases excessively, and that the peak pressure reached in the drywell is always below its design pressure. Therefore it is concluded that the integrity of the containment is not challenged during a loss of coolant accident at uprate power conditions.The analysis of the main steam isolation valve transients at overpressure conditions, and the analysis of the particular cases of the failure of one to six safety relief valves to open, show that the vessel peak pressures are below the design pressure and have no significant effect on vessel integrity. (Author)

Quality studies of the energy in the electric net of the gathering warehouse of reusable parts and contaminate oils of the nuclear power plant Laguna Verde

International Nuclear Information System (INIS)

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

2012-10-01

In the industry exist the high costs by faults of electronic and electric equipment s, due to during the design process, installation, tests and operation of these equipment s, is not had appropriate detection equipment to carry out quality studies of the energy. These studies give an important support to know that occurs in an electric net, the cause of the anomalous behavior of the equipment s and this way to avoid the expensive faults carrying out necessary engineering adaptations in an electric net. The elements of the electricity that are determined are the tension, current and frequency that are inside acceptable operational parameters that facilitate the operation and constant operation of the equipment s, free of interruptions and failures. The application of the quality studies of the energy is growing little by little in Mexico for the problems solution in the equipment s. This field is also developing new techniques and technologies integrated in the equipment s for its monitoring detection and protection. The present work offers the results of the first Quality Study of the Energy in the nuclear power plant of Laguna Verde to solve the problem in the gathering warehouse of reusable parts and contaminate oils, in which the failure of the two radiation monitors of the gassy effluent of ventilation HVAC of the warehouse took place. (Author)

Simulations of the design basis accident at conditions of power increase and the o transient of MSIV at overpressure conditions of the Laguna Verde Power Station

International Nuclear Information System (INIS)

Araiza M, E.; Nunez C, A.

2001-01-01

This document presents the analysis of the simulation of the loss of coolant accident at uprate power conditions, that is 2027 MWt (105% of the current rated power of 1931MWt). This power was reached allowing an increase in the turbine steam flow rate without changing the steam dome pressure value at its rated conditions (1020 psiaJ. There are also presented the results of the simulation of the main steam isolation va/ve transient at overpressure conditions 1065 psia and 1067 MWt), for Laguna Verde Nuclear Power Station. Both simulations were performed with the best estimate computer code TRA C BF1. The results obtained in the loss of coolant accident show that the emergency core coolant systems can recover the water level in the core before fuel temperature increases excessively, and that the peak pressure reached in the drywell is always below its design pressure. Therefore it is concluded that the integrity of the containment is not challenged during a loss of coolant accident at uprate power conditions.The analysis of the main steam isolation valve transients at overpressure conditions, and the analysis of the particular cases of the failure of one to six safety relief valves to open, show that the vessel peak pressures are below the design pressure and have no significant effect on vessel integrity. (Author)

Technical and economic proposal for the extension of the Laguna Verde Nuclear Power plant with an additional nuclear reactor

International Nuclear Information System (INIS)

Leal C, C.D.; Francois L, J.L.

2006-01-01

The increment of the human activities in the industrial environments and of generation of electric power, through it burns it of fossil fuels, has brought as consequence an increase in the atmospheric concentrations of the calls greenhouse effect gases and, these in turn, serious repercussions about the environment and the quality of the alive beings life. The recent concern for the environment has provoked that industrialized countries and not industrialized carry out international agreements to mitigate the emission from these gases to the atmosphere. Our country, like part of the international community, not is exempt of this problem for what is necessary that programs begin guided toward the preservation of the environment. As for the electric power generation, it is indispensable to diversify the sources of primary energy; first, to knock down the dependence of the hydrocarbons and, second, to reduce the emission of polluting gases to the atmosphere. In this item, the nucleo electric energy not only has proven to be safe and competitive technical and economically, able to generate big quantities of electric power with a high plant factor and a considerable cost, but rather also, it is one of the energy sources that less pollutants it emits to the atmosphere. The main object of this work is to carry out a technical and economic proposal of the extension of the Laguna Verde Nuclear power plant (CNLV) with a new nuclear reactor of type A BWR (Advanced Boiling Water Reactor), evolutionary design of the BWR technology to which belong the two reactors installed at the moment in the plant, with the purpose of increasing the installed capacity of generation of the CNLV and of the Federal Commission of Electricity (CFE) with foundation in the sustainable development and guaranteeing the protection of the environment by means of the exploitation of a clean and sure technology that counts at the moment with around 12,000 year-reactor of operational experience in more of

Calculations of hydrogen transport for the simulation of a Sbo in the NPP-L V using the code CFD GASFLOW; Calculos de transporte de hidrogeno para la simulacion de un SBO en la CNLV usando el codigo CFD GASFLOW

Energy Technology Data Exchange (ETDEWEB)

Gomez T, A. M.; Xolocostli M, V. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Lopez M, R.; Filio L, C.; Mugica R, C. A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); Royl, P., E-mail: armando.gomez@inin.gob.mx [Karlsruhe Institute of Technology, Consultor, Hermann-von-Helmholtz-Platz, D-76344 Eggenstein -Leopoldshafen, Karlsruhe (Germany)

2013-10-15

The scenario of electric power total loss in the nuclear power plant of Laguna Verde (NPP-L V) has been analyzed using the code MELCOR previously, until reaching fault conditions of the primary container. A mitigation measure to avoid the loss of the primary contention is the realization of a venting toward the secondary contention (reactor building), however this measure bears the potential explosions occurrence risk when the hydrogen accumulated in the primary container with the oxygen of the reactor building atmosphere reacting. In this work a scenario has been supposed that considers the mentioned venting when the pressure of 4.5 kg/cm{sup 2} is reached in the primary container. The information for the hydrogen like an entrance fact is obtained of the MELCOR results and the hydrogen transport in both contentions is analyzed with the code CFD GASFLOW that allows predicting the detailed distribution of the hydrogen volumetric concentration and the possible detonation of flammability conditions in the reactor building. The results show that the venting will produce detonation conditions in the venting level (level 33) and flammability in the level of the recharge floor. The methodology here described constitutes the base of a detailed calculation system of this type of phenomena that can use to make safety evaluations in the NPP-L V on scenarios that include gases transport. (Author)

Arrangement and statistics of storage containers of spent fuel for assemblies of the SFP of NPP-L V, Unit 1

International Nuclear Information System (INIS)

Mijangos D, Z. E.; Vargas A, A. F.; Amador C, C.

2014-10-01

This work presents the determination of assemblies of the spent fuel pool (SFP) of the nuclear power plant of Laguna Verde (NPP-L V) which are candidates to be assigned to storage containers of independent spent fuel, with the objective of liberating decay heat and to have more space in the SFP, for the store of retired assemblies of the reactors in future reloads of NPP-L V, besides that the removed assemblies of the SFP should be stored in specific containers to guarantee the physical safety of them, as well as the radiological protection to the population and the environment. The design of the containers considered in this work is to store a maximum of 69 assemblies; it has a thermal capacity of 26 kilowatts and allows storing assemblies with a minimum of 5 years of have been extracted of the reactor core. Is considered that in 2016 start the storage of the spent assemblies on the containers, the candidates assemblies to store cover from the first reload in 1991, until the assemblies deposited in the SFP in the 14 reload in 2010; therefore in 2016, such assemblies will have fulfilled with the criteria of 5 years of have been removed of the Reactor, also the 69 assemblies assigned to each container will have a resulting decay heat that does not exceed the thermal capacity of the container, but that in great percentage approximates to the same one, and this way to take full advantage of their storage capacity and thermal capacity for each container. This work also contains the arrangement to accommodate the assemblies in the containers; such arrangement is constituted by areas according to the decay heat of each assembly. (Author)

Analysis of the three dimensional core kinetics NESTLE code coupling with the advanced thermo-hydraulic code systems, RELAP5/SCDAPSIM and its application to the Laguna Verde Central reactor

International Nuclear Information System (INIS)

Salazar C, J.H.; Nunez C, A.; Chavez M, C.

2004-01-01

The objective of the written present is to propose a methodology for the joining of the codes RELAP5/SCDAPSIM and NESTLE. The development of this joining will be carried out inside a doctoral program of Engineering in Energy with nuclear profile of the Ability of Engineering of the UNAM together with the National Commission of Nuclear Security and Safeguards (CNSNS). The general purpose of this type of developments, is to have tools that are implemented by multiple programs or codes such a that systems or models of the three-dimensional kinetics of the core can be simulated and those of the dynamics of the reactor (water heater-hydraulics). In the past, by limitations for the calculation of the complete answer of both systems, the developed models they were carried out for separate, putting a lot of emphasis in one but neglecting the other one. These methodologies, calls of better estimate, will be good to the nuclear industry to evaluate, with more high grades of detail, the designs of the nuclear power plant (for modifications to those already existent or for new concepts in the designs of advanced reactors), besides analysing events (transitory and have an accident), among other applications. The coupled system was applied to design studies and investigation of the Laguna Verde Nuclear power plant (CNLV). (Author)

Evaluation of the reduction of boron-10 in the control rods in the BWR of the Laguna Verde Central, through steady state calculations

International Nuclear Information System (INIS)

Montes T, J.L.; Perusquia, R.; Hernandez, J.L.; Ramirez S, J.R.

2003-01-01

One of the more important aspects related with the safety and economy in the operation of a nuclear power reactor, it is without a doubt the control of the reactivity. During the normal operation of a reactor of boiling water (BWR-Boiling Water Reactor), the control of the reactivity in the nucleus it is strongly determined by the efficiency of the control rods. In the case of the Laguna Verde Nuclear power station (CNLV) the nucleus of the reactors has 109 control rods grouped in 4 sets. The CNLV at the moment uses the CCC method (Control Cell Core) in the design of the cycle. With this method only the A2 group is used for the control of the reactivity at full power. With the purpose of quantifying the effect of the decrease of the burnable poison (B 4 C) of the control rods and in particular to the effect due to the postulated lost of 10% of Boron 10, it was carried out a series of calculations of the nucleus in stationary state by means of the system of HELIOS/CM-PRESTO codes. In this work the main derived results of these 3D simulations(three dimensions) of the reactors of the CNLV are presented. It was analyzed the one behavior of the infinite neutron multiplication factor (K infinite ), at fuel assemble cell level used in an equilibrium cycle for the CNLV. It was also analyzed the effect in the shutdown margin (ShutDown Margin- SDM) in cold condition CZP (Cold Zero Power). Its are also included those results of the ARI cases (All Rods In) and SRO (Strong Rod Out). From the cases in condition HFP (Hot Full Power) the behavior of the effective multiplication factor (K eff ) is presented. (Author)

Radiological analysis by the addition of hydrogen and noble metals in the reactors of the Laguna Verde central

International Nuclear Information System (INIS)

Padilla C, I.

2006-01-01

and of the radiological behavior when applying them, its allowed to settle down strategies in the Laguna Verde Central to control and to reduce the magnitude of the radiological increment in the primary steam lines in both units during the initial period of application. The radiological effects by the addition of hydrogen and of the noble metals, and its incorporation sequence to the reactor are the one reason of this work. (Author)

Using largest Lyapunov exponent to confirm the intrinsic stability of boiling water reactors

International Nuclear Information System (INIS)

Gavilian-Moreno, Carlos; Espinosa-Paredes, Gilberto

2016-01-01

The aim of this paper is the study of instability state of boiling water reactors with a method based in largest Lyapunov exponents (LLEs). Detecting the presence of chaos in a dynamical system is an important problem that is solved by measuring the LLE. Lyapunov exponents quantify the exponential divergence of initially close state-space trajectories and estimate the amount of chaos in a system. This method was applied to a set of signals from several nuclear power plant (NPP) reactors under commercial operating conditions that experienced instabilities events, apparently each of a different nature. Laguna Verde and Forsmark NPPs with in-phase instabilities, and Cofrentes NPP with out-of-phases instability. This study presents the results of intrinsic instability in the boiling water reactors of three NPPs. In the analyzed cases the limit cycle was not reached, which implies that the point of equilibrium exerts influence and attraction on system evolution

Using largest Lyapunov exponent to confirm the intrinsic stability of boiling water reactors

Energy Technology Data Exchange (ETDEWEB)

Gavilian-Moreno, Carlos [Iberdrola Generacion, S.A., Cofrentes Nuclear Power Plant, Project Engineering Department, Paraje le Plano S/N, Valencia (Spain); Espinosa-Paredes, Gilberto [Area de ingeniera en Recursos Energeticos, Universidad Autonoma Metropolitana-Iztapalapa, Mexico city (Mexico)

2016-04-15

The aim of this paper is the study of instability state of boiling water reactors with a method based in largest Lyapunov exponents (LLEs). Detecting the presence of chaos in a dynamical system is an important problem that is solved by measuring the LLE. Lyapunov exponents quantify the exponential divergence of initially close state-space trajectories and estimate the amount of chaos in a system. This method was applied to a set of signals from several nuclear power plant (NPP) reactors under commercial operating conditions that experienced instabilities events, apparently each of a different nature. Laguna Verde and Forsmark NPPs with in-phase instabilities, and Cofrentes NPP with out-of-phases instability. This study presents the results of intrinsic instability in the boiling water reactors of three NPPs. In the analyzed cases the limit cycle was not reached, which implies that the point of equilibrium exerts influence and attraction on system evolution.

Using Largest Lyapunov Exponent to Confirm the Intrinsic Stability of Boiling Water Reactors

Directory of Open Access Journals (Sweden)

Carlos J. Gavilán-Moreno

2016-04-01

Full Text Available The aim of this paper is the study of instability state of boiling water reactors with a method based in largest Lyapunov exponents (LLEs. Detecting the presence of chaos in a dynamical system is an important problem that is solved by measuring the LLE. Lyapunov exponents quantify the exponential divergence of initially close state-space trajectories and estimate the amount of chaos in a system. This method was applied to a set of signals from several nuclear power plant (NPP reactors under commercial operating conditions that experienced instabilities events, apparently each of a different nature. Laguna Verde and Forsmark NPPs with in-phase instabilities, and Cofrentes NPP with out-of-phases instability. This study presents the results of intrinsic instability in the boiling water reactors of three NPPs. In the analyzed cases the limit cycle was not reached, which implies that the point of equilibrium exerts influence and attraction on system evolution.

Ultrasonic meters in the feedwater flow to recover thermal power in the reactor of nuclear power plant of Laguna Verde U1 and U2; Medidores ultrasonicos en el flujo de agua de alimentacion para recuperar potencia termica en el reactor de la Central Nuclear Laguna Verde U1 and U2

Energy Technology Data Exchange (ETDEWEB)

Tijerina S, F. [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)]. e-mail: francisco.tijerina@cfe.gob.mx

2008-07-01

The engineers in nuclear power plants BWRs and PWRs based on the development of the ultrasonic technology for the measurement of the mass, volumetric flow, density and temperature in fluids, have applied this technology in two primary targets approved by the NRC: the use for the recovery of thermal power in the reactor and/or to be able to realize an increase of thermal power licensed in a 2% (MUR) by 1OCFR50 Appendix K. The present article mentions the current problem in the measurement of the feedwater flow with Venturi meters, which affects that the thermal balance of reactor BWRs or PWRs this underestimated. One in broad strokes describes the application of the ultrasonic technology for the ultrasonic measurement in the flow of the feedwater system of the reactor and power to recover thermal power of the reactor. One is to the methodology developed in CFE for a calibration of the temperature transmitters of RTD's and the methodology for a calibration of the venturi flow transmitters using ultrasonic measurement. Are show the measurements in the feedwater of reactor of the temperature with RTD's and ultrasonic measurement, as well as the flow with the venturi and the ultrasonic measurement operating the reactor to the 100% of nominal thermal power, before and after the calibration of the temperature transmitters and flow. Finally, is a plan to be able to realize a recovery of thermal power of the reactor, showing as carrying out their estimations. As a result of the application of ultrasonic technology in the feedwater of reactor BWR-5 in Laguna Verde, in the Unit 1 cycle 13 it was recover an equivalent energy to a thermal power of 25 MWt in the reactor and an exit electrical power of 6 M We in the turbogenerator. Also in the Unit 2 cycle 10 it was recover an equivalent energy to a thermal power of 40 MWt in the reactor and an exit electrical power of 16 M We in the turbogenerator. (Author)

Development of the stationary state and simulation of an accident severe stage type station blackout with the MELCOR code version 1.8.6 for the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Mugica R, C. A.; Godinez S, V.

2011-11-01

Considering the events happened since the 11 March of 2011, in Japan, where an earthquake of 9.1 grades Ritcher of intensity and a later tsunami impacted in an important way the operation of a nuclear power plant located in the Fukushima, Japan; damaging and disabling their cooling systems and injection of emergency water due to the total loss of electric power (commonly denominated Station Blackout), is eminent the analysis of this stage type that took to the nuclear power plant to conditions of damage to the core and explosions generation by hydrogen concentrations in the reactor building. In this work an analysis of a stage type station blackout is presented, using the model of the nuclear power plant of Laguna Verde starting of the stationary state. The analysis is carried out using the MELCOR code (Methods for Estimation of Leakages and Consequences of Releases) version 1.8.6 whose purpose is to model the accidents progression for light water reactors. The obtained results are qualitatively similar to the events observed in the Fukushima nuclear power plant even though limitations exist to achieve a precise simulation of the events happened in Japan, such as the information flow of the chronology of the operator actions, as well as of the characteristic design of the power plant, volumes in cavities and rooms, water/cooling inventories, interconnected systems and their own emergency procedures or guides for the administration of severe accidents among others. (Author)

Talento verde y cadenas de suministro verdes: ¿existe una relación significativa?

Directory of Open Access Journals (Sweden)

María del Carmen Torres-Salazar

2016-01-01

Full Text Available Introducción: En este texto se presentan resultados estadísticos de la relación entre directivos con características de talento verde y la implementación de prácticas de cadena de suministro verde. Debido a que existen investigaciones sobre la importancia de la visión de la alta dirección para la adopción de prácticas verdes; y sin embargo ninguna da cuenta de las características personales del directivo, ni tampoco de la relación significativa entre estas características y la puesta en marcha de prácticas de cadena de suministro verde, esta es la aportación de la presente investigación. El trabajo se desarrolló en empresas manufactureras con más de diez trabajadores de la zona oriente del estado de Morelos México. La caracterización del término talento verde se reportó en el artículo, Talento verde: caracterización y búsqueda, publicado en el número 14 de esta revista. Método: El método utilizado consistió en la construcción de una encuesta dividida en tres categorías que posteriormente se convirtieron en variables: prácticas de cadena de suministro verde, presiones institucionales y talento verde. Las dos primeras se adaptaron de la encuesta de Zhu y Sarkis (2007 y la tercera surgió de la representación social de talento verde, producto de una fase de esta investigación. La encuesta se validó con un grupo de empresarios miembros de la Cámara Nacional de la Industria de la Transformación (CANACINTRA capítulo Morelos. El instrumento validado se aplicó a 26 directivos de empresas manufactureras con más de diez trabajadores de la zona oriente de Morelos, con el fin de probar la relación entre directivos con características de talento verde y la puesta en marcha de prácticas de cadena de suministro verde. Para ello se utilizaron como herramientas estadísticas la correlación de Pearson y la regresión lineal múltiple. Resultados: Las prácticas de cadena de suministro verde de las empresas

Ultrasonic meters in the feedwater flow to recover thermal power in the reactor of nuclear power plant of Laguna Verde U1 and U2

International Nuclear Information System (INIS)

Tijerina S, F.

2008-01-01

The engineers in nuclear power plants BWRs and PWRs based on the development of the ultrasonic technology for the measurement of the mass, volumetric flow, density and temperature in fluids, have applied this technology in two primary targets approved by the NRC: the use for the recovery of thermal power in the reactor and/or to be able to realize an increase of thermal power licensed in a 2% (MUR) by 1OCFR50 Appendix K. The present article mentions the current problem in the measurement of the feedwater flow with Venturi meters, which affects that the thermal balance of reactor BWRs or PWRs this underestimated. One in broad strokes describes the application of the ultrasonic technology for the ultrasonic measurement in the flow of the feedwater system of the reactor and power to recover thermal power of the reactor. One is to the methodology developed in CFE for a calibration of the temperature transmitters of RTD's and the methodology for a calibration of the venturi flow transmitters using ultrasonic measurement. Are show the measurements in the feedwater of reactor of the temperature with RTD's and ultrasonic measurement, as well as the flow with the venturi and the ultrasonic measurement operating the reactor to the 100% of nominal thermal power, before and after the calibration of the temperature transmitters and flow. Finally, is a plan to be able to realize a recovery of thermal power of the reactor, showing as carrying out their estimations. As a result of the application of ultrasonic technology in the feedwater of reactor BWR-5 in Laguna Verde, in the Unit 1 cycle 13 it was recover an equivalent energy to a thermal power of 25 MWt in the reactor and an exit electrical power of 6 M We in the turbogenerator. Also in the Unit 2 cycle 10 it was recover an equivalent energy to a thermal power of 40 MWt in the reactor and an exit electrical power of 16 M We in the turbogenerator. (Author)

Soil transfer function obtention by Wiener's optimum filter

International Nuclear Information System (INIS)

Flores Ruiz, J.H.

1987-01-01

Transfer function in nuclear power plant Laguna Verde, Veracruz, using Wiener filter. This paper deal with identification of complex structural and soil-interaction systems often are modeling in nuclear industry. Nonparametric identification techniques are used to analyse the response of a class nonlinear vibrations. Efficient computational algorithms and experimental techniques based input-output system methods such as the Wiener-Kernel approach and least-square regression techniques are applied to get the transfer function in nuclear power plant Laguna Verde, Veracruz (Mexico) (Author)

Komposisi dan Kemelimpahan Fitoplankton di Laguna Glagah Kabupaten Kulonprogo Provinsi Daerah Istimewa YOGYAKARTA

OpenAIRE

Ramadani, Aisyah Hadi; Wijayanti, Arini; Hadisusanto, Suwarno

2013-01-01

Penelitian bertujuan untuk: 1) mengidentifikasi jenis fitoplankton di laguna Glagah; 2) meng-identifikasi kemelimpahan fitoplankton di laguna Glagah; 3) mempelajari hubungan faktor fisiko-kimia lingkungan dengan kemelimpahan fitoplankton di laguna Glagah. Penelitian dilaksanakan pada tanggal 10 Desember 2012 di laguna Glagah desa Glagah kecamatan Temon Kabupaten Kulonprogo DIY. Pengambilan sampel dilakukan pada 3 stasiun pengamatan untuk mengidentifikasi faktor fisiko-kimia (pH, DO, dan al...

Charpy V, an application in Mat lab

International Nuclear Information System (INIS)

Castillo M, J.A.; Torres V, M.

2003-01-01

The obtained results with the system Charpy V V 1 designed in Mat lab for the estimate of parameters of three mathematical models are shown. The adjustment of data is used to determine the fracture energy, the lateral expansion and the percentage of ductility of steels coming from the reactor vessels of Laguna Verde, Veracruz. The data come from test tubes type Charpy V of irradiated material and not irradiated. To verify our results they were compared with those obtained by General Electric of data coming from the Laguna Verde nuclear power plant. (Author)

Charpy V, an application in Mat lab; Charpy V, una aplicacion en Matlab

Energy Technology Data Exchange (ETDEWEB)

Castillo M, J.A.; Torres V, M. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2003-07-01

The obtained results with the system Charpy V{sub V}1 designed in Mat lab for the estimate of parameters of three mathematical models are shown. The adjustment of data is used to determine the fracture energy, the lateral expansion and the percentage of ductility of steels coming from the reactor vessels of Laguna Verde, Veracruz. The data come from test tubes type Charpy V of irradiated material and not irradiated. To verify our results they were compared with those obtained by General Electric of data coming from the Laguna Verde nuclear power plant. (Author)

Future perspectives in neutrino physics: The Laguna-LBNO case

CERN Document Server

Buizza Avanzini, M

2013-01-01

LAGUNA-LBNO is a Design Study funded by the European Commission to develop the de- sign of a deep underground neutrino observatory; its physics program involves the study of neutrino oscillations at long baselines, the investigation of the Grand Unication of elemen- tary forces and the detection of neutrinos from known and unknown astrophysical sources. Building on the successful format and on the ndings of the previous LAGUNA Design Study, LAGUNA-LBNO is more focused and is specically considering Long Baseline Neutrino Oscil- lations (LBNO) with neutrino beams from CERN. Two sites, Frejus (in France at 130 km) and Pyhasalmi (in Finland at 2300 km), are being considered. Three dierent detector technolo- gies are being studied: Water Cherenkov, Liquid Scintillator and Liquid Argon. Recently the LAGUNA-LBNO consortium has submitted an Expression of Interest for a very long baseline neutrino experiment, selecting as a rst priority the option of a Liquid Argon detector at Pyhasalmi.

Cabo Verde - Private Sector Development

Data.gov (United States)

Millennium Challenge Corporation — The objective of the Private Sector Development Project activities of the 2005-2010 Cabo Verde Compact was to support Cabo Verde's long-term economic transformation...

The nuclear power electricity an opportunity for Mexico. Final report

International Nuclear Information System (INIS)

Fernandez de la Garza, R.; Garcia, C. F.; Trejo R, S.; Zazueta R, T.; Castaneda G, M. A.; Cruz B, H. J.; Mercado V, J. J.

2009-01-01

Inside this document the outstanding information is presented included in the report that develops the technical, financial, environmental and social aspects to consider for the incorporation from a new power plant to the national interconnected system, which was elaborated and presented to the nuclear power plant of Laguna Verde in August of 2009. The treated topics are: the nuclear power electricity, the experience of Laguna Verde, advanced reactors to consider for a new nuclear power plant, environmental aspects, costs of a new nuclear power plant, financing, socioeconomic impact. This work was prepared to evaluate the feasibility of building a new unit of nuclear power plant in Mexico before the evident resurgence at world level of use of nuclear energy to generate electricity. It is important that Mexico maintains inside its development programs and construction, to the nuclear power electricity like a viable and sure alternative of generating electricity, being able to take advantage of experience won with the operation of Laguna Verde, allowing that the country has diverse technologies for electricity generation and have technical capacity to manage the tip technology. (Author)

Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV

International Nuclear Information System (INIS)

Serrano R, M. L.

2015-09-01

This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the

Estudio Limnológico preliminar de la Laguna Hule, Costa Rica

Directory of Open Access Journals (Sweden)

Elizabeth Ramírez R.

2016-03-01

Full Text Available La Laguna Hule, localizada en la Vertiente Caribe, Costa Rica a 750m sobre el nivel del mar, forma parte del complejo de lagunas volcánicas llamado “Bosque Alegre”. El área de la laguna es de 60.3 ha y su profundidad máxima de 22.5m. La investigación se realizó de abril a setiembre de 1989 determinándose, en cada muestreo la temperatura, el óxido disuelto, el ácido sulfhídrico (H2S, el pH, la alcalinidad y la concentración de iones calcio, magnesio, hierro y manganeso. La laguna presenta un perfil clinógrado de oxígeno; el 60% del volumen total es anóxico con presencia de H2S a partir de los 8m de profundidad. Los valores de pH y alcalinidad indican que las aguas son bicarbonatadas, caracterizándose por un alto contenido de hierro. La curva de temperatura señala una diferencia de hasta 4.3 °C entre la superifcie y el fondo, permitiendo a la laguna permanecer estratificada (hay un epilimnion y un hipolimnion bien definido.

Ouro Verde MG 2: nova cultivar de mungo-verde para Minas Gerais Ouro Verde MG 2: new mungbean cultivar for Minas Gerais State, Brazil

Directory of Open Access Journals (Sweden)

Rogério F. Vieira

2002-03-01

Full Text Available Dentre várias linhagens introduzidas do "Asian Vegetable Research and Development Center" (AVRDC, sobressaiu a linhagem VC 3984-B-2-B-4-1-B, que recebeu o nome de Ouro Verde MG 2. Suas sementes são verde-brilhantes e o peso de 1000 unidades varia de 43 a 51 g. O início da floração ocorre em torno de 33 dias após a emergência e a primeira vagem madura surge entre 23 e 33 dias. Por se tratar de espécie de maturação desuniforme, podem ser necessárias duas a quatro colheitas. As plantas podem atingir 95 cm de altura. As vagens são marrom-escuras e concentram-se na parte superior da planta. É suscetível a duas doenças que geralmente aparecem no final do ciclo de vida do mungo-verde: míldio-pulverulento (Erysiphe polygoni e mancha-foliar-de-cercospora (Cercospora canescens. A 'Ouro Verde MG 2' é resistente ao acamamento, e o seu rendimento, em três ensaios instalados em dezembro, janeiro e fevereiro, variou de 1,5 a 2,0 t/ha. Esses rendimentos foram, em média, 12% superior ao da cultivar Ouro Verde.Among many accessions introduced from Asian Vegetable Research and Development Center (AVRDC, the VC 3984-B-2-B-4-1-B stood out and was named 'Ouro Verde MG 2'. The seeds are bright green and 1000-seed weight ranges from 43 to 51 g. Flowering starts approximately 33 days after emergence and the first pod ripens between 23 and 33 days later. As mungbean is a non-uniform maturation species, two to four harvests could be necessary. The plant can reach 95 cm high. The pods are dark brown and concentrated in the upper canopy. This cv. is susceptible to two diseases which generally appear late in the crop: powdery mildew (Erysiphe polygoni and cercospora leaf spot (Cercospora canescens. 'Ouro Verde MG 2' is resistant to lodging. The yield measured in three experiments carried out in December, January, and February, ranged from 1.5 to 2.0 t/ha. In average, these yields were 12% superior than the achieved by the cultivar 'Ouro Verde'.

Inventario nacional de lagunas y represamientos: segunda aproximación

OpenAIRE

Oficina Nacional de Evaluación de Recursos Naturales

1980-01-01

Contiene el inventario de las lagunas y represamientos existentes en el territorio nacional, destinado a establecer la capacidad física de regulación de los ríos del país. El inventario comprende un listado y descripción sistemática de las lagunas y represamientos en explotación, en estudios o sin uso.

An evaluation on the design optimization of large capacity tanks in the chemical and volume control system for YGN 3 and 4

International Nuclear Information System (INIS)

Park, Byung Ho; Kim, Eun Ki; Ko, Deuk Yoon; Ko, Yong Sang; Kim, Seok Bum

1996-06-01

The design of Yonggwang nuclear power plant units 3 and 4 (YGN 3 and 4) is referenced to that of Palo Verde nuclear power plant (Palo Verde NPP) in Arizona, USA. The reactor vessel and steam generator of YGN 3 and 4 are smaller than that of Palo Verde NPP because Palo Verde NPP produces 1,300 Mw electricity, on the other hand, YGN 3 and 4 produces 1,000 Mw electricity. However, other components and systems of YGN 3 and 4 are the same as those of Palo verde NPP. The oversized system components may be considered to ensure the safety and operability by providing sufficient design margin, but it requires unnecessary cost burden to the owner of the plant. This report focuses on the optimization of the volume of the large tanks (i.e., above 400,000 gallons) in CVCS. These tanks are refueling water tank (RWT), reactor makeup water tank (RMWT) and holdup tank (HT). It has been performed that the calculation on the required tank volume based on design requirements, comparison on the calculation results with as-built design, and estimation on the instrumentation setpoint. 19 tabs., 12 figs., 13 refs. (Author)

2013 Tres Lagunas Post Fire, 12

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 5

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 30

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 14

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 26

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 3

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 33

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 8

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 18

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 11

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 17

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 27

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 6

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 24

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 4

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 21

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 7

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 32

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 1

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 28

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 9

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 35

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 31

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

2013 Tres Lagunas Post Fire, 34

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — USDA USFS Southwestern Region Contract # AG-8371-C-10-0011 Delivery # AG-8371-D-13-0056 DIGITAL PHOTOGRAPHY ACQUISITION, TRES LAGUNAS FIRE, NEW MEXICO Project...

Calculation and analysis of hydrogen volume concentrations in the vent pipe rigid proposed for NPP-L V

International Nuclear Information System (INIS)

Gomez T, A. M.; Xolocostli M, V.; Lopez M, R.; Filio L, C.; Royl, P.

2014-10-01

In 2012 was modeled of primary and secondary container of the nuclear power plant of Laguna Verde (NPP-L V) for the CFD Gas-Flow code. These models were used to calculate hydrogen volume concentrations run release the reactor building in case of a severe accident. The results showed that the venting would produce detonation conditions in the venting level (level 33) and flammability at ground level of reload. One of the solutions to avoid reaching critical concentrations (flammable or detonable) inside the reactor building and thus safeguard the contentions is to make a rigid venting. The rigid vent is a pipe connected to the primary container could go to the level 33 of the secondary container and style fireplace climb to the top of the reactor building. The analysis of hydrogen transport inside the vent pipe can be influenced by various environmental criteria and factors vent, so a logical consequence of the 2012 analysis is the analysis of the gases transport within said pipe to define vent ideal conditions. For these evaluations the vent pipe was modeled with a fine mesh of 32 radial interior nodes and a coarse mesh of 4 radial interior nodes. With three-dimensional models were realized calculations that allow observing the influence of heat transfer in the long term, i.e. a complete analysis of exhaust (approx. 700 seconds). However, the most interesting results focus on the first milliseconds, when the H 2 coming from the atmosphere of the primary container faces the air in the vent pipe. These first milliseconds besides allowing evaluating the detonation criteria in great detail in the different tubular sections similarly allow evaluating the pressure wave that occurs in the pipe and that at some point slows to the fluid on the last tubular section and could produce a detonation inside the pipe. Results are presented for venting fixed conditions, showing possible detonations into the pipe. (Author)

36 CFR 7.39 - Mesa Verde National Park.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Mesa Verde National Park. 7... SPECIAL REGULATIONS, AREAS OF THE NATIONAL PARK SYSTEM § 7.39 Mesa Verde National Park. (a) Visiting of... the admission of commercial automobiles and buses to Mesa Verde National Park, contained in § 5.4 of...

Graphic console for analysis of severe accidents visualization of OEs, NAEs and calculation of the source term for the NPP-LV (CoGrAAS)

International Nuclear Information System (INIS)

Sandoval V, S.; Mendoza E, P. R.; Gonzalez C, J. M.; Cecenas F, M.; Tijerina S, F.

2016-09-01

In response to the Fukushima Daiichi nuclear power plant accident, the NRC conducted an analysis and issued recommendations to improve the safety of the nuclear reactors. These include strengthening and integrating emergency response capabilities and emphasizing periodic staff training, the performance of simulation exercises. As a tool to observe these recommendations, the Graphic Console was developed for Analysis of Severe Accidents, Visualization of OEs, NAEs and calculation of the source term for nuclear power plant of Laguna Verde (NPP-LV ; CoGrAAS). The CoGrAAS is a computer system that displays in an integrated, graphic and dynamic way the information of a catalog of previously simulated accident scenarios. Has core mimics, vessel, primary containment and safety systems, trend graph of thermodynamic and radiological variables and the emergency procedures (OEs), chronological list of events, windows with detailed information for the dry-well, among others. The use of CoGrAAS allows that staff to understand and become familiar with the thermo-hydraulic progression of actual scenarios that exceed the design basis including those with core damage as severe accidents. The system enables personnel to develop an integral vision of the scenarios during the exercises and drills by observing and analyzing the evolution of the main reactor, core and primary containment variables, the response of emergency systems and the influence of that progression on OEs and the emergency action levels (NAEs). The CoGrAAS allows o observe the radiological variables and obtain the source term, to make the projection of doses, at any time within the scenario evolution. Thus, not only can the phenomenology of severe accidents be analyzed and understood, it is also possible to exercise, verify and evaluate the performance of critical tasks in the application of procedures, guidelines and emergency management plans. (Author)

Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico

Energy Technology Data Exchange (ETDEWEB)

Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2012-10-15

So that the construction stages, of operation, closing, dismantlement and the radioactive waste disposal of a nuclear power plant (NPP) are carried out in Mexico, is necessary that the operator has a license, permission or authorization for each stage. In Mexico, these licenses, permissions or authorizations are granted by the Energy Secretariat with base in the verdict of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The operation licenses ar the moment effective for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) they will expire respectively in the year 2020 and 2025 for the Unit 1 and Unit 2, for what the CNSNS has begun its preparation before a potential solicitude of the licensee to continue the operation of the NPP-L V. Defining the process to continue and to generate the documents that would help in this phase as normalization, guides, procedures, regulations, controls, etc., is the task that intends to be carried out the regulator body so that the evaluation process is effective and efficient, so much for the same regulator body as for the licensee. This work exposes the advance that the CNSNS has in this aspect and is centered specifically in the conformation of an evaluation process of license renovation solicitude, taking as base what the regulator body of the United States of North America (US NRC) established and following to the IAEA. Also, this work includes statistical of electric power production in Mexico, licensing antecedents for the NPP-L V, a world perspective of the license renovations and the regulation of the US NRC related to the license renovation of a NPP. (Author)

Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico

International Nuclear Information System (INIS)

Serrano R, M. L.

2012-10-01

So that the construction stages, of operation, closing, dismantlement and the radioactive waste disposal of a nuclear power plant (NPP) are carried out in Mexico, is necessary that the operator has a license, permission or authorization for each stage. In Mexico, these licenses, permissions or authorizations are granted by the Energy Secretariat with base in the verdict of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). The operation licenses ar the moment effective for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) they will expire respectively in the year 2020 and 2025 for the Unit 1 and Unit 2, for what the CNSNS has begun its preparation before a potential solicitude of the licensee to continue the operation of the NPP-L V. Defining the process to continue and to generate the documents that would help in this phase as normalization, guides, procedures, regulations, controls, etc., is the task that intends to be carried out the regulator body so that the evaluation process is effective and efficient, so much for the same regulator body as for the licensee. This work exposes the advance that the CNSNS has in this aspect and is centered specifically in the conformation of an evaluation process of license renovation solicitude, taking as base what the regulator body of the United States of North America (US NRC) established and following to the IAEA. Also, this work includes statistical of electric power production in Mexico, licensing antecedents for the NPP-L V, a world perspective of the license renovations and the regulation of the US NRC related to the license renovation of a NPP. (Author)

Impact on the bar value in hot by the introduction of advanced control bars in the Unit 1 of the Laguna Verde Nuclear power plant; Impacto sobre el valor de barra en caliente por la introduccion de barras de control avanzadas en la U1 de la CNLV

Energy Technology Data Exchange (ETDEWEB)

Montes, J.L.; Perusquia, R.; Ortiz, J.J.; Hernandez, J.L.; Ramirez, J.R. [ININ, Carretera Mexico-Toluca Km. 36.5, 52045 Estado de Mexico (Mexico)]. e-mail: jlmt@nuclear.inin.mx

2004-07-01

In recent dates the Laguna Verde Nuclear Power station (CNLV) has acquired new designs of control bars, this new type of bars presents modifications important in their design. For what is important to analyze their performance inside those reactors of this nuclear power station. Presently work is shown the behavior of the nucleus of the reactor in hot condition (HFP) when three different types of control bar are used. The first of them corresponds the one that initially has been used in this power station and that we will call original. The second type of control bars, it corresponds to an advanced type and it is the first design different from the original and it corresponds to a bar design that it includes Hafnium (Hf) like one of their neutronic absorption characteristics. The third, denoted as 2AV, include besides the material of the second type new design characteristics, and it is the last finish bar type that it has been introduced in the operation of the reactors of the CNLV. With base in the studied cases is found that the bars 2AV have a total power value, 7.6 % bigger respect the bars 1AV; and in turn the bars 1AV, 6.1 % bigger with respect the ORG control bars. (Author)

Condiciones sedimentológicas de la laguna la restinga, isla de margarita, venezuela

OpenAIRE

C, Julio; Salazar, L; A, Jesús; C, Rosas; C, Julio; Rodríguez, R

2003-01-01

Resumen La laguna La Restinga, en el sureste del Mar Caribe, es una laguna costera que comprende pequeñas lagunas rodeadas de manglares, conformando el sistema lagunar más importante de la Isla de Margarita. Se comunica con el mar, al sur, a través de una boca de 800m de largo, 80-100m de ancho y profundidad promedio de 6m. Está separada del mar, al norte, por un istmo o restinga de 23,5km, y sus drenajes naturales se evidencian solamente en la época de lluvia. Se estudiaron algunos aspectos ...

Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

International Nuclear Information System (INIS)

Egorov, Yu.A.

1987-01-01

Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

Design Study for a Future Laguna-LBNO Long-Baseline Neutrino Facility at CERN

CERN Document Server

Alabau-Gonzalvo, J; Antoniou, F; Benedikt, M; Calviani, M; Efthymiopoulos, I; Ferrari, A; Garoby, R; Gerigk, F; Gilardoni, S; Goddard, B; Kosmicki, A; Lazaridis, C; Osborne, J; Papaphillippou, Y; Parfenova, A; Shaposhnikova, E; Steerenberg, R; Velten, P; Vincke, H

2013-01-01

The Large Apparatus studying Grand Unification and Neutrino Astrophysics (LAGUNA) study [1] investigated seven pre-selected underground sites in Europe (Finland, France, Italy, Poland, Romania, Spain and UK), capable of housing large volume detectors for terrestrial, accelerator generated and astrophysical neutrino research. The study was focused on geo-technical assessment of the sites, concluding that no show-stoppers exist for the construction of the required large underground caverns in the chosen sites. The LAGUNA-LBNO FP7/EC-funded design study extends the LAGUNA study in two key aspects: the detailed engineering of detector construction and operation, and the study of a long-baseline neutrino beam from CERN, and possibly other accelerator centres in Europe. Based on the findings of the LAGUNA study, the Pyh¨asalmi mine in Finland is chosen as prime site for the far detector location. The mine offers the deepest underground location in Europe (-1400 m) and a baseline of 2’300 km from CERN (Fig. 1). ...

Technology for NPP decantate treatment realized at Kola NPP

International Nuclear Information System (INIS)

Stakhiv, Michael; Avezniyazov, Slava; Savkin, Alexander; Fedorov, Denis; Dmitriev, Sergei; Kornev, Vladimir

2007-01-01

At Moscow SIA 'Radon' jointly with JSC 'Alliance Gamma', the technology for NPP Decantate Treatment was developed, tested and realized at Kola NPP. This technology consists of dissolving the salt residue and subsequent treatment by ozonization, separation of the deposits formed from ozonization and selective cleaning by ferro-cyanide sorbents. The nonactive salt solution goes to an industrial waste disposal site or a repository specially developed at NPP sites for 'exempt waste' products by IAEA classification. This technology was realized at Kola NPP in December 2006 year. At this time more than 1000 m 3 of decantates log time stored are treated. It allows solving very old problem to empty decantates' tanks at NPPs in environmentally safe manner and with high volume reduction factor. (authors)

Scenarios catalog for the graphical console for analysis of severe accidents visualization of OEs, NAEs and calculation of source term of the NPP-LV

International Nuclear Information System (INIS)

Sandoval V, S.; Mendoza R, M. E.; Tijerina S, F.; Garcia C, T.

2016-09-01

A nuclear power plant is operated at all times within the design criteria of structures, systems and components, and according to the operation technical specifications. For different areas of work of a nuclear power plant is necessary to carry out practices in which is useful to have the prediction of the thermo-hydraulic and radiological progression of scenarios that imply exceeding that design bases, even reaching the damage of the fuel in different degree. During the exercises and drills of the External Plan of Emergency Response, the projection of doses is done to exercise the different tasks of the plan. To make the projection of doses is required to have the radiological source term of the scenario on which is practiced. Because of this, was identified the convenience of having a catalog of scenarios for which the radiological source term was calculated. In 2004, a first version of the catalog was produced for a power of 2027 MW, and in 2011 the catalog was updated for extended power conditions, 2317 MW. Both versions were made using the severe accident simulator MAAP-3B. That catalog consists of a form and an optical storage device. The form contains tables and figures in which the characteristics of the scenario to be practiced are searched and the electronic files of the corresponding radiological source term are located in the storage device. Due to the recent development of the graphical console for analysis of severe accidents, visualization of OEs, NAEs and calculation of the source term for the nuclear power plant of Laguna Verde (NPP-LV) CoGrAAS, the catalog printed was replaced by an electronic catalog for the CoGrAAS. The new catalog retains the philosophy of the previous catalog, constituted by a wide collection of scenarios that involve different circumstances and phenomena, that can be used to practice different tasks during training exercises or simulacrums, and combined with the following advantages: the scenario selection is made from an

Palo Verde nuclear dynamic analysis (PANDA)

International Nuclear Information System (INIS)

Girjashankar, P.V.; Secker, P.A. Jr.; LeClair, S.J.; Mendoza, J.; Webb, J.R.

1988-01-01

Arizona Nuclear Power Project (ANPP) has initiated the development of a large scale dynamic analysis computer program for the Palo Verde Nuclear Generating Station (PVNGS). This paper presents the decision processes and preliminary development activities that have been pursued related to the code development. The PANDA (Palo Verde Nuclear Dynamic Analysis) code will be used for a variety of applications as described in this paper

Botanical ecology and conservation of the Laguna de la Herrera (Sabana de Bogotá, Colombia Botanical ecology and conservation of the Laguna de la Herrera (Sabana de Bogotá, Colombia

Directory of Open Access Journals (Sweden)

Wijninga V. M.

1989-09-01

Full Text Available The acuatic, helophytic and pleustophytic vegetation of the Laguna de La Herrera, on the southwestern border of the high plain of Bogotá at 2550 m was studied following the Zurich- Montpellier approach. The communities recognized were: terrestrial community of Phytolacca bogotensis; helophytic communities of scirpus californicus and Typha angustifolia ; scirpus californicus ; Polygonum punctatum ; Rumex obtusifolius with Polygonum punctatum; Bidens laevis ; Hydrocotyle ranunculoides. Pleustophytic communities of Limnobium laevigatum; Azolla filiculoides with Lemna cf. gibba and Eichornia crassipes. The structure, floristic composition and ecological aspects were also considered. Several recommendations about conservation of the Laguna are given. Se estudió la vegetación alrededor de la Laguna de La Herrera, una laguna andina a 2550 m. Se diferenciaron una comunidad de Phytolacca bogotensis (1: comunidades helofíticas dominadas por: Scirpus californicus y Typha angustifolia (2; Scirpus californicus (3; Polygonum punctatum (4; Rumex obtusifolius y Polygonum punctatum (5; Bidens laevis (6; Hydrocotyle ranunculoides (7; comunidades pleustofíticas con: Limnobium laevigatum; (8; Azolla filiculoides y Lemna cf. gibba (9 y Eichhornia crassipes (10. Se registraron la estructura, composición florística, los rasgos ecológicos y la distribución de las comunidades y se comparó con la conductividad eléctrica y la calidad del agua. Finalmente, se hacen recomendaciones para la conservación de la laguna y la vegetación acuática.

Decommissioning of Brennilis NPP

International Nuclear Information System (INIS)

Baize, Jean-Marc

1998-01-01

This EDF press communique give information related to the decommissioning of the Brennilis NPP. The following five items are developed in this report: 1. the level-2 decommissioning operations at the Brennilis NPP; 2. the Brennilis NPP, a pilot operation from the commissioning up to the decommissioning; 3. history of the Brennilis NPP decommissioning; 4. the types of radioactive wastes generated by the Brennilis NPP decommissioning; 5. the Brennilis NPP - a yard management as a function of the wastes. The document contains also seven appendices addressing the following subjects: 1. the share of decommissioning assigned to EDF and the decommissioning steps; 2. the EDF installations in course of decommissioning; 3. the CEA decommissioned installations or in course of decommissioning; 4. regulations; 5. costs; 6. waste management - principles; 7. data on the decommissioning yard

Verde pentru biciclete (Green for Bycicles

Directory of Open Access Journals (Sweden)

Romina Faur

2011-06-01

Full Text Available The campaign “Verde pentru biciclete” (Engl. “Green for bicycles” is the first official initiative from Timişoara that encourages adopting cycling as an ecological and economical alternative to urban transportation; this addresses the citizens of Timişoara and not only, regardless of age. “Verde pentru biciclete” is a pedalling movement supported by the Bega Foundation, in collaboration with the Gratzu Sportive Club, KissFM, Ziua de Vest, Agenda and agenda.ro. The debut of the campaign took place of October 25th 2008, with the first “Verde pentru biciclete” event – “The bicycles Counting”. All the events that followed were held to draw attention on the importance of cycling, together with obtaining of certain facilities, necessary for the cyclists’ safe movement in traffic. Moreover, a number of communication platforms have been created between the fans of cycling; thus, the website www.pedaleaza.ro has been created, through which those interested can inform themselves or communicate on the forum and discussions group verde_pentru_biciclete@yahoogroups.com o through the social network Facebook (facebook.com/ verdepentrubiciclete. This paper presents the activities held within the campaign since its beginning until today, as well as our future plans.

Decommissioning of NPP A-1

International Nuclear Information System (INIS)

Anon

2009-01-01

In this presentation the Operation history of A1 NPP, Project 'Decommissioning of A1 NPP' - I stage, Project 'Decommissioning of A1 NPP ' - II stage and Next stages of Project 'Decommissioning of A1 NPP ' are discussed.

Seismic influence in the Quaternary uplift of the Central Chile coastal margin, preliminary results.

Science.gov (United States)

Valdivia, D.; del Valle, F.; Marquardt, C.; Elgueta, S.

2017-12-01

In order to quantify the influence of NW striking potentially seismogenic normal faults over the longitudinal variation of the Central Chile Coastal margin uplift, we measured Quaternary marine terraces, which represent the tectonic uplift of the coastal margin. Movement in margin oblique normal faults occurs by co-seismic extension of major subduction earthquakes and has occurred in the Pichilemu fault, generating a 7.0 Mw earthquake after the 2010 8.8 Mw Maule earthquake.The coastal area between 32° and 34° S was selected due to the presence of a well-preserved sequence of 2 to 5 Quaternary marine terraces. In particular, the margin oblique normal NW-trending, SW-dipping Laguna Verde fault, south of Valparaiso (33° S) puts in contact contrasting morphologies: to the south, a flat coast with wide marine terraces is carved in both, Jurassic plutonic rocks and Neogene semi-consolidated marine sediments; to the north, a steeper scarp with narrower marine terraces, over 120 m above the corresponding ones in the southern coast, is carved in Jurassic plutonic rocks.We have collected over 6 months microseimic data, providing information on seismic activity and underground geometry of the Laguna Verde fault. We collected ca. 100 systematic measurements of fringes at the base of paleo coastal scarps through field mapping and a 5 m digital elevation model. These fringes mark the maximum sea level during the terrace's carving.The heights of these fringes range between 0 and 250 masl. We estimate a 0.7 mm/yr slip rate for the Laguna Verde fault based on the height difference between corresponding terraces north- and southward, with an average uplift rate of 0.3 mm/yr for the whole area.NW striking normal faults, besides representing a potential seismic threat to the near population on one of the most densely populated areas of Chile, heavily controls the spatial variation of the coastal margin uplift. In Laguna Verde, the uplift rate differs more than three times northward

Stability analysis of a recycling circuit of a BWR type reactor. Theoretical study

International Nuclear Information System (INIS)

Salinas H, J.G.; Espinosa P, G.; Gonzalez M, V.M.

2000-01-01

The Technology, Regulation and Services Management of the National Commission of Nuclear Safety and Safeguards financed and in coordinate form with the I.P.H. Department of the Metropolitan Autonomous-Iztapalapa University developed the present project with the purpose of studying the effect of the recycling system on the linear stability of a BWR reactor whose reference central is the Laguna Verde power station. The present project forms part of a work series focused to the linear stability of the nuclear reactor of the Unit 1 at Laguna Verde power station. The components of the recycling system considered for the study of stability are the recycling external circuit (recycling pumps, valves) and the internal circuit (downcomer, jet pumps, lower full, driers, separators). The mathematical model is obtained applying mass balances and movement quantity in each one of the mentioned circuits. With respect to the nucleus model two regions are considered, the first one is made of a flow in one phase and the second one of a flow in two phases. For modelling the biphasic region it is considered homogenous flow. Generally it is studied the system behavior in the frequency domain starting from the transfer function applied to four operational states which correspond to the lower stability zone in the map power-flow of the Unit 1 of Laguna Verde power station. The Nyquist diagrams corresponding to each state as well as their characteristic frequency were determined. The results show that exists a very clear dependence of the power-flow relation on the stability of the system. It was found that the boiling length is an important parameter for the linear stability of the system. The obtained results show that the characteristic frequencies in unstability zones are similar to the reported data of the Unit 1 of the Laguna Verde power station in the event of power oscillations carried out in January 1995. (Author)

Stability analysis of a recycling circuit of a BWR type reactor. Theoretical study; Analisis de estabilidad de un circuito de recirculacion de un reactor del tipo BWR. Estudio teorico

Energy Technology Data Exchange (ETDEWEB)

Salinas H, J.G.; Espinosa P, G. [Universidad Autonoma Metropolitana-Iztapalapa, 09000 Mexico D.F. (Mexico); Gonzalez M, V.M. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 04000 Mexico D.F. (Mexico)

2000-07-01

The Technology, Regulation and Services Management of the National Commission of Nuclear Safety and Safeguards financed and in coordinate form with the I.P.H. Department of the Metropolitan Autonomous-Iztapalapa University developed the present project with the purpose of studying the effect of the recycling system on the linear stability of a BWR reactor whose reference central is the Laguna Verde power station. The present project forms part of a work series focused to the linear stability of the nuclear reactor of the Unit 1 at Laguna Verde power station. The components of the recycling system considered for the study of stability are the recycling external circuit (recycling pumps, valves) and the internal circuit (downcomer, jet pumps, lower full, driers, separators). The mathematical model is obtained applying mass balances and movement quantity in each one of the mentioned circuits. With respect to the nucleus model two regions are considered, the first one is made of a flow in one phase and the second one of a flow in two phases. For modelling the biphasic region it is considered homogenous flow. Generally it is studied the system behavior in the frequency domain starting from the transfer function applied to four operational states which correspond to the lower stability zone in the map power-flow of the Unit 1 of Laguna Verde power station. The Nyquist diagrams corresponding to each state as well as their characteristic frequency were determined. The results show that exists a very clear dependence of the power-flow relation on the stability of the system. It was found that the boiling length is an important parameter for the linear stability of the system. The obtained results show that the characteristic frequencies in unstability zones are similar to the reported data of the Unit 1 of the Laguna Verde power station in the event of power oscillations carried out in January 1995. (Author)

Study of the oscillations event of the CNLV-U1 with Wavelets techniques

International Nuclear Information System (INIS)

Amador G, R.; Nunez C, A.; Prieto G, A.; Espinosa P, G.

2004-01-01

Presently work is described and the techniques are applied of the Fourier Transformation in Short Time, the Continuous Transformation of Wavelets and the Multi resolution Analysis for the analysis of the event of oscillations of power in the Nuclear Power station of Laguna Verde Unit 1 happened in January of 1995. In general, the wavelets techniques allows to carry out studies of the different signals generated by a nuclear plant in the plane Time-frequency, Time-scale as well as the decomposition of the signals. The results obtained study presently demonstrate that the frequency of the event of oscillations in the Nuclear Power station of Laguna Verde Unit 1 are approximately 0.52 Hz for the 3 analysis techniques, besides being observed the evolution of the frequency in function of the time. (Author)

Study of the oscillations event of the CNLV-U1 with Wavelets techniques; Estudio del evento de oscilaciones de la CNLV-U1 con tecnicas de wavelets

Energy Technology Data Exchange (ETDEWEB)

Amador G, R.; Nunez C, A. [CNSNS, Dr. Barragan 779, 03020 Mexico D.F. (Mexico)]. E-mail: ragarcia@cnsns.gob.mx; Prieto G, A.; Espinosa P, G. [UAM-I, 09340 Mexico D.F. (Mexico)

2004-07-01

Presently work is described and the techniques are applied of the Fourier Transformation in Short Time, the Continuous Transformation of Wavelets and the Multi resolution Analysis for the analysis of the event of oscillations of power in the Nuclear Power station of Laguna Verde Unit 1 happened in January of 1995. In general, the wavelets techniques allows to carry out studies of the different signals generated by a nuclear plant in the plane Time-frequency, Time-scale as well as the decomposition of the signals. The results obtained study presently demonstrate that the frequency of the event of oscillations in the Nuclear Power station of Laguna Verde Unit 1 are approximately 0.52 Hz for the 3 analysis techniques, besides being observed the evolution of the frequency in function of the time. (Author)

Mochovce NPP simulator

International Nuclear Information System (INIS)

Ziakova, M.

1998-01-01

Mochovce NPP simulator basic features and detailed description of its characteristics are presented with its performance, certification and application for training of NPP operators as well as the training scenario

Two managerial grids in NPP

International Nuclear Information System (INIS)

Zhao Hui

2012-01-01

Today, the nuclear power corporation (NPC) enjoys the profit of LCEP (the low carbon economic policy). at the same time, they also enduring more and more pressure. For example, the partner competition or the NPP potential occupational risk . The efficient counterplot of risk is the self-ability cultivation. It is essential to research the NPP managerial flow. The nuclear power plant (NPP) unit is a carrier of the NPC enterprise management system, and has taken on a new look 'pull one portion then the whole moving'. The NPP has three systematical characters, the security responsibility center, the man-machine system and the input-output system. The manufacturing system and the enterprise management system are the great constituents of the NPP managerial flows. Means of systems analysis, we can find out the truth of the NPP running interface. In CHINA, there are many operating experiences near 20 years. It indicates that the NPP manufacturing system and the enterprise system are the roots of the nuclear power corporation, the core of the all NPP systems must be based on it. So the ability cultivation is the work core to NPP. It is reliably to ensure the NPP to be up against problems, for instance, the security duty, the costing control and the man-machine system running harmoniously. This paper introduces the NPP managerial flow and the present state of QNPC, also come up with a proposal to refer for the NPC development actions of collective measure, specialization, standardization, fine. (author)

Approach to criticality in cold core of the Unit 1 of the cycle 10 of the Laguna Verde power plant with control rods similar in design to the original ones and the advanced ones

International Nuclear Information System (INIS)

Perusquia, R.; Ramirez, J.R.; Ortiz, J.J.; Hernandez, J.L.; Montes, J.L.

2004-01-01

In the Laguna Verde power plant (CLV) worn out control bars have been replacing for control rods of advanced design. At the moment of the 109 rods of similar design to the original of the Unit 1 of the CLV, 14 of them have been substituted with two types of different advanced control rods. The same as the original rods the advanced rods use boron carbide as control element for neutrons, but additionally they use hafnium, to achieve a longer useful half life. The rods of similar design to the original are homogeneous axially on the other hand the advanced presenting several zones. In principle the advanced rods were designed to be neutronically compatible to the original rods. However the differences in the design and of constituents assumed to consider a different performance during the operation. Since the one numbers of advanced bars is growing with the number of cycles of the CLV reactor has requested to the National Institute of Nuclear Research (ININ) to evaluate in detailed form the performance of the control rods. Previously the calculations and analysis of cycle design that that were carried out assumed that control rods should be of similar design as the original. Using the HELIOS/CM-LENDS system, the effect of the inclusion of advanced rods was analyzed in the approximation of the criticality in cold (20 C) in the cycle 10 of the Unit 1. Four scenarios were poposed, where the type of the rod of substitution control is varied. The value of reactivity was calculated for the rods similar in design to the original and for the advanced one. By comparison of these values, it was found that the value of reactivity of the control rods of the advanced design was superior to the value for rods similar to the original ones by 7.6% for one of the advanced designs and of 13.6% for the other one. (Author)

Laguna Verde annulus pressurization loads evaluation

International Nuclear Information System (INIS)

Castaneda, M. A.; Cruz, M. A.; Cardenas, J. B.; Vargas, A.; Cruz, H. J.; Mercado, J. J.

2010-10-01

Annulus pressurization, jet impingement, pipe whip restraint and jet thrust are phenomena related to postulated pipe ruptures. A postulated pipe rupture at the weld between recirculation, or feedwater piping and a reactor nozzle safe end, will lead to a high flow rate of flashing water/steam mixture into the annulus between the reactor pressure vessel and the biological shield wall. The total effect of the vessel and pipe inventory blowdown from the break being postulated must be accounted for in the evaluation. A recirculation line break will give rise to an angular dependent short term pressure differential around the vessel, followed by a longer term pressure buildup in the annulus. A recirculation line postulated rupture may not produce worst case conditions and reference to time intervals for only the recirculation break should be treated superficially. A postulated rupture of the feedwater piping may produce the extreme case for determining: 1) the shield wall and reactor vessel to pedestal interactions, 2) loading on the reactor vessel internals, or 3) responses for the balance of piping attached to the vessel. Recently it was identified a potential issue regarding the criteria used to determine which cases were evaluated for Annulus Pressurization (A P) loads for new loads plants. The original A P loads methodology in the late 1970 and early 1980 years separated the mass/energy release calculation from the structural response calculation based on the implicit assumption that the maximum overall mass/energy release will result in maximizing the structural response and corresponding stresses on the reactor pressure vessel, internals, and containment structures. This process did not consider the dynamic response in the primary and secondary safety related structures, components and equipment. Consequently, the A P loads used as input for design adequacy evaluations of Nuclear Steam Supply System safety related components for new loads plants might have resulted in non-conservative evaluations. (Author)

Aves acuáticas de la laguna de Acuitlapilco, Tlaxcala, México

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Juanita Fonseca

2012-07-01

Full Text Available Estudiamos la abundancia y distribución estacional de las aves acuáticas en la laguna de Acuitlapilco, Tlaxcala, México. De febrero de 2011 a enero de 2012, realizamos censos en puntos de conteo para el registro de las especies. Registramos un total de 36 especies de aves acuáticas con una abundancia total acumulada de 48,794 individuos. Doce de las especies registradas fueron residentes, 10 migratorias y 14 fueron especies transitorias o de registro accidental. Observamos que la mayor riqueza de especies y abundancia de aves fueron en invierno, cuando la mayoría de las especies migratorias llegaron a la laguna. Nuestros resultados muestran que esta área es importante para especies de aves acuáticas tanto residentes como migratorias, y refleja la necesidad de un mayor número de estudios sobre el papel de las lagunas continentales como reservorios de biodiversidad.

Changing NPP consumption patterns in the Holocene: from Megafauna "liberated" NPP to "ecological bankruptcy"

Science.gov (United States)

Doughty, C.

2015-12-01

There have been vast changes in how net primary production (NPP) is consumed by humans and animals during the Holocene beginning with a potential increase in availability following the Pleistocene megafauna extinctions. This was followed by the development of agriculture which began to gradually restrict availability of NPP for wild animals. Finally, humans entered the industrial era using non-plant based energies to power societies. Here I ask the following questions about these three energy transitions: 1. How much NPP energy may have become available following the megafauna extinctions? 2. When did humans, through agriculture and domestic animals, consume more NPP than wild mammals in each country? 3. When did humans and wild mammals use more energy than was available in total NPP in each country? To answer this last question I calculate NPP consumed by wild animals, crops, livestock, and energy use (all converted to units of MJ) and compare this with the total potential NPP (also in MJ) for each country. We develop the term "ecological bankruptcy" to refer to the level of consumption where not all energy needs can be met by the country's NPP. Currently, 82 countries and a net population of 5.4 billion are in the state of ecologically bankruptcy, crossing this threshold at various times over the past 40 years. By contrast, only 52 countries with a net population of 1.2 billion remain ecologically solvent. Overall, the Holocene has seen remarkable changes in consumption patterns of NPP, passing through three distinct phases. Humans began in a world where there was 1.6-4.1% unclaimed NPP to consume. From 1700-1850, humans began to consume more than wild animals (globally averaged). At present, >82% of people live in countries where not even all available plant matter could satisfy our energy demands.

Transactions of the Second Annual Congress of the Sociedad Nuclear Mexicana A.C.; Memorias del Segundo Congreso Anual de la Sociedad Nuclear Mexicana A.C.

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-11-01

With no doubt, 1991 has been a good year for Nuclear Energy in Mexico. The record imposed by Laguna Verde Nuclear Power Plant, the first in his type in the world, operating without interruption in its first operating cycle, represents a splendid incentive for we all the nuclear workers. This fact is reflected in the percentage of papers presented in this congress, dealing with several aspects of Laguna Verde Central. This achievement should serve as an impulse for the development of other areas of application of nuclear energy in the country and at the same time be a reflection of the participation of the members of our society with good quality papers. In this Second Congress of Sociedad Nuclear Mexicana A.C., around thirty papers were presented in the technical sessions, in areas as: fuel management, radiation protection, reactor physics, transients analysis, nuclear materials and others. A special section is dedicated to present the experiences of the first fuel reload of Unit 1 in Laguna Verde Nuclear Power Plant,as well as different plenary meetings dedicated to subjects of general interest as advanced reactors, waste disposal and others. It is the wish of all the members of Sociedad Nuclear Mexicana A.C., that this annual meetings will be enriched with the enthusiastic participation of the scholars of nuclear field and that they represent the forum that we all need for the exchange of knowledge and experiences. (Author).

Camp Verde Adult Reading Program. Final Performance Report.

Science.gov (United States)

Maynard, David A.

This document begins with a four-page performance report describing how the Camp Verde Adult Reading Program site was relocated to the Community Center Complex, and the Town Council contracted directly with the Friends of the Camp Verde Library to provide for the requirements of the program. The U.S. Department of Education grant allowed the…

Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM

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C. M. Allison

2012-01-01

Full Text Available Immediately after the accident at Fukushima Daiichi, Innovative Systems Software and other members of the international SCDAP Development and Training Program started an assessment of the possible core/vessel damage states of the Fukushima Daiichi Units 1–3. The assessment included a brief review of relevant severe accident experiments and a series of detailed calculations using RELAP/SCDAPSIM. The calculations used a detailed RELAP/SCDAPSIM model of the Laguna Verde BWR vessel and related reactor cooling systems. The Laguna Verde models were provided by the Comision Nacional de Seguridad Nuclear y Salvaguardias, the Mexican nuclear regulatory authority. The initial assessment was originally presented to the International Atomic Energy Agency on March 21 to support their emergency response team and later to our Japanese members to support their Fukushima Daiichi specific analysis and model development.

NPOESS Preparatory Project (NPP) Science Overview

Science.gov (United States)

Butler, James J.

2011-01-01

NPP Instruments are: (1) well understood thanks to instrument comprehensive test, characterization and calibration programs. (2) Government team ready for October 25 launch followed by instrument activation and Intensive Calibration/Validation (ICV). NPP Data Products preliminary work includes: (1) JPSS Center for Satellite Applications and Research (STAR) team ready to support NPP ICV and operational data products. (2) NASA NPP science team ready to support NPP ICV and EOS data continuity.

Cape Verde

Science.gov (United States)

2007-01-01

This Mars Exploration Rover Opportunity Pancam 'super resolution' mosaic of the approximately 6 m (20 foot) high cliff face of the Cape Verde promontory was taken by the rover from inside Victoria Crater, during the rover's descent into Duck Bay. Super-resolution is an imaging technique which utilizes information from multiple pictures of the same target in order to generate an image with a higher resolution than any of the individual images. Cape Verde is a geologically rich outcrop and is teaching scientists about how rocks at Victoria crater were modified since they were deposited long ago. This image complements super resolution mosaics obtained at Cape St. Mary and Cape St. Vincent and is consistent with the hypothesis that Victoria crater is located in the middle of what used to be an ancient sand dune field. Many rover team scientists are hoping to be able to eventually drive the rover closer to these layered rocks in the hopes of measuring their chemistry and mineralogy. This is a Mars Exploration Rover Opportunity Panoramic Camera image mosaic acquired on sols 1342 and 1356 (November 2 and 17, 2007), and was constructed from a mathematical combination of 64 different blue filter (480 nm) images.

Frequency modulator. Transmission of meteorological signals in LVC; Modulador de frecuencia. Transmision de senales meteorologicas en CLV

Energy Technology Data Exchange (ETDEWEB)

Rivero G, P.T.; Ramirez S, R.; Gonzalez M, J.L.; Rojas N, P.; Celis del Angel, L. [ININ, 52750 La marquesa, Estado de Mexico (Mexico)

2007-07-01

The development of the frequency modulator and demodulator circuit for transmission of meteorological signals by means of fiber optics of the meteorology station to the nuclear reactor unit 1 in the Laguna Verde Central in Veracruz is described. (Author)

Frequency modulator. Transmission of meteorological signals in LVC

International Nuclear Information System (INIS)

Rivero G, P.T.; Ramirez S, R.; Gonzalez M, J.L.; Rojas N, P.; Celis del Angel, L.

2007-01-01

The development of the frequency modulator and demodulator circuit for transmission of meteorological signals by means of fiber optics of the meteorology station to the nuclear reactor unit 1 in the Laguna Verde Central in Veracruz is described. (Author)

NPP life management (abstracts)

International Nuclear Information System (INIS)

Litvinskij, L.L.; Barbashev, S.V.

2002-01-01

Abstracts of the papers presented at the International conference of the Ukrainian Nuclear Society 'NPP Life Management'. The following problems are considered: modernization of the NPP; NPP life management; waste and spent nuclear fuel management; decommissioning issues; control systems (including radiation and ecological control systems); information and control systems; legal and regulatory framework. State nuclear regulatory control; PR in nuclear power; training of personnel; economics of nuclear power engineering

Prefabricated solution to modular construction in Cape Verde

Science.gov (United States)

Vieira, Nuno; Amado, Miguel; Pinho, Fernando

2017-02-01

Nowadays, the lack of adequate housing in Cape Verde is a growing problem. The migration of the population living in the countryside to the major cities generates an increase of the diameter of the cities. With the lack of economic power, the migrating families tend to occupy the land with houses which don't present proper conditions to living. Praia is the capital of Cape Verde and so on the biggest city of the country. This fact leads Praia to being the city with major economic power and job offer in all country. Consequently, Praia has developed the biggest slum of the Cape Verde and it is urgent to approach this problem in order to create solutions that reveal capacity to start solving it. Cape Verde's unique dry subtropical climate turns indispensable a careful resolution of the housing, in order to ensure the comfort of the occupants. The modular construction is a solution with potential to approach this problem with a fast and economic response. In order to answer the situation, this article introduces a modular solution in order to reach the needing of thermal comfort to the specific case of Praia.

DISTRIBUSI HUTAN BAKAU DI LAGUNA PANTAI SELATAN YOGYAKARTA (Mangrove Distribution at the Lagoons in the Southern Coast of Yogyakarta

Directory of Open Access Journals (Sweden)

Tjut Sugandawaty Djohan

2007-03-01

Full Text Available ABSTRAK  Kehadiran sisa hutan bakau di laguna Bogowonto, pantai selatan Yogyakarta menunjukkan bahwa pada masa lalu laguna tersebut didominasi oleh hutan bakau, sehingga penelitian ini bertujuan mempelajari kehadiran vegetasi bakau di laguna-laguna dan muara sungai di pantai selatan tersebut. Ada empat laguna di pantai Selatan Yogyakarta, laguna Bogowonto, Serang, Progo, Opak, dan satu muara sungai, Kali Baron. Laguna tersebut merupakan laguna internitten, artinya pada musim kemarau, mulut sungainya tertutup gumuk pasir dan laguna didominasi oleh perairan tawar dan merupakan ekosistem tergenang. Sebaliknya di musim hujan mulut sungai terbuka, laguna bersifat sebagai ekosistem pasang surut. Data vegetasi dicuplik dengan menggunakan kuadrat plot berukuran 10m x 20m dengan ulangan dua kali. Kuadrat plot ditempatkan pada pusat distribusi mangrovenya, yang dipilih mulai dari rawa burit ke arah muara sungai. Tekstur tanah, hara tanah, salinitas air dan hara air juga dikaji. Kehadiran hutan bakau di laguna dibatasi oleh tekstur tanah. Tekstur pasir, 60-99 %, mendominasi laguna Serang, Progo, Opak dan muara kali Baron. Komunitas bakau hanya ditemukan di laguna Bogowonto, yang tersusun atas 5 jenis bakau, Sonneratia alba, Nypa fruticans, Acanthus ilicifolius, Acrosticum sp., dan Derris heterophylla, dan dua jenis spesies peralihan, Pandanus sp. dan Cynodon dactylon. Pola distribusi komunitasnya mengelompok (clump, mempunyai tipe riverine mangrove,dan tidak membentuk zonasi. Sonneratia hadir mulai dari muara sungai sampai di rawa burit. Ketika air surut salinitas berkisar antara 0-6,5 %. Nypa hanya ditemukan satu kelompok di kaki gumuk. Distribusi Sonneratia tidak ditentukan oleh tinggi genangan, akan tetapi tinggi pneumatophor mengikuti pola tinggi genangan air. Di laguna Bogowonto, spesies bakau tidak mempunyai zonasi dan beradaptasi pada sistem ekologinya.   ABSTRACT  The presence of mangrove remnant at the lagoon of Bogowonto River in the southern

Aves ocasionales en la Sabana de Bogotá y las Lagunas de Fúquene y de Tota

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Borrero José Ignacio

1947-12-01

Full Text Available En números anteriores de esta misma revista publiqué algunas listas preliminares anotando la presencia ocasional de ciertas aves en la Sabana de Bogotá y la Laguna de Fúquene. A continuación hago mención de otras especies que he encontrado en las mismas localidades o también en la Laguna de Tota, Boyacá, a 3015 metros de altitud. Por considerarlo de importancia desde el punto de vista de la distribución geográfica, doy también datos referentes a la presencia de un ave migratoria norteamericana (Colymbus niqricollis californicus en la Laguna de Tota.

Determination of the exposition rapidity in the level 49.90 of the reactor building for the decrease in the water level of the spent fuel pool; Determinacion de la rapidez de exposion en el nivel 49.90 del edificio del reactor por la disminucion en el nivel de agua de la alberca de combustible gastado

Energy Technology Data Exchange (ETDEWEB)

Mijangos D, Z. E.; Herrera H, S. F.; Cruz G, M. A.; Amador C, C., E-mail: zoedelfin@gmail.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Km 44.5 Carretera Cardel-Nautla, 91476 Laguna Verde, Alto Lucero, Veracruz (Mexico)

2014-10-15

The fuel assemblies storage in the nuclear power plant of Laguna Verde (NPP-L V) represents a crucial aspect, due to the generated dose by the decay heat of the present radio-nuclides in the assemblies retired of the reactor core, after their useful life. These spent assemblies are located inside the spent fuel pool (SFP), in the level 49.90 m in the Reload Floor of the Reactor building of NPP-L V. This leads to the protection at personnel applying the ALARA (As Low As Reasonably Achievable) criteria, fulfilling the established dose criteria by the Regulator Body the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). Considering the loss scenario of the cooling system of the SFP, in which the SFP water vaporizes, is important to know the water level in which the limit of effective dose equivalent is fulfilled for the personnel. Also, is important for the instrumentation of the SFP, for the useful life of the same instruments. In this work is obtained the exposition rapidity corresponding to different water levels of SFP in the Reload Floor of NPP-L V, to identify the minimum level of water where the limit of effective dose equivalent is fulfilled of 25 rem s to the personnel, established in the Article 48 of the General Regulation of Radiological Safety of CNSNS and the Chapter 50 Section 67 of the 10-Cfr of Nuclear Regulatory Commission in USA. The water level is also identified where the exposition rapidity is of 15 m R/hr, being the value of the set point of the area radiation monitor D21-Re-N003-1, located to 125 cm over the level 49.90 meters of the Reload Floor of NPP-L V. (Author)

Determination of the exposition rapidity in the level 49.90 of the reactor building for the decrease in the water level of the spent fuel pool

International Nuclear Information System (INIS)

Mijangos D, Z. E.; Herrera H, S. F.; Cruz G, M. A.; Amador C, C.

2014-10-01

The fuel assemblies storage in the nuclear power plant of Laguna Verde (NPP-L V) represents a crucial aspect, due to the generated dose by the decay heat of the present radio-nuclides in the assemblies retired of the reactor core, after their useful life. These spent assemblies are located inside the spent fuel pool (SFP), in the level 49.90 m in the Reload Floor of the Reactor building of NPP-L V. This leads to the protection at personnel applying the ALARA (As Low As Reasonably Achievable) criteria, fulfilling the established dose criteria by the Regulator Body the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS). Considering the loss scenario of the cooling system of the SFP, in which the SFP water vaporizes, is important to know the water level in which the limit of effective dose equivalent is fulfilled for the personnel. Also, is important for the instrumentation of the SFP, for the useful life of the same instruments. In this work is obtained the exposition rapidity corresponding to different water levels of SFP in the Reload Floor of NPP-L V, to identify the minimum level of water where the limit of effective dose equivalent is fulfilled of 25 rem s to the personnel, established in the Article 48 of the General Regulation of Radiological Safety of CNSNS and the Chapter 50 Section 67 of the 10-Cfr of Nuclear Regulatory Commission in USA. The water level is also identified where the exposition rapidity is of 15 m R/hr, being the value of the set point of the area radiation monitor D21-Re-N003-1, located to 125 cm over the level 49.90 meters of the Reload Floor of NPP-L V. (Author)

TRATAMIENTO DE EFLUENTES PISCÍCOLAS (TILAPIA ROJA EN LAGUNAS CON Azolla pinnata

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GUILLERMO CHAUX F

2013-12-01

Full Text Available Los sistemas con plantas acuáticas flotantes son una alternativa económicamente sostenible para el tratamiento de efluentes piscícolas. Se evaluó a escala piloto el desempeñ,o de un sistema de lagunas con Azolla pinnata en serie para el tratamiento de efluentes de cría de tilapia roja durante el proceso de levante y engorde. El sistema construido en la piscícola La Yunga (Popayán, Colombia consistió en dos líneas de cinco lagunas en serie; la primera con A. pinnata y la segunda sin la planta acuática; cada laguna se operó con un tiempo de detención de un día. La evaluación se realizó en época seca. La producción de Azolla fresca osciló entre 42 y 87 g/m2.d y el contenido de proteína entre 18,5% y 20,4%. Las eficiencias de remoción obtenidas en las líneas (con Azolla, sin Azolla fueron respectivamente: 56% y 46% DBO5; 49% y 26% DQO; 56% y 33% SST; 28% y 36% N-NTK; -108% y 23% N-NH4+; 64% y 34% fósforo total, mostrando superioridad del sistema con Azolla. Con solo tres lagunas en serie plantadas con A. pinnata se alcanzan las eficiencias máximas obtenidas en la remoción de DBO5, DQO, SST y fósforo total.

Intraplate seismicity across the Cape Verde swell

Science.gov (United States)

Vales, Dina; Matias, Luís.; Haberland, Christian; Silveira, Graça.; Weber, Michael; Carrilho, Fernando; Dias, Nuno

2010-05-01

The Cape Verde Archipelago ((15-17°N, 23-26°W) is located within the African plate, about 500km west of Senegal, in the African coast. The islands are located astride the Cape Verde mid-plate topographic swell, one of the largest features of its type in the world's ocean basins. The origin of this Cape Verde swell is still in debate. Previous determinations of the elastic thickness (Te) reveal a normal Te and a modest heat flow anomaly which suggest that the swell cannot be fully explained by uplift due to thermal reheating of the lithosphere by an underlying ‘‘hot spot'' and that other, deep-seated, mantle processes must be involved. The CV-PLUME (An investigation on the geometry and deep signature of the Cape Verde mantle plume) project intends to shape the geometry and deep origin of the Cape Verde mantle plume, via a combined study of seismic, magnetic, gravimetric and geochemical observations. Through this study we intend to characterize the structure beneath the archipelago from the surface down to the deep mantle. The core of this 3-year project was a temporary deployment of 39 Very Broad Band seismometers, across all the inhabited islands, to recorder local and teleseismic earthquakes. These instruments were operational from November 2007 to September 2008. In this work we report on the preliminary results obtained from the CV-PLUME network on the characterization of the local and regional seismicity. To detect the small magnitude seismic events the continuous data stream was screened using spectrograms. This proved to be a very robust technique in the face of the high short-period noise recorded by many of the stations, particularly during day time. The 10 month observation time showed that the background seismic activity in the Archipelago and surrounding area is low, with only a very few events recorded by the complete network. However, two clusters of earthquakes were detected close to the Brava Island, one to the NW and a second one, more active

Indice fisicoquímico de la calidad de agua para el manejo de lagunas tropicales de inundación

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Ana Gabriela Pérez-Castillo

2008-12-01

Full Text Available Se creó un índice fisicoquímico de calidad del agua (ICA-L, para lagunas que se desbordan, el cual fue validado en el sector de riego de Tamarindo, y en una sección del sistema de lagunas del Parque Nacional Palo verde (Guanacaste, Costa Rica. El índice incluye las variables: porcentaje de saturación de oxígeno disuelto, pH, concentración de nitratos, concentración de fósforo total, demanda química de oxígeno, concentración de sólidos suspendidos, conductividad eléctrica y temperatura. El índice se fija automáticamente en cero si la concentración de alguna sustancia tóxica excede el máximo permitido. Los factores de ponderación se ajustaron con base en los pesos definidos en el Índice de Calidad de Agua de la National Sanitation Foundation (ICA-NSF, se excluyó el peso del conteo de coliformes fecales, se integró la ponderación de turbiedad y de sólidos totales una sola, de sólidos suspendidos, y se asignó a la conductividad un factor de 0.08. El índice per-mite evaluar la capacidad del agua de las lagunas tropicales de inundación de agua dulce, para lograr el sostenimiento de la biodiversidad y el desarrollo de la vida acuática, cuando surgen peligros por prácticas agropecuarias.Physicochemical water quality index, a management tool for tropical-flooding lagoons. We propose ICA-L, a wetland physicochemical water quality index (WWQI, to be used as a management tool for seasonal-flooding lagoons in Palo verde National Park, Guanacaste, Costa Rica. The goal is to preserve their natural role for native plants as well as migrants and local animal species. The index was developed in four steps: parameter selection, assignment of parameter weight, transformation of data to their corresponding sub indices and selection of an appropriate aggregation function. In this process, the following criteria were used as a reference: WQI from the National Sanitation Foundation, WQI for the Des Moines River, Escribano and De Frutos

QUÍMICA VERDE: UN NUEVO RETO

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Nerlis Paola Pájaro Castro

2011-01-01

Full Text Available En la actualidad, existe un enorme deterioro del medio ambiente que ha generado la necesidad de buscar alternativas que conduzcan a la sostenibilidad ambiental. Una de estas herramientas es la ¿química verde¿, concepto que contempla el diseño de productos y procesos que reduzcan la generación de sustancias peligrosas y maximicen la eficiencia en la utilización de recursos materiales y energéticos. El empleo de tecnologías menos contaminantes, permitirá a las empresas químicas mitigar los efectos ambientales asociados a su actividad, reduciendo el consumo de materiales e incrementando la participación de recursos renovables. Para alcanzar estas metas, se han propuesto 12 principios básicos de química verde, aplicables en diferentes campos, tales como la medicina, la agricultura, la industria química y farmacéutica. Esta revisión detalla los principios y usos principales de la química verde, y su aplicación como una filosofía de trabajo para avanzar hacia un verdadero desarrollo sostenible.

Inspection activities of the Mexican regulatory body during the construction stage of the first unit of Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Salgado Gonzalez, Julio Ricardo

1996-01-01

The paper addresses the regulatory framework established for the design, construction and operation of the NPP. The regulatory bases of the inspection program are mentioned.A summary of the inspection and reviewing activities carried out by the former Nuclear Safety Management Construction area during the construction stage, taking the year 1977 as the beginning of regular inspection activities for this construction stage, and up to the year 1987, when this one is considered as practically completed, and a stage of pre-operational tests has been started. Finally, the main inspection areas are described, and a summary is given of the classification of deficiencies detected during the inspections

To report the obtained results in the operation multicycle study of the L V U-1 using design data with the FCSII (1D) and PRESTO (3D) codes of the FMS system

International Nuclear Information System (INIS)

Montes T, J.L.; Cortes C, C.C.

1991-07-01

This work is to carry out a multicycle study for the Laguna Verde U-1 reactor with the FCS-II (1 - 20 cycles) and PRESTO (1 - 6 cycles) codes and to compare the obtained results against those reported by General Electric. (Author)

Application of the Scandpower methodology for the pattern design of the control bars at full power in the cycle 1 of the CNLV; Aplicacion de la metodologia de Scandpower para el diseno de patrones de barras de control a plena potencia en el ciclo uno de la CNLV

Energy Technology Data Exchange (ETDEWEB)

Montes T, J L; Perusquia C, R [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1992-05-15

The objective of this report is by means of the methodology provided by Scandpower to design a group of patterns of control bars to full power for the operation of the first operation cycle of the Laguna Verde Unit 1 reactor. (Author)

Safety culture in Mexico

International Nuclear Information System (INIS)

Salgado Gonzalez, C.H.

2002-01-01

In this paper, there are describe the activities already accomplished and the activities planned to be executed by the licensee and the regulator with the aim to develop, maintain and strength Safety Culture in all the Laguna Verde Nuclear Power Plant activities. (author)

Application of the Scandpower methodology for the pattern design of the control bars at full power in the cycle 1 of the CNLV

International Nuclear Information System (INIS)

Montes T, J.L.; Perusquia C, R.

1992-05-01

The objective of this report is by means of the methodology provided by Scandpower to design a group of patterns of control bars to full power for the operation of the first operation cycle of the Laguna Verde Unit 1 reactor. (Author)

To report the obtained results in the operation multicycle study of the L V U-1 using design data with the FCSII (1D) and PRESTO (3D) codes of the FMS system; Reportar los resultados obtenidos en el estudio de multiciclos de operacion de LV U-1 utilizando datos de diseno con los codigos FCSII (1D) y PRESTO (3D) del sistema FMS

Energy Technology Data Exchange (ETDEWEB)

Montes T, J L; Cortes C, C C

1991-07-15

This work is to carry out a multicycle study for the Laguna Verde U-1 reactor with the FCS-II (1 - 20 cycles) and PRESTO (1 - 6 cycles) codes and to compare the obtained results against those reported by General Electric. (Author)

The V-1 NPP and V-2 NPP upgrading

International Nuclear Information System (INIS)

1998-01-01

A brief account of activities in the V-1 NPP and V-2 NPP upgrading as well as maintenance carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. The V-1 NPP applied the so called 'Small Backfitting Programme'covering 81 points of the Czechoslovak Atomic energy Commission Decree No 5/91. Continual upgrading continued after the Backfitting Programme completion with the Safety Report and following Nuclear Regulatory Authority of Slovak Republic (NRA SR) Decrees No 1/94 and 110/94 setting spheres and procedure for adopting and implementation of measures enabling the units to operate further on. Results of expert missions, analyses and assessments of components identified by Basic Engineering became the basis for the development of the Gradual Reconstruction Programme. The Programme outputs underwent economic and probabilistic assessing their contribution to nuclear safety. This process resulted in finalizing the Gradual Reconstruction Programme which started to be implemented in 1996 and will be completed in 1999. It is implemented by the REKON consortium and covers 17 areas including Instrumentation and Control, self-consumption emergency supply, leakage monitoring, emergency core cooling system, seismic reinforcement and radioactivity localisation. Both units will reach internationally acceptable safety standards for the remaining life-time period. The V-2 NPP Upgrading and Safety Enhancement Programme includes results of activities performed in the course of last years to define all important activities leading to enhancement of nuclear safety and performance reliability and effectiveness within the plant life-time period and to establish conditions for extending the life-time of these units for 40 years. The V-2 NPP Upgrading and Safety Enhancement Programme aims to assure safe operation with a probability of the core damages less than 10 -4 /reactor · year

Talento verde: caracterización y búsqueda

Directory of Open Access Journals (Sweden)

María del Carmen Torres-Salazar

2015-01-01

Full Text Available Introducción: Los impactos del calentamiento global y el cambio climático son una preocupación en prácticamente todos los sectores de la sociedad, debido a las consecuencias que ya se perciben y que afectarán cada día más tanto a los sistemas naturales como a los creados por el hombre, generalmente de forma negativa. Para revertir estos efectos negativos y no continuar deteriorando el medio ambiente, es necesario un tipo especial de personas que sean capaces de tomar las decisiones adecuadas en los ámbitos en los que se desenvuelven. En esta investigación, estos seres humanos se denominan: “personas con talento verde”. El término talento verde no ha sido caracterizado y su uso es aun restringido. Esta investigación hace una caracterización del talento verde y propone una encuesta para detectar a las personas que cuentan con estas características. En este artículo, se reporta solo la validación de la encuesta. Es importante hacer notar que este trabajo forma parte de una investigación más amplia que busca conocer la relación entre directivos con talento verde y prácticas de cadena de suministro sustentable. Método: La caracterización del talento verde se realizó a través de la metodología de representaciones sociales, de la cual surgieron una serie de preguntas que buscan las características de talento verde en directivos de empresas y que forman parte de una encuesta de mayor cobertura que fue piloteada para su validación. La confiabilidad se midió a través del Alfa de Crombach y la validez por un Análisis Factorial. Resultados: Se encontraron nueve aspectos que caracterizan a las personas con talento verde, con las cuales se construyeron también nueve preguntas. Estas preguntas se hicieron a 25 directivos de empresas que participan en la Cámara de la Industria de la Transformación (CANACINTRA con el objetivo de validar el instrumento. El alfa de Crombrach obtenido fue del 0.948 y el análisis factorial indica

NPP Decommissioning: the concept; state of activities

International Nuclear Information System (INIS)

Nemytov, S.; Zimin, V.

2001-01-01

The main principles of NPP decommissioning concept in Russia are given. The conditions with fulfillment of works on NPP unit pre-decommissioning and decommissioning including: development of the normative documentation, creation of special fund for financing NPP decommissioning activities, deriving the Gosatomnadzor license for decommissioning of shut down NPP units, development of the equipment and technologies for waste and spent fuel management are presented. The decommissioning cost and labour intensity of one WWER-440 unit are shown. The practical works, executed on shut down units at Beloyarsk NPP (Unit1 and 2) and Novo Voronezh NPP (Unit 1 and 2) are outlined

ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

International Nuclear Information System (INIS)

Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

2009-01-01

Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

International Nuclear Information System (INIS)

Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

2008-01-01

Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

Contaminación producida por piscicultura intensiva en lagunas andinas de Junín, Perú

Directory of Open Access Journals (Sweden)

Mauro Mariano

2011-05-01

Full Text Available Se reportan los cambios producidos por el cultivo intensivo de la trucha Oncorhynchus mykiss en siete lagunas andinas. Las observaciones se realizaron en el año 1996, y entre el 2002 - 2007 y permitieron observar el proceso de deterioro de las lagunas, caracterizado por el incremento en las concentraciones de fosforo total y la disminución del oxigeno disuelto y la transparencia. La comunidad béntica fue evaluada en las siete lagunas en el 2007, resultando el número de especies y los índices de diversidad bajos (H'<1,26; <8 spp.. La abundancia varió entre 7 y 35 ind./0,04m2. La materia orgánica y carbonatos en fondo fueron altos (30,22 - 42,45%.

Botanical ecology and conservation of the laguna de la herrera (sabana de bogotá, colombia)

OpenAIRE

Wijninga, V. M.; Rangel, Orlando; Cleef, A. M.

2012-01-01

Se estudió la vegetación alrededor de la Laguna de La Herrera, una laguna andina a 2550 m. Se diferenciaron una comunidad de Phytolacca bogotensis (1): comunidades helofíticas dominadas por: Scirpus californicus y Typha angustifolia (2); Scirpus californicus (3); Polygonum punctatum (4); Rumex obtusifolius y Polygonum punctatum (5); Bidens laevis (6); Hydrocotyle ranunculoides (7); comunidades pleustofíticas con: Limnobium laevigatum; (8); Azolla filiculoides y Lemna cf. gibba (9) y Eichhorni...

NPP service life management

International Nuclear Information System (INIS)

Elagin, Yu.P.

2001-01-01

Problems of NPP service life management and service life prolongation are reviewed. Methods for the prolongation of the French NPP service life are discussed, priority directions of nuclear block service life management in regard to aging in the context of the European program of investigation into the materials aging are identified. Questions of the provision of the 60 years service life of the Mihama 1 block (Japan) and decision of the problem of the control equipment aging in Great Britain are discussed. Situation with the prolongation of licenses on the NPP operation in the USA and Spain is considered [ru

Desarrollo, trabajo y género: El caso de la Laguna de Yahuarcocha

Directory of Open Access Journals (Sweden)

Diosey Ramon Lugo-Morin

2015-06-01

Full Text Available El presente estudio propone valorar el papel de la mujer rural de los territorios aledaños a la Laguna de Yahuarcocha.  Escenario propicio para generar una dinámica económica en las comunidades de San Miguel de Yahuarcocha y Priorato donde las mujeres tienen un rol de importancia estratégica.  Se concluye que la participación de  las mujeres en la dinámica económica entorno a la Laguna de Yahuarcocha es determinante para el desarrollo del territorio sobre todo en el ámbito turístico.

Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico. Part 2; Conformacion de un proceso de evaluacion para una solicitud de renovacion de licencia de una central nuclear en Mexico. Parte 2

Energy Technology Data Exchange (ETDEWEB)

Serrano R, M. de L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2013-10-15

At the present time the operation licenses in force for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) will expire in the year 2020 and 2025 for the Unit-1 and Unit-2, respectively, for which the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has begun its preparation to assist a solicitude of the licensee to continue the operation of the NPP-L V. The present work has the purpose of defining the steps to continue and to generate the documents that would help in this process, as the normative, guides, procedures, regulations, controls, etc. so that the evaluation process will be effective and efficient, as much for the regulator organ as for the licensee. The advance carried out in the continuation of the conformation of an evaluation process of license renovation solicitude is also exposed, taking like base the requirements established by the CNSNS, the regulator organ of the United States (US NRC), and the IAEA for license renovation solicitude of this type. A summary of the licenses granted from the beginning of commercial operation of the NPP-L V is included, both units and the amendments to these licenses, explaining the reason of the amendment shortly and in the dates they were granted. A brief exposition of the nuclear power plants to world level that have received extension of its operation is included. The normative that can be applied in a life extension evaluation is presented, the evaluation process to continue with the guides of the US NRC, the reach of the evaluation and the minimum information required to the licensee that should accompany to their solicitude. (author)

Conformation of an evaluation process for a license renovation solicitude of a nuclear power plant in Mexico. Part 2

International Nuclear Information System (INIS)

Serrano R, M. de L.

2013-10-01

At the present time the operation licenses in force for the reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) will expire in the year 2020 and 2025 for the Unit-1 and Unit-2, respectively, for which the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) has begun its preparation to assist a solicitude of the licensee to continue the operation of the NPP-L V. The present work has the purpose of defining the steps to continue and to generate the documents that would help in this process, as the normative, guides, procedures, regulations, controls, etc. so that the evaluation process will be effective and efficient, as much for the regulator organ as for the licensee. The advance carried out in the continuation of the conformation of an evaluation process of license renovation solicitude is also exposed, taking like base the requirements established by the CNSNS, the regulator organ of the United States (US NRC), and the IAEA for license renovation solicitude of this type. A summary of the licenses granted from the beginning of commercial operation of the NPP-L V is included, both units and the amendments to these licenses, explaining the reason of the amendment shortly and in the dates they were granted. A brief exposition of the nuclear power plants to world level that have received extension of its operation is included. The normative that can be applied in a life extension evaluation is presented, the evaluation process to continue with the guides of the US NRC, the reach of the evaluation and the minimum information required to the licensee that should accompany to their solicitude. (author)

The role of eclogite in the mantle heterogeneity at Cape Verde

DEFF Research Database (Denmark)

Barker, Abigail Katrine; Holm, Paul Martin; Troll, Valentin R.

2014-01-01

The Cape Verde hotspot, like many other Ocean Island Basalt provinces, demonstrates isotopic heterogeneity on a 100–200 km scale. The heterogeneity is represented by the appearance of an EM1-like component at several of the southern islands and with a HIMU-like component present throughout...... have been limited. We apply the minor elements in olivine approach (Sobolev et al. in Nature 434:590–597, 2005; Science, doi:10.1126/science.1138113, 2007), to determine and quantify the contributions of peridotite, pyroxenite and eclogite melts to the mantle heterogeneity observed at Cape Verde. Cores...... of olivine phenocrysts of the Cape Verde volcanics have low Mn/FeO and low Ni*FeO/MgO that deviate from the negative trend of the global array. The global array is defined by mixing between peridotite and pyroxenite, whereas the Cape Verde volcanics indicate contribution of an additional eclogite source...

History of the future; Historia del futuro

Energy Technology Data Exchange (ETDEWEB)

Manzini, Fabio [Centro de Investigacion en Energia (CIE) de la UNAM, Temixco, Morelos (Mexico)

2010-07-01

The desired future is to imagine a world energized by energy sources that do not infringe against our environmental heritage, because the environment is the determining factor in the equation of human sustainability: without environment there is neither society nor economy. In this document are mentioned the energy reserves in Mexico of uranium as a fuel for the Laguna Verde nuclear power plant, Veracruz; coal, oil and natural gas. It also mentions the renewable resources and existing energy scenarios in Mexico. [Spanish] El futuro deseado es imaginarnos un mundo energizado por fuentes de energia que no atenten en contra de nuestro patrimonio ambiental, porque el ambiente es el factor determinante en la ecuacion de la sustentabilidad humana; sin ambiente no existe ni sociedad ni economia. En este documento se mencionan las reservas energeticas en Mexico de uranio como combustible para la central nuclear Laguna Verde, Veracruz; de carbon, de petroleo y gas natural. Se mencionan tambien los recursos renovables existentes y los escenarios energeticos en Mexico.

MCTP, a code for the thermo-mechanical analysis of a fuel rod of BWR type reactors (Neutron part)

International Nuclear Information System (INIS)

Hernandez L, H.; Ortiz V, J.

2003-01-01

In the National Institute of Nuclear Research of Mexico a code for the thermo-mechanical analysis of the fuel rods of the BWR type reactors of the Nucleo electric Central of Laguna Verde is developed. The code solves the diffusion equation in cylindrical coordinates with several energy groups. The code, likewise, calculates the temperature distribution and power distribution in those fuel rods. The code is denominated Multi groups With Temperatures and Power (MCTP). In the code, the energy with which the fission neutrons are emitted it is divided in six groups. They are also considered the produced perturbations by the changes in the temperatures of the materials that constitute the fuel rods, the content of fission products, the uranium consumption and in its case the gadolinium, as well as the plutonium production. In this work there are present preliminary results obtained with the code, using data of operation of the Nucleo electric Central of Laguna Verde. (Author)

MCTP, a code for the thermo-mechanical analysis of a fuel rod of BWR type reactors (Neutron part); MCTP, un codigo para el analisis termo-mecanico de una barra combustible de reactores tipo BWR (Parte Neutronica)

Energy Technology Data Exchange (ETDEWEB)

Hernandez L, H; Ortiz V, J [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2003-07-01

In the National Institute of Nuclear Research of Mexico a code for the thermo-mechanical analysis of the fuel rods of the BWR type reactors of the Nucleo electric Central of Laguna Verde is developed. The code solves the diffusion equation in cylindrical coordinates with several energy groups. The code, likewise, calculates the temperature distribution and power distribution in those fuel rods. The code is denominated Multi groups With Temperatures and Power (MCTP). In the code, the energy with which the fission neutrons are emitted it is divided in six groups. They are also considered the produced perturbations by the changes in the temperatures of the materials that constitute the fuel rods, the content of fission products, the uranium consumption and in its case the gadolinium, as well as the plutonium production. In this work there are present preliminary results obtained with the code, using data of operation of the Nucleo electric Central of Laguna Verde. (Author)

Results of the benchmarking in radiological protection practices during fuel reloads in the nuclear power plants of Limerick (BWR) and Ginna (PWR) in the United States of North America; Resultados del benchmarking en practicas de proteccion radiologica durante recargas de combustible en las centrales nucleoelectricas de Limerick (BWR) y Ginna (PWR) en los Estados Unidos de Norteamerica

Energy Technology Data Exchange (ETDEWEB)

Lara H, M. A., E-mail: marco.lara@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

2011-11-15

The nuclear power plant of Laguna Verde, unique in our country, has been imposed several goals related with the continuous improvement of their acting; increase in the quantity of continuous days for operation cycle, improvement in the chemical indexes of the reactor coolant, improvement in the indexes of nuclear security, improvement in the indicators of industrial security, improvement in the standards of radiological protection, etc.; in this last item is precisely where is necessary to search creative solutions to be able to maintain the collective doses of the personnel so low as reasonably it is possible (ALARA) especially due to the last projects of extension of useful life of the nuclear power plant (zinc injection, noble metals and hydrogen) and of power increment of the nuclear power plant of Laguna Verde, same that represent in the short period an increment of collective dose and of exposition levels (until 200%) in very specific points of the primary systems of the reactor. (Author)

Clima, cultura y disponibilidad de espacios verdes urbanos

OpenAIRE

Sierra, Eduardo Mario; Pérez, Silvia Patricia; Nizzero, Gustavo Raúl

2002-01-01

p.165-171 El rápido crecimiento urbano mundial hace que la calidad de vida dependa cada vez más de la disponibilidad de espacios verdes. Este trabajo trata de relacionar la disponibilidad de espacios verdes urbanos públicos con los factores climáticos y culturales. Las ciudades del Hemisferio Norte en países de cultura europea, donde se llevan a cabo programas de sustentabilidad muestran mayores disponibilidades lo cual refleja el impacto de los factores culturales. Desde el punto de vista...

Modernization programme at Dukovany NPP

International Nuclear Information System (INIS)

Trnka, M.

2000-01-01

The main goal of each NPP is to produce electricity safely, economically and without influence to environment. For Dukovany NPP it means to upgrade all documentation and perform the Equipment Upgrading Programme. All these activities are time and money consuming and therefore the determination of priority of all items was necessary. In the presentation there are mentioned some important changes in documentation, results of PSA studies and reason for Equipment Upgrading Programme performance. It was selected the most important item from the list of Equipment Upgrading Programme the I and C upgrading. Management has decided that Dukovany NPP will become among the best NPPs with WWER type of reactor. It seems this decision is the best way how to extend lifetime of the NPP. (author)

Emergency preparedness at Ignalina NPP

International Nuclear Information System (INIS)

Kairys, A.

1998-01-01

Brief review of Ignalina NPP safety upgrading and personnel preparedness to act in cases of accidents is presented. Though great activities are performed in enhancing the plant operation safety, the Ignalina NPP management pays a lot of attention to preparedness for emergency elimination and take measures to stop emergency spreading. A new Ignalina NPP emergency preparedness plan was drawn up and became operational. It is the main document to carry out organizational, technical, medical, evacuation and other activities to protect plant personnel, population, the plant and the environment from accident consequences. Great assistance was rendered by Swedish experts in drawing this new emergency preparedness plan. The plan consists of 3 parts: general part, operative part and appendixes. The plan is applied to the Ignalina NPP personnel, Special and Fire Brigade and also to other contractor organizations personnel carrying out works at Ignalina NPP. There are set the following emergency classes: incident, emergency situation, alert, local emergency, general emergency. Separate intervention level corresponds to each emergency class. Overview of personnel training to act in case of an emergency is also presented

Palo Verde College Facts, 2001.

Science.gov (United States)

Palo Verde Coll., Blythe, CA.

This is a 2001 report on Palo Verde College (PVC) (California) student demographics, enrollment status, citizenship, educational goals, and academic persistence. Student data were collected and analyzed to meet accrediting standards, improve institutional effectiveness, and fulfill the local district's mission. The report discusses enrollment…

Does climate directly influence NPP globally?

Science.gov (United States)

Chu, Chengjin; Bartlett, Megan; Wang, Youshi; He, Fangliang; Weiner, Jacob; Chave, Jérôme; Sack, Lawren

2016-01-01

The need for rigorous analyses of climate impacts has never been more crucial. Current textbooks state that climate directly influences ecosystem annual net primary productivity (NPP), emphasizing the urgent need to monitor the impacts of climate change. A recent paper challenged this consensus, arguing, based on an analysis of NPP for 1247 woody plant communities across global climate gradients, that temperature and precipitation have negligible direct effects on NPP and only perhaps have indirect effects by constraining total stand biomass (Mtot ) and stand age (a). The authors of that study concluded that the length of the growing season (lgs ) might have a minor influence on NPP, an effect they considered not to be directly related to climate. In this article, we describe flaws that affected that study's conclusions and present novel analyses to disentangle the effects of stand variables and climate in determining NPP. We re-analyzed the same database to partition the direct and indirect effects of climate on NPP, using three approaches: maximum-likelihood model selection, independent-effects analysis, and structural equation modeling. These new analyses showed that about half of the global variation in NPP could be explained by Mtot combined with climate variables and supported strong and direct influences of climate independently of Mtot , both for NPP and for net biomass change averaged across the known lifetime of the stands (ABC = average biomass change). We show that lgs is an important climate variable, intrinsically correlated with, and contributing to mean annual temperature and precipitation (Tann and Pann ), all important climatic drivers of NPP. Our analyses provide guidance for statistical and mechanistic analyses of climate drivers of ecosystem processes for predictive modeling and provide novel evidence supporting the strong, direct role of climate in determining vegetation productivity at the global scale. © 2015 John Wiley & Sons Ltd.

New approach of second Romanian NPP siting

International Nuclear Information System (INIS)

Mauna, Traian

2010-01-01

The NPP sitting studies in Romania began before 1975. The first Romanian NPP CANDU 6 type reactor gone to erection in 1980 on Cernavoda site planned to have 5 units. Gained the experience from Cernavoda NPP sitting, the first mission of new multi-branch of specialists team was to choose new NPP sites adapting the NPP Cernavoda project to the new parameters of close water cooling circuit and hard less and no rock foundation strata. The studies were carrying out in different stages on the inner rivers Olt, Mures, Somes in Transylvania historical region. This paper tries to reconsider shortly the old analysis according to the last IAEA Safety Standards, taking into account the new NPP generation requirement. Paper is focused on geological aspects and other local sites characteristics. (authors)

Tourism in Laguna (SC): Impacts and attitude.

OpenAIRE

Susana de Araujo Gastal; Sandra Dall'Agnol

2012-01-01

The places by the sea, as spaces of tourism and second homes, suffer the impacts from the activity. The local population attitude, seeing these places as bonuses or otherwise, as a burden, contributes to the viability of tourism in the locality. This article aims to present a research, methodologically related to attitude construct of social psychology, conducted in Laguna, Santa Catarina, Brazil to evaluate the relationship between the community and the different impacts caused by tourism,. ...

Specification of requirements to get a license for an Independent Spent Fuel Dry Storage Installation (ISFSI) at the site of the NPP-LV; Especificacion de los requerimientos para tramitar una licencia de una instalacion independiente de almacenamiento temporal en seco de combustible gastado (ISFSI) en el sitio de la CNLV

Energy Technology Data Exchange (ETDEWEB)

Serrano R, M. L., E-mail: mlserrano@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

2015-09-15

This article describes some of the work done in the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) to define specifically the requirements that the Federal Electricity Commission (CFE) shall meet to submit for consideration of CNSNS an operation request of an Independent Spent Fuel Dry Storage Installation (ISFSI). The project of a facility of this type arose from the need to provide storage capacity for spent nuclear fuel in the nuclear power plant of Laguna Verde (NPP-LV) and to continue the operation at the same facility in a safe manner. The licensing of these facilities in the United States of America has two modes: specific license or general license. The characteristics of these licenses are described in this article. However, in Mexico the existing national legislation is not designed for such license types, in fact there is a lack of standards or regulations in this regard. The regulatory law of Article 27 of the Constitution in the nuclear matter, only generally establishes that this type of facility requires an authorization from the Ministry of Energy. For this reason and because there is not a national legislation, was necessary to use the legislation that provides the Nuclear Regulatory Commission of USA, the US NRC. However, it cannot be applied as is established, so was necessary that the CNSNS analyze one by one the requirements of both types of license and determine what would be required to NPP-LV to submit its operating license of ISFSI. The American regulatory applicable to an ISFSI, the 10-Cfr-72 of the US NRC, establishes the requirements for both types of licenses. Chapter 10-Cfr was analyzed in all its clauses and coupled to the laws, regulations and standards as well as to the requirements established by CNSNS, all associated with a store spent fuel on site; the respective certification of containers for spent fuel dry storage was not included in this article, even though the CNSNS also performed that activity under the

75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

Science.gov (United States)

2010-08-24

... Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental Assessment and Finding of No.... NPF-74, issued to Arizona Public Service Company (APS, the licensee), for operation of Palo Verde... Statement for the Palo Verde Nuclear Generating Station, NUREG-0841, dated February 1982. Agencies and...

77 FR 9974 - Notice of Entering Into a Compact With the Republic of Cape Verde

Science.gov (United States)

2012-02-21

... Republic of Cape Verde AGENCY: Millennium Challenge Corporation. ACTION: Notice. SUMMARY: In accordance..., and the Republic of Cape Verde. Representatives of the United States Government and the Republic of Cape Verde executed the Compact documents on February 10, 2012. Dated: February 14, 2012. Melvin F...

The seismic reassessment Mochovce NPP

International Nuclear Information System (INIS)

Baumeister, P.

2004-01-01

The design of Mochovce NPP was based on the Novo-Voronez type WWER-440/213 reactor - twin units. Seismic characteristic of this region is characterized by very low activity. Mochovce NPP site is located on the rock soil with volcanic layer (andesit). Seismic reassessment of Mochovce NPP was done in two steps: deterministic approach up to commissioning confirmed value Horizontal Peak Ground Acceleration HPGA=0.1 g and activities after commissioning as a consequence of the IAEA mission indicate higher hazard values. (author)

NPDES Permit for Mesa Verde National Park Wastewater Treatment Facility in Colorado

Science.gov (United States)

Under NPDES permit number CO-0034398, the United States Department of the Interior, National Park Service, Mesa Verde National Park is authorized to discharge from the Mesa Verde National Park wastewater treatment plant, in Montezuma County, Colo.

Ignalina NPP: living and working conditions

International Nuclear Information System (INIS)

Chiuzhas, A.

1998-01-01

The conference was devoted to discuss the social problems related with the operation of Ignalina NPP. The main topics are the following: analysis of public opinion of surrounding region of Ignalina NPP including neighbouring Daugavpils district in Latvia, environment impact evaluation of Daugavpils district, assessment of the influence of Ignalina NPP operation to the development of business in the region, investigation of problems of Visaginas town - residence of Ignalina NPP personnel. The specificity of Visaginas (former Sniechkus) is defined by the majority of non-native Lithuanians living there. Cultural transformation and political organization of the region were surveyed as well

Is a changing climate affecting the tropical cyclone behavior of Cape Verde?

Science.gov (United States)

Emmenegger, T. W.; Mann, M. E.; Evans, J. L.

2016-12-01

An existing dataset of synthetic tropical cyclone (TC) tracks derived from climate change simulations were used to explore TC variability within a 250 km radius of the Cape Verde Islands (16.5388N, 23.0418W). The synthetic sets were examined according to genesis point location, track projection, intensity, frequency, and seasonality within the observational era (1851 AD to present). These factors of TC variability have been shown to be strongly related to climate oscillations, thus the historical era was grouped by the increasing and decreasing regimes of sea surface temperature (SST) in the main development region (MDR) of the Atlantic Ocean. Numerous studies have examined Atlantic Basin activity throughout this era; the goal of this study is to investigate possible variations in TC behavior around Cape Verde, ultimately determining whether Cape Verde experiences similar fluctuations in activity as observed basin-wide. We find that several facets of TC variability such as intensity, seasonality, and genesis point location around Cape Verde are not significantly different to that of the entire basin, thus forecasts of the entire basin in these respects may also apply to our site. A long-term trend of increasing TC frequency can be identified basin-wide within the observed set, yet activity around Cape Verde does not display this same behavior observably or in any synthetic set. A relationship between the location of genesis points and the regimes of SST fluctuation is shown to be existent. We find both more observed and synthetic genesis points within the vicinity of Cape Verde during cool periods, and an eastward and equatorward shift in cyclogenesis is evident during warm regimes. This southeastern shift in genesis points attributes to the increased intensities of TCs seen during periods of warmer SST. Years of increased SST are additionally linked to an earlier seasonality in Cape Verde.

High-$\\gamma$ Beta Beams within the LAGUNA design study

CERN Document Server

Orme, Christopher

2010-01-01

Within the LAGUNA design study, seven candidate sites are being assessed for their feasibility to host a next-generation, very large neutrino observatory. Such a detector will be expected to feature within a future European accelerator neutrino programme (Superbeam or Beta Beam), and hence the distance from CERN is of critical importance. In this article, the focus is a $^{18}$Ne and $^{6}$He Beta Beam sourced at CERN and directed towards a 50 kton Liquid Argon detector located at the LAGUNA sites: Slanic (L=1570 km) and Pyh\\"{a}salmi (L=2300 km). To improve sensitivity to the neutrino mass ordering, these baselines are then combined with a concurrent run with the same flux directed towards a large Water \\v{C}erenkov detector located at Canfranc (L=650 km). This degeneracy breaking combination is shown to provide comparable physics reach to the conservative Magic Baseline Beta Beam proposals. For $^{18}$Ne ions boosted to $\\gamma=570$ and $^{6}$He ions boosted to $\\gamma=350$, the correct mass ordering can be...

Achieving engineering excellence at Palo Verde

International Nuclear Information System (INIS)

Prawlocki, F.C.

1989-01-01

Early in 1988, the management of the newly formed Palo Verde Nuclear Generating Station (PVNGS) Engineering and Construction Division was faced with a dilemma: how to build a competent, confident, efficient engineering organization in the face of increasing requirements and tightened fiscal controls. This paper discusses steps taken by Palo Verde to address actions taken to effect a smooth transition from construction to operations and the development of the Engineering Excellence Program. The Engineering Excellence Program will continue to evolve over time as the number of the NED's [Nuclear Engineering Department] personnel grown and processes are changed over the course of the next few years. As tasks from the Engineering Excellence Program action plan are completed, the results achieved are expected to be integrated into the routine business of the NED

Subsidence of the Laguna Salada Basin, northeastern Baja California, Mexico, inferred from Milankovitch climatic changes

Energy Technology Data Exchange (ETDEWEB)

Contreras, Juan; Martin-Barajas, Arturo [Departamento de Geologia, CICESE, Ensenada Baja California (Mexico); Herguera, Juan Carlos [Division de Oceanologia, CICESE, Ensenada Baja California (Mexico)

2005-01-15

Laguna Salada in northern Baja California, Mexico, is an active half-graben product of the trans-tensional tectonics of the Gulf of California. It is sensitive to changes in sediment supply from the Colorado River basin. We present a time series analysis of the upper 980 m of a gamma-ray log from a borehole drilled near the Laguna Salada fault. The power spectrum of the gammaray log resembles the spectrum of {delta}{sup 1}8{omicron} Pleistocene isotopic variations from ice cores and from the deep ocean, known to be strongly controlled by Milankovitch cycles. We correlate {delta}{sup 1}8{omicron} stages with silty and sandy intervals in the log. Downcore ages for the last 780 ky are constrained within {approx}10 kyr. We derive a simple time vs. depth calibration relation for the basin over this time interval. Estimated sedimentation rates at the drill site appear to be constant with a value of {approx}1.6 mm/yr. We propose that this subsidence rate is produced by the Laguna Salada fault. [Spanish] La cuenca de Laguna Salada en el norte de Baja California, Mexico, es un semigraben activo producto de la tectonica ranstensional del Golfo de California. Esta cuenca endorreica es sensible a cambios en sedimentacion por variaciones en el aporte e sedimentos de fuentes cercanas y distales transportados por arroyos de las sierras adyacentes y por el Rio Colorado. Esta cuenca es un sitio excepcional para explorar el uso de cambios climaticos ciclicos como herramienta de datacion y estimar tasas de sedimentacion y subsidencia en el area. Para demostrar esto se presenta un analisis de series de tiempo de un registro de rayos de gama de un pozo geotermico exploratorio perforado adyacente a la falla de Laguna Salada, la cual limita el margen oriental de la cuenca. Los resultados del analisis indican que el espectro de los primeros 980 m del registro de rayos gama tiene una alta coherencia con el espectro de registros isotopicos paleoclimaticos de {delta}{sup 1}8{omicron} del

Waterbirds (other than Laridae nesting in the middle section of Laguna Cuyutlán, Colima, México

Directory of Open Access Journals (Sweden)

Eric Mellink

2008-03-01

Full Text Available Laguna de Cuyutlán, in the state of Colima, Mexico, is the only large coastal wetland in a span of roughly 1150 km. Despite this, the study of its birds has been largely neglected. Between 2003 and 2006 we assessed the waterbirds nesting in the middle portion of Laguna Cuyutlán, a large tropical coastal lagoon, through field visits. We documented the nesting of 15 species of non-Laridae waterbirds: Neotropic Cormorant (Phalacrocorax brasilianus, Tricolored Egret (Egretta tricolor, Snowy Egret (Egretta thula, Little Blue Heron (Egretta caerulea, Great Egret (Ardea alba, Cattle Egret (Bubulcus ibis, Black-crowned Nightheron (Nycticorax nycticorax, Yellow-crowned Night-heron (Nyctanassa violacea, Green Heron (Butorides virescens, Roseate Spoonbill (Platalea ajaja, White Ibis (Eudocimus albus, Black-bellied Whistling-duck (Dendrocygna autumnalis, Clapper Rail (Rallus longirostris, Snowy Plover (Charadrius alexandrinus, and Black-necked Stilt (Himantopus mexicanus. These add to six species of Laridae known to nest in that area: Laughing Gulls (Larus atricilla, Royal Terns (Thalasseus maximus, Gull-billed Terns (Gelochelidon nilotica, Forster’s Terns (S. forsteri, Least Terns (Sternula antillarum, and Black Skimmer (Rynchops niger, and to at least 57 species using it during the non-breeding season. With such bird assemblages, Laguna Cuyutlán is an important site for waterbirds, which should be given conservation status. Rev. Biol. Trop. 56 (1: 391-397. Epub 2008 March 31.Durante la prospección de la parte media de la Laguna Cuyutlán, una gran laguna costera en Colima, México, entre 2003 y 2006, documentamos la anidación de 15 especies de aves acuáticas que no pertenecer a la familia Laridae: Phalacrocorax brasilianus, Egretta tricolor, Egretta thula, Egretta caerulea, Ardea alba, Bubulcus ibis, Nycticorax nycticorax, Nyctanassa violacea, Butorides virescens, Platalea ajaja, Eudocimus albus, Dendrocygna autumnalis, Rallus longirostris

Spain in South Ukraine NPP

International Nuclear Information System (INIS)

Ibanez, M.

1994-01-01

A Technical Assistance Protocol was signed between the Governments of the GIS and the Commission of the European Union (CEU) on August 2, 1991 and this was the starting point of the TACIS program. In this article, the activities described are those related to the TACIS-92/93/94 on site technical assistance to South Ukraine NPP (SUK NPP). Within the scope of the TACIS 92 Program the CEU and the Ukrainian Authorities agreed a list of projects to be implemented at South Ukraine NPP with the aim to improve the operational safety of the plant. This part of the program is called TACIS 92 on-site activities. The total budget allocated to these projects is a MECU. The European Union ''utility'' selected to lead this program at South Ukraine NPP was UNESA and the first contract to cover our activities was signed in July 1993 between the CEU (Mr. Pablo Benavides) and UNESA (Mr. Pedro Rivero). The projects will be implemented at SUK NPP but according to the contract UNESA is ''The Consultant'' and GOSKOMATON (The Ukrainian Sate Committee on Nuclear Power Utilization) is the ''Recipient Institution''. (Author)

Selection of NPP for Kazakhstan

International Nuclear Information System (INIS)

Zhotabaev, Zh.R.

2003-01-01

Commercial NPP for Kazakhstan should to meet to several main requirements: 1). Safety operation (accident probability not more than 10 -6 1/p. year). 2). High efficiency > 40 %. 3). Possibility of use for high-temperature chemistry and hydrogen production. 4). Possibility for manufacturing of considerable part of equipment in Kazakhstan. 5). Possibility for fuel production and reprocessing in Kazakhstan. 6). Independence from existence of large water-supply sources. Comparative analysis of several NPP with different reactors (WWR-1000, Candu, BREST, VG-400; graphite molten salt reactor) shows that NPP with the graphite molten salt reactor meets to all above requirements, but hydrogen production it is possible by more complete 4-stage technology, since coolant temperature is 800 Deg. C. The principle advantage is possibility of manufacturing of main equipment and fuel in Kazakhstan that reduce the cost of NPP construction and operation

Origin and evolution of the Laguna Potrok Aike maar (Patagonia, Argentina)

Science.gov (United States)

Gebhardt, A. C.; de Batist, M.; Niessen, F.; Anselmetti, F. S.; Ariztegui, D.; Ohlendorf, C.; Zolitschka, B.

2009-04-01

Laguna Potrok Aike, a maar lake in southern-most Patagonia, is located at about 110 m a.s.l. in the Pliocene to late Quaternary Pali Aike Volcanic Field (Santa Cruz, southern Patagonia, Argentina) at about 52°S and 70°W, some 20 km north of the Strait of Magellan and approximately 90 km west of the city of Rio Gallegos. The lake is almost circular and bowl-shaped with a 100 m deep, flat plain in its central part and an approximate diameter of 3.5 km. Steep slopes separate the central plain from the lake shoulder at about 35 m water depth. At present, strong winds permanently mix the entire water column. The closed lake basin contains a sub saline water body and has only episodic inflows with the most important episodic tributary situated on the western shore. Discharge is restricted to major snowmelt events. Laguna Potrok Aike is presently located at the boundary between the Southern Hemispheric Westerlies and the Antarctic Polar Front. The sedimentary regime is thus influenced by climatic and hydrologic conditions related to the Antarctic Circumpolar Current, the Southern Hemispheric Westerlies and sporadic outbreaks of Antarctic polar air masses. Previous studies demonstrated that closed lakes in southern South America are sensitive to variations in the evaporation/precipitation ratio and have experienced drastic lake level changes in the past causing for example the desiccation of the 75 m deep Lago Cardiel during the Late Glacial. Multiproxy environmental reconstruction of the last 16 ka documents that Laguna Potrok Aike is highly sensitive to climate change. Based on an Ar/Ar age determination, the phreatomagmatic tephra that is assumed to relate to the Potrok Aike maar eruption was formed around 770 ka. Thus Laguna Potrok Aike sediments contain almost 0.8 million years of climate history spanning several past glacial-interglacial cycles making it a unique archive for non-tropical and non-polar regions of the Southern Hemisphere. In particular, variations of

Kinetic data bank for Ramona of the Siemens 9x9-IX

International Nuclear Information System (INIS)

Alonso V, G.

1993-12-01

With the purpose of making the transitory analyses of the Laguna Verde Nuclear Power station when Siemens fuel of the type 9x9-IX is used, proposed for the cycle 2 of the Unit 2, the kinetic data bank in hot condition for the Ramona code has been generated. (Author)

A brief overview of Ignalina NPP safety issues

International Nuclear Information System (INIS)

Almenas, K.; Ushpuras, E.

1998-01-01

A description of the safety of Ignalina NPP in a very popular form is presented. Answers to the most frequently recurring questions concerning the Ignalina NPP are provided based on recently completed international studies. Questions are like these: can a similar accident to the one that occurred in Chernobyl take place at Ignalina NPP, does the Ignalina NPP have a containment, what are the probabilities and potential consequences of accidents, etc. The brochure contains a short description of Ignalina NPP safety improvement programs

Population size, breeding biology and on-land threats of Cape Verde petrel (Pterodroma feae) in Fogo Island, Cape Verde.

Science.gov (United States)

Militão, Teresa; Dinis, Herculano Andrade; Zango, Laura; Calabuig, Pascual; Stefan, Laura M; González-Solís, Jacob

2017-01-01

Cape Verde petrel (Pterodroma feae) is currently considered near threatened, but little is known about its population size, breeding biology and on land threats, jeopardizing its management and conservation. To improve this situation, we captured, marked and recaptured (CMR) birds using mist-nets over 10 years; measured and sexed them; monitored up to 14 burrows, deployed GPS devices on breeders and analyzed activity data of geolocators retrieved from breeders in Fogo (Cape Verde). We set cat traps over the colony and investigated their domestic/feral origin by marking domestic cats from a nearby village with transponders, by deploying GPS devices on domestic cats and by performing stable isotope analyses of fur of the trapped and domestic cats. The population of Fogo was estimated to be 293 birds, including immatures (95% CI: 233-254, CMR modelling). Based on geolocator activity data and nest monitoring we determined the breeding phenology of this species and we found biometric differences between sexes. While monitoring breeding performance, we verified a still ongoing cat predation and human harvesting. Overall, data gathered from trapped cats without transponder, cats GPS trips and the distinct isotopic values between domestic and trapped cats suggest cats visiting the colony are of feral origin. GPS tracks from breeders showed birds left and returned to the colony using the sector NE of the islands, where high level of public lights should be avoided specially during the fledging period. Main threats for the Cape Verde petrel in the remaining breeding islands are currently unknown but likely to be similar to Fogo, calling for an urgent assessment of population trends and the control of main threats in all Cape Verde Islands and uplisting its conservation status.

Population size, breeding biology and on-land threats of Cape Verde petrel (Pterodroma feae in Fogo Island, Cape Verde.

Directory of Open Access Journals (Sweden)

Teresa Militão

Full Text Available Cape Verde petrel (Pterodroma feae is currently considered near threatened, but little is known about its population size, breeding biology and on land threats, jeopardizing its management and conservation. To improve this situation, we captured, marked and recaptured (CMR birds using mist-nets over 10 years; measured and sexed them; monitored up to 14 burrows, deployed GPS devices on breeders and analyzed activity data of geolocators retrieved from breeders in Fogo (Cape Verde. We set cat traps over the colony and investigated their domestic/feral origin by marking domestic cats from a nearby village with transponders, by deploying GPS devices on domestic cats and by performing stable isotope analyses of fur of the trapped and domestic cats. The population of Fogo was estimated to be 293 birds, including immatures (95% CI: 233-254, CMR modelling. Based on geolocator activity data and nest monitoring we determined the breeding phenology of this species and we found biometric differences between sexes. While monitoring breeding performance, we verified a still ongoing cat predation and human harvesting. Overall, data gathered from trapped cats without transponder, cats GPS trips and the distinct isotopic values between domestic and trapped cats suggest cats visiting the colony are of feral origin. GPS tracks from breeders showed birds left and returned to the colony using the sector NE of the islands, where high level of public lights should be avoided specially during the fledging period. Main threats for the Cape Verde petrel in the remaining breeding islands are currently unknown but likely to be similar to Fogo, calling for an urgent assessment of population trends and the control of main threats in all Cape Verde Islands and uplisting its conservation status.

HLA polymorphisms in Cabo Verde and Guiné-Bissau inferred from sequence-based typing.

Science.gov (United States)

Spínola, Hélder; Bruges-Armas, Jácome; Middleton, Derek; Brehm, António

2005-10-01

Human leukocyte antigen (HLA)-A, -B, and -DRB1 polymorphisms were examined in the Cabo Verde and Guiné-Bissau populations. The data were obtained at high-resolution level, using sequence-based typing. The most frequent alleles in each locus was: A*020101 (16.7% in Guiné-Bissau and 13.5% in Cabo Verde), B*350101 (14.4% in Guiné-Bissau and 13.2% in Cabo Verde), DRB1*1304 (19.6% in Guiné-Bissau), and DRB1*1101 (10.1% in Cabo Verde). The predominant three loci haplotype in Guiné-Bissau was A*2301-B*1503-DRB1*1101 (4.6%) and in Cabo Verde was A*3002-B*350101-DRB1*1001 (2.8%), exclusive to northwestern islands (5.6%) and absent in Guiné-Bissau. The present study corroborates historic sources and other genetic studies that say Cabo Verde were populated not only by Africans but also by Europeans. Haplotypes and dendrogram analysis shows a Caucasian genetic influence in today's gene pool of Cabo Verdeans. Haplotypes and allele frequencies present a differential distribution between southeastern and northwestern Cabo Verde islands, which could be the result of different genetic influences, founder effect, or bottlenecks. Dendrograms and principal coordinates analysis show that Guineans are more similar to North Africans than other HLA-studied sub-Saharans, probably from ancient and recent genetic contacts with other peoples, namely East Africans.

The cone snails of Cape Verde: Marine endemism at a terrestrial scale

Directory of Open Access Journals (Sweden)

Howard Peters

2016-07-01

Full Text Available Cape Verde in the Eastern Atlantic is typical of many island groups in supporting a wealth of endemic species both terrestrial and marine. Marine gastropod molluscs of the genus Conus, commonly known as cone snails, occur in coastal tropical waters throughout the globe, but in Cape Verde their endemism reaches its apogee with 53 out of 56 species occurring nowhere else, the majority of which are restricted to single islands and frequently to single bays. However, Cape Verde is rapidly moving to a tourism-based economy with a projected boom in infrastructure development often coincidental with the shallow-water habitat of many range-restricted Conus. The conservation assessment of Conus to standards of the International Union for the Conservation of Nature (IUCN Red List of Endangered Species, found that 45.3% of 53 species assessed from Cape Verde are threatened or near-threatened with extinction compared to 7.4% of 579 species in the rest of the world. The only three Conus species globally assessed as Critically Endangered and on the cusp of extinction are all endemic to Cape Verde. Our analysis of Conus species distribution, together with spatial data of coastal protected areas and tourism development zones, identify important areas for future research and new marine protection. Our findings show that endemism with its associated risks for Conus in Cape Verde has worldwide parallels with many non-marine taxa, while our proposed strategy for Conus conservation extends beyond the confines of the country and this taxonomic group.

Bats of Mesa Verde National Park, Colorado: composition, reproduction, and roosting habits.

Science.gov (United States)

O'Shea, Thomas J.; Cryan, Paul M.; Snider, E. Apple; Valdez, Ernest W.; Ellison, Laura E.; Neubaum, Daniel J.

2011-01-01

We determined the bat fauna at Mesa Verde National Park (Mesa Verde) in 2006 and 2007, characterized bat elevational distribution and reproduction, and investigated roosting habits of selected species. We captured 1996 bats of 15 species in mist nets set over water during 120 nights of sampling and recorded echolocation calls of an additional species. The bat fauna at Mesa Verde included every species of bat known west of the Great Plains in Colorado, except the little brown bat (Myotis lucifugus). Some species showed skewed sex ratios, primarily due to a preponderance of males. Thirteen species of bats reproduced at Mesa Verde. Major differences in spring precipitation between the 2 years of our study were associated with differences in reproductive rates and, in some species, with numbers of juveniles captured. Reduced reproductive effort during spring drought will have a greater impact on bat populations with the forecasted increase in aridity in much of western North America by models of global climate change. We radiotracked 46 bats of 5 species to roosts and describe the first-known maternity colonies of spotted bats (Euderma maculatum) in Colorado. All 5 species that we tracked to diurnal roosts relied almost exclusively on rock crevices rather than trees or snags, despite the presence of mature forests at Mesa Verde and the use of trees for roosts in similar forests elsewhere by some of these species. Comparisons with past bat surveys at Mesa Verde and in surrounding areas suggest no dramatic evidence for effects of recent stand-replacing fires on the composition of the bat community.

ASPECTOS HIDROLOGICOS DE LAS LAGUNAS DE ATASTA Y POM, MEXICO

Directory of Open Access Journals (Sweden)

Alejandro Ruiz-Marín

2009-01-01

Full Text Available Las lagunas de Pom y Atasta forman parte del área natural protegida de flora y fauna laguna de Términos en la región de Campeche, México. Esta es una  importante área ecológica ya que es el habitad de muchas especies nativas y migratorias. Estas lagunas han sido afectadas por actividades industriales y por descargas de aguas residuales. Monitoreo de nitrógeno, fósforo y coliformes fecales en agua superficial fueron realizados a lo largo de ambas lagunas durante las temporadas de seca, lluvia y nortes durante un año. Las altas temperaturas en verano (31 ºC y mínimas en nortes (25ºC fueron asociadas con valores de oxigeno disuelto (5.1 y 6.3 mg l-1, respectivamente indicando también una probable relación con la actividad fitoplanctonica. El pH (8.0-8.2 y la salinidad (0.32 - 3.48 UPS no mostraron variación significativa entre las tres temporadas climáticas. El nivel de amonio no fue mayor a los valores sugeridos para el control de eutroficación (0.1 mg l-1, mientras que los niveles de fósforo fueron de mayor concentración (2.0-3.5 mg l-1 que aquellos considerados seguros (0.01-0.125 mg l-1 para el medio ambiente. Las más altas concentraciones de N y P cerca de las áreas habitadas sugiere un importante contribución de nutrientes provenientes de aguas de desecho, asociado con la descomposición de material orgánico. La concentración de coliformes fecales durante la temporada de lluvias y nortes (8.0-26.0 MPN 100 ml-1 fue mayor que durante la temporada de seca (1.3-3.5 MPN 100 ml-1 sugiriendo un importante acceso por escurrimiento pluvial y aguas residuales no tratadas proveniente de las áreas cercanas al lago habitadas. La deforestación de manglares y la descontrolada actividad de agricultura afectaran la calidad del agua en ambos lagos en el futuro.

75 FR 47808 - Verde Hydro, LLC; Notice of Preliminary Permit Application Accepted for Filing and Soliciting...

Science.gov (United States)

2010-08-09

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 13819-000] Verde Hydro, LLC... Intervene, and Competing Applications August 2, 2010. On July 21, 2010, Verde Hydro, LLC filed an... the feasibility of the Verde Hydroelectric Project, located in Maricopa County, in the State of...

NPP Krsko decommissioning concept

International Nuclear Information System (INIS)

Novsak, M.; Fink, K.; Spiler, J.

1996-01-01

At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP Krsko. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for a decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill the decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economic aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling of all activities necessary for the decommissioning of the NPP Krsko are presented. (author)

NPP Krsko decommissioning concept

International Nuclear Information System (INIS)

Novsak, M.; Fink, K.; Spiler, J.

1996-01-01

At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP KRSKO. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and the results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economical aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling all activities necessary for the decommissioning of the NPP KRSKO are presented. (author)

Graphic console for analysis of severe accidents visualization of OEs, NAEs and calculation of the source term for the NPP-LV (CoGrAAS); Consola grafica para analisis de accidentes severos visualizacion de OEs, NAEs y calculo del termino fuente para la CLV (CoGrAAS)

Energy Technology Data Exchange (ETDEWEB)

Sandoval V, S.; Mendoza E, P. R.; Gonzalez C, J. M.; Cecenas F, M. [Instituto Nacional de Electricidad y Energias Limpias, Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Tijerina S, F., E-mail: francisco.tijerina@cfe.gob.mx [CFE, Central Nucleoelectrica Laguna Verde, Carretera Federal Cardel-Nautla Km 42.5, 91476 Municipio Alto Lucero, Veracruz (Mexico)

2016-09-15

In response to the Fukushima Daiichi nuclear power plant accident, the NRC conducted an analysis and issued recommendations to improve the safety of the nuclear reactors. These include strengthening and integrating emergency response capabilities and emphasizing periodic staff training, the performance of simulation exercises. As a tool to observe these recommendations, the Graphic Console was developed for Analysis of Severe Accidents, Visualization of OEs, NAEs and calculation of the source term for nuclear power plant of Laguna Verde (NPP-LV ; CoGrAAS). The CoGrAAS is a computer system that displays in an integrated, graphic and dynamic way the information of a catalog of previously simulated accident scenarios. Has core mimics, vessel, primary containment and safety systems, trend graph of thermodynamic and radiological variables and the emergency procedures (OEs), chronological list of events, windows with detailed information for the dry-well, among others. The use of CoGrAAS allows that staff to understand and become familiar with the thermo-hydraulic progression of actual scenarios that exceed the design basis including those with core damage as severe accidents. The system enables personnel to develop an integral vision of the scenarios during the exercises and drills by observing and analyzing the evolution of the main reactor, core and primary containment variables, the response of emergency systems and the influence of that progression on OEs and the emergency action levels (NAEs). The CoGrAAS allows o observe the radiological variables and obtain the source term, to make the projection of doses, at any time within the scenario evolution. Thus, not only can the phenomenology of severe accidents be analyzed and understood, it is also possible to exercise, verify and evaluate the performance of critical tasks in the application of procedures, guidelines and emergency management plans. (Author)

Corredores verdes urbanos: estudo da viabilidade de conexão das áreas verdes de Vitória

Directory of Open Access Journals (Sweden)

Homero Marconi Penteado

2007-12-01

Full Text Available Grande parte dos profissionais de planejamento urbano tem buscado melhorar a qualidade de vida da população e a aplicação de princípios de sustentabilidade, que se refletem, na maioria dos casos, na busca de ampliação das áreas verdes, sejam na forma de parques, praças, arborização de vias ou mesmo incentivo aos jardins particulares. Esta pesquisa apresenta o resultado do estudo de viabilidade de criação de corredores verdes urbanos na cidade de Vitória, estabelecendo uma rede de conexões utilizando-se de sua malha viária, visando incrementar as condições ecológicas e paisagísticas urbanas e melhores condições de circulação de pedestres e ciclistas. Está alicerçada nos conceitos desenvolvidos pela ecologia da paisagem, baseada em fragmentos, corredores e matriz. A metodologia adotada foi aplicada em uma área teste, onde foram realizados levantamentos preliminares, mapeamento das áreas verdes, seleção de vias para implantação de corredores, avaliação dos possíveis corredores, inventário e análise das vias, diretrizes para estabelecimento dos corredores, ensaio projetual e criação de uma rede de corredores verdes. Dentre os principais resultados, verificou-se a possibilidade de criação de corredores com pequenas modificações nos perfis de vias que permitiriam a inserção de vegetação contínua, calçadas e ciclovias com consequências diretas (otimização das condições microclimáticas, melhoria na paisagem, atratividade para pequenos animais, incentivo ao percurso não motorizado, entre outros e indiretas (redução das partículas em suspensão, redução dos níveis de ruído e do consumo de combustíveis etc..

Operation Aspect of the Main Control Room of NPP

International Nuclear Information System (INIS)

Sahala M Lumbanraja

2009-01-01

The main control room of Nuclear Power Plant (NPP) is operational centre to control all of the operation activity of NPP. NPP must be operated carefully and safely. Many aspect that contributed to operation of NPP, such as man power whose operated, technology type used, ergonomic of main control room, operational management, etc. The disturbances of communication in control room must be anticipated so the high availability of NPP can be achieved. The ergonomic of the NPP control room that will be used in Indonesia must be designed suitable to anthropometric of Indonesia society. (author)

Analysis of the three dimensional core kinetics NESTLE code coupling with the advanced thermo-hydraulic code systems, RELAP5/SCDAPSIM and its application to the Laguna Verde Central reactor; Analisis para el acoplamiento del codigo NESTLE para la cinetica tridimensional del nucleo al codigo avanzado de sistemas termo-hidraulicos, RELAP5/SCDAPSIM y su aplicacion al reactor de la CNLV

Energy Technology Data Exchange (ETDEWEB)

Salazar C, J H; Nunez C, A [CNSNS, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D.F. (Mexico); Chavez M, C [UNAM, Facultad de Ingenieria, DEPFI Campus Morelos (Mexico)

2004-07-01

The objective of the written present is to propose a methodology for the joining of the codes RELAP5/SCDAPSIM and NESTLE. The development of this joining will be carried out inside a doctoral program of Engineering in Energy with nuclear profile of the Ability of Engineering of the UNAM together with the National Commission of Nuclear Security and Safeguards (CNSNS). The general purpose of this type of developments, is to have tools that are implemented by multiple programs or codes such a that systems or models of the three-dimensional kinetics of the core can be simulated and those of the dynamics of the reactor (water heater-hydraulics). In the past, by limitations for the calculation of the complete answer of both systems, the developed models they were carried out for separate, putting a lot of emphasis in one but neglecting the other one. These methodologies, calls of better estimate, will be good to the nuclear industry to evaluate, with more high grades of detail, the designs of the nuclear power plant (for modifications to those already existent or for new concepts in the designs of advanced reactors), besides analysing events (transitory and have an accident), among other applications. The coupled system was applied to design studies and investigation of the Laguna Verde Nuclear power plant (CNLV). (Author)

Implementacion de modulos constructivistas que atiendan "misconceptions" y lagunas conceptuales en temas de la fisica en estudiantes universitarios

Science.gov (United States)

Santacruz Sarmiento, Neida M.

Este estudio se enfoco en los "misconception" y lagunas conceptuales en temas fundamentales de Fisica como son Equilibrio Termodinamico y Estatica de fluidos. En primer lugar se trabajo con la identificacion de "misconceptions" y lagunas conceptuales y se analizo en detalle la forma en que los estudiantes construyen sus propias teorias de fenomenos relacionados con los temas. Debido a la complejidad en la que los estudiantes asimilan los conceptos fisicos, se utilizo el metodo de investigacion mixto de tipo secuencial explicativo en dos etapas, una cuantitativa y otra cualitativa. La primera etapa comprendio cuatro fases: (1) Aplicacion de una prueba diagnostica para identificar el conocimiento previo y lagunas conceptuales. (2) Identificacion de "misconceptions" y lagunas del concepto a partir del conocimiento previo. (3) Implementacion de la intervencion por medio de modulos en el topico de Equilibrio Termodinamico y Estatica de Fluidos. (4) Y la realizacion de la pos prueba para analizar el impacto y la efectividad de la intervencion constructivista. En la segunda etapa se utilizo el metodo de investigacion cualitativo, por medio de una entrevista semiestructurada que partio de la elaboracion de un mapa conceptual y se finalizo con un analisis de datos conjuntamente. El desarrollo de este estudio permitio encontrar "misconceptions" y lagunas conceptuales a partir del conocimiento previo de los estudiantes participantes en los temas trabajados, que fueron atendidos en el desarrollo de las distintas actividades inquisitivas que se presentaron en el modulo constructivista. Se encontro marcadas diferencias entre la pre y pos prueba en los temas, esto se debio al requerimiento de habilidades abstractas para el tema de Estatica de Fluidos y al desarrollo intuitivo para el tema de Equilibrio Termodinamico, teniendo mejores respuestas en el segundo. Los participantes demostraron una marcada evolucion y/o cambio en sus estructuras de pensamiento, las pruebas estadisticas

Eficiencia del tratamiento de residuales porcinos en digestores de laguna tapada

Directory of Open Access Journals (Sweden)

D Blanco

Full Text Available Se evaluó la eficiencia de dos lagunas tapadas, diseñadas para tratar los residuales de las granjas porcinas P-3 y T-2.1 _pertenecientes a la Asociación de Porcicultores de Yucatán, México_, con el objetivo de verificar la factibilidad de implementar en Cuba esta tecnología. Los indicadores físico-químicos y microbiológicos de los efluentes fueron determinados en el momento de su entrada y su salida de los digestores, y a su salida del lago de estabilización. El digestor de la granja P-3 logró remover más del 90 % de la demanda química de oxígeno (DQO y hasta el 71 % de los sólidos suspendidos totales (SST presentes; mientras que el digestor de la granja T-2.1 alcanzó una remoción del 78 % en la DQO y el 62 % de los SST. Los análisis sanitarios indicaron que las bacterias coliformes totales presentaron una disminución importante, de 2,4 x 108 a 1,7 x 103 en la granja P-3 y de 4,2 x 107 a 2,7 x 103 en la granja T-2.1. En ambas lagunas, los huevos de helmintos mostraron una reducción del 100 %. Se concluye que las lagunas tapadas tuvieron un adecuado desempeño en el tratamiento de los residuales porcinos, y que esta tecnología es factible de ser empleada en Cuba.

Fitoplancton y aspectos físicos y químicos de la laguna de Chingaza en Cundinamarca, Colombia Fitoplancton y aspectos físicos y químicos de la laguna de Chingaza en Cundinamarca, Colombia

Directory of Open Access Journals (Sweden)

Donato R. John Charles

1991-12-01

Full Text Available En la laguna de Chingaza (3265 m alt. Cordillera Oriental Colombiana, se realizaron muestreos de fitoplancton, mediciones de temperatura, oxígeno y parámetros físicos y químicos. La comunidad de fitoplancton comprende principalmente Desmidiaceae, Bacillariophyceae, y Cyanophyceae: La Desmidiacea Closterium sp. es la dominante durante la mayor parte del muestreo, pero en octubre (1989 la Cianofícea Oscillatoria sp. es la más significativa. En esta misma época la laguna presenta estratificación térmica y deficiencia de nitrógeno en sus aguas. Debido a los bajos valores en la relación nitrógeno/fósforo, conductividad, sólidos disueltos, acidez y ciertos organismos indicadores la laguna de chingaza es oligotrófica. At the Chingaza pond (3.265 m alt., located on the eastern Colombian cordillera, samples and measurements of temperature, oxygen, and physical-chemical parameters were taken. Phytoplankton community mainly consisted of Desmidiaceae, Bacillariophyceae, and Cyanophceae. Desmidiaceae species dominated in most samples, but in october (1989 Oscillatoria sp. (Cyanophyceae was the most abundant species. During the latter period the laguna exhibited strong thermal stratification and its inorganic nitrogen content was extremely low. It is believed that this is a good example of an oligotrophic pond given the presence of certain bioindicators, the low nitrogen/phosphorus ratio, conductivity, and quantity of suspended solids.

Burrowing Owl - Palo Verde Valley [ds197

Data.gov (United States)

California Natural Resource Agency — These burrowing owl observations were collected during the spring and early summer of 1976 in the Palo Verde Valley, eastern Riverside County, California. This is an...

Low concentrations of persistent organic pollutants (POPs) in air at Cape Verde.

Science.gov (United States)

Nøst, Therese Haugdahl; Halse, Anne Karine; Schlabach, Martin; Bäcklund, Are; Eckhardt, Sabine; Breivik, Knut

2018-01-15

Ambient air is a core medium for monitoring of persistent organic pollutants (POPs) under the Stockholm Convention and is used in studies of global transports of POPs and their atmospheric sources and source regions. Still, data based on active air sampling remain scarce in many regions. The primary objectives of this study were to (i) monitor concentrations of selected POPs in air outside West Africa, and (ii) to evaluate potential atmospheric processes and source regions affecting measured concentrations. For this purpose, an active high-volume air sampler was installed on the Cape Verde Atmospheric Observatory at Cape Verde outside the coast of West Africa. Sampling commenced in May 2012 and 43 samples (24h sampling) were collected until June 2013. The samples were analyzed for selected polychlorinated biphenyls (PCBs), polybrominated diphenyl ethers (PBDEs), hexachlorobenzene (HCB) and chlordanes. The concentrations of these POPs at Cape Verde were generally low and comparable to remote sites in the Arctic for several compounds. Seasonal trends varied between compounds and concentrations exhibited strong temperature dependence for chlordanes. Our results indicate net volatilization from the Atlantic Ocean north of Cape Verde as sources of these POPs. Air mass back trajectories demonstrated that air masses measured at Cape Verde were generally transported from the Atlantic Ocean or the North African continent. Overall, the low concentrations in air at Cape Verde were likely explained by absence of major emissions in areas from which the air masses originated combined with depletion during long-range atmospheric transport due to enhanced degradation under tropical conditions (high temperatures and concentrations of hydroxyl radicals). Copyright © 2017 The Author(s). Published by Elsevier B.V. All rights reserved.

Radiation ecological monitoring in NPP region

International Nuclear Information System (INIS)

Egorov, Yu.A.; Kazakov, S.V.

1985-01-01

The known principle of sanitary-hygienic regulation of NPP radiation effect on man and environment is analyzed. An ecological approach is required to optimize NPP relations with the environment and to regulate radioactivity of the NPP - environment system. The ecological approach envisages the development of standards of permissible concentrations of radioactive and chemical substances (as well as heat) in natural environment, taking into account their synergism, corresponding to ecologically permissible response reactions of biota to their effect. The ecological approach also comprises the sanitary-hygienic principle of radiation protection of man. Attention is paid to ecological monitoring in NPP region, comprising consideration of factors, affecting the environment, evaluation of the actual state of the environment, prediction of the environmental state, evaluation of the expected environmental state

Strategic Analysis for the MER Cape Verde Approach

Science.gov (United States)

Gaines, Daniel; Belluta, Paolo; Herman, Jennifer; Hwang, Pauline; Mukai, Ryan; Porter, Dan; Jones, Byron; Wood, Eric; Grotzinger, John; Edgar, Lauren;

77 FR 14058 - Santa Teresa Southern Railroad, LLC-Operation Exemption-Rail Line of Verde Logistics Railroad...

Science.gov (United States)

2012-03-08

... Southern Railroad, LLC--Operation Exemption--Rail Line of Verde Logistics Railroad, LLC at Santa Teresa... notice of exemption under 49 CFR 1150.31 to operate approximately 12,000 feet of rail line owned by Verde Logistics Railroad, LLC (Verde). The rail line extends between a point of connection with Union Pacific...

Composición por especies y tallas de los peces en la laguna Barra de Navidad, Pacífico central mexicano

Directory of Open Access Journals (Sweden)

Gaspar González-Sansón

2014-03-01

Full Text Available Las lagunas costeras son consideradas áreas de crianza importantes para muchas especies de peces costeros. La laguna costera Barra de Navidad (3.76km² es importante para la economía local y soporta un desarrollo turístico y pesquerías artesanales. Sin embargo, el rol de esta laguna en la dinámica de las poblaciones de peces costeros es poco conocido. Los objetivos de la investigación fueron: caracterizar el agua de la laguna y las condiciones climáticas relacionadas, elaborar el elenco sistemático de la ictiofauna y estimar la proporción de juveniles en el total de individuos capturados de las especies más abundantes. Las operaciones de recolecta de peces se realizaron entre marzo 2011 y febrero 2012. Se utilizaron varios artes de pesca diferentes que incluyeron atarraya, chinchorro playero y redes de agalla con cuatro tamaños de malla diferentes. Se midieron las variables físicas y químicas en épocas de lluvias y de secas. La laguna es euhalina (salinidad 30-40 ups la mayor parte del tiempo, aunque en determinados periodos cortos puede tener características mixopolihalinas (salinidad 18-30 ups. Las concentraciones de clorofila y nutrientes indican que la laguna está eutrofizada. La temperatura media del agua varió estacionalmente de 24.9°C (abril, pleamar a 31.4°C (octubre, bajamar. Se recolectaron en total 36 448 individuos, pertenecientes a 92 especies, de las cuales 31 tienen una relevancia ecológica con base en el número de individuos capturados. Las especies dominantes fueron: Anchoa spp. (44.6%, Diapterus peruvianus (10.5%, Eucinostomus currani (8.1%, Cetengraulis mysticetus (7.8%, Mugil curema (5.2% y Opisthonema libertate (4.5%. La laguna es un hábitat de juveniles importante para 22 de las 31 especies más abundantes. Estas incluyeron algunas especies de importancia comercial como los pargos (Lutjanus argentiventris, L. colorado y L. novemfasciatus, el robalo (Centropomus nigrescens y la lisa (Mugil curema. Otras

Environmental impact of the NPP Krsko

International Nuclear Information System (INIS)

Novosel, N.

1996-01-01

The Ministry of Economic Affairs has for six years now been monitoring the operation of the Krsko NPP (NEK) and its impact on the environment. A bulletin titled 'NEK - Energy and Environment' is being issued every three months. It contains information on operation of the Krsko NPP for the previous three months, a graph of duration of temperature increase of water in the Sava river (delta T) in that period, an assessment of the radiological impact of Krsko NPP on the environment through an equivalent dose cumulatively throughout the calendar year, and a short current text related to Krsko NPP. The Ministry of Economic Affairs organizes a press conference on every issue of the bulletin, as an attempt of introducing this subject to the media and to the public. This paper contains a review of information given in the NEK bulletin from 1990 to 1995 with a special emphasis on the contribution of the Krsko NPP to the artificially caused radiation on the border between the Republic of croatia and the Republic of Slovenia. (author)

NPP Prevlaka - Preparation of construction

International Nuclear Information System (INIS)

Bojic, K.

1984-01-01

On the basis of study 'Optimal electricity generation structure till the year 2000' production of 3 x 500 MWe in nuclear power plants has been anticipated. Second Croatian-Slovenian NPP project will be based on the same principles the first one (NPP Krsko) was based on. Preconstruction investigation studies are performed at site Prevlaka on river Sava downstream of Zagreb. Licensing procedure has started with republic Urban countryside planning activities. Preconstruction activities are planned to be finished by the end of 1986. while the construction is expected to start during 1987. Parallel to investigation studies for NPP Prevlaka, evaluation of nuclear technology and reactor type is planned to be made. (author)

Verde Macael: A Serpentinite Wrongly Referred to as a Marble

OpenAIRE

Navarro, Rafael; Pereira, Dolores; Gimeno, Ana; Barrio, Santiago

2013-01-01

Serpentinites are used in both exterior and interior locations, but not all serpentinites are equal: they vary in physical-mechanical behavior and are not all suitable for similar uses. The serpentinites most commonly used worldwide come from India, Pakistan or Egypt. Spain has traditionally quarried two ultramafic massifs, one in Galicia (Verde Pirineos) and one in Andalucía (Verde Macael). Some of these quarries were small family-run businesses. In both cases, these rocks are commercially a...

Seismic characterization of the NPP Krsko site

International Nuclear Information System (INIS)

Obreza, J.

2000-01-01

The goal of NPP Krsko PSA Project Update was the inclusion of plant changes (i.e. configuration/operational related) through the period January 1, 1993 till the OUTAGE99 (April 1999) into the integrated Internal/External Level 1/Level 2 NPP Krsko PSA RISK SPECTRUM model. NPP Krsko is located on seismotectonic plate. Highest earthquake was recorded in 1917 with magnitude 5.8 at a distance of 7-9 km. Site (founded) on Pliocene sediments which are as deep as several hundred meters. No surface faulting at the Krsko site has been observed and thus it is not to be expected. NPP Krsko is equipped with seismic instrumentation, which allows it to complete OBE (SSE). The seismic PSA successfully showed high seismic margin at Krsko plant. NPP Krsko seismic design is based on US regulations and standards

Analysis of the 3 and 4 cycles with extensions in the operation of the CNLV U-1; Analisis de los ciclos 3 y 4 con extensiones en la operacion de la CNLV U-1

Energy Technology Data Exchange (ETDEWEB)

Montes T, J.L.; Torres A, C.; Perusquia C, R. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1992-08-15

The objective of the report is the comparison of the radial distributions of burned in the core among the results of the simulation of the Laguna Verde Central U-1 reactor during the operation of the cycles 1 to 4 and the data of the operation with information provided by the fuel supplier. (Author)

Analysis of the 3 and 4 cycles with extensions in the operation of the CNLV U-1

International Nuclear Information System (INIS)

Montes T, J.L.; Torres A, C.; Perusquia C, R.

1992-08-01

The objective of the report is the comparison of the radial distributions of burned in the core among the results of the simulation of the Laguna Verde Central U-1 reactor during the operation of the cycles 1 to 4 and the data of the operation with information provided by the fuel supplier. (Author)

Some problems of NPP personnel training

International Nuclear Information System (INIS)

Vajshnis, P.P.; Kumkov, L.P.; Omel'chuk, V.V.

1984-01-01

Shortcomings of NPP personnel training are discussed. Development of full-scale training systems is necessary for qualitative training operative personnel. Primary problems that should be necessarily solved for ensuring effective training NPP personnel are considered

Atmospheric emissions control at ENELVEN`s Ramon Laguna thermal power plant; Control de emisiones a la atmosfera en la central termoelectrica Ramon Laguna de ENELVEN

Energy Technology Data Exchange (ETDEWEB)

Rincon Rincon, Edis Rafael [Empresa de Servicio Electrico (ENELVEN), (Venezuela)

1997-12-31

ENELVEN is an electric utility that covers the areas of generation, transmission and distribution of the Western an South coast of the Maracaibo Lake of the Zulia State, Venezuela. General aspects of the Ramon Laguna of ENELVEN fossil power plant are presented, as well as the environmental measures implanted in this power station to avoid detrimental effects on the environment that could be caused by the emission of combustion products without the appropriate control, such as particulate matter, sulfur oxides, nitrogen oxides and carbon oxides [Espanol] ENELVEN es una empresa de servicio electrico que cubre las areas de generacion, transmision y distribucion de la Costa Occidental y Sur del Lago de Maracaibo, del Estado Zulia, Venezuela. Se presentan aspectos generales de la planta termoelectrica Ramon Laguna de la empresa ENELVEN, asi como las medidas ambientales implantadas en esta central para evitar efectos adversos sobre el ambiente que pudieran producirse por la emision de productos de la combustion si no existiera el debido control, tales como: particulas, oxidos de azufre, oxidos de nitrogeno y oxidos de carbono

Atmospheric emissions control at ENELVEN`s Ramon Laguna thermal power plant; Control de emisiones a la atmosfera en la central termoelectrica Ramon Laguna de ENELVEN

Energy Technology Data Exchange (ETDEWEB)

Rincon Rincon, Edis Rafael [Empresa de Servicio Electrico (ENELVEN), (Venezuela)

1996-12-31

ENELVEN is an electric utility that covers the areas of generation, transmission and distribution of the Western an South coast of the Maracaibo Lake of the Zulia State, Venezuela. General aspects of the Ramon Laguna of ENELVEN fossil power plant are presented, as well as the environmental measures implanted in this power station to avoid detrimental effects on the environment that could be caused by the emission of combustion products without the appropriate control, such as particulate matter, sulfur oxides, nitrogen oxides and carbon oxides [Espanol] ENELVEN es una empresa de servicio electrico que cubre las areas de generacion, transmision y distribucion de la Costa Occidental y Sur del Lago de Maracaibo, del Estado Zulia, Venezuela. Se presentan aspectos generales de la planta termoelectrica Ramon Laguna de la empresa ENELVEN, asi como las medidas ambientales implantadas en esta central para evitar efectos adversos sobre el ambiente que pudieran producirse por la emision de productos de la combustion si no existiera el debido control, tales como: particulas, oxidos de azufre, oxidos de nitrogeno y oxidos de carbono

Statistical analysis of the wind around a nuclear power plant; Analisis estadistico del viento alrededor de una central nucleoelectrica

Energy Technology Data Exchange (ETDEWEB)

Tejeda, A; Alvarez, Oscar; Contreras, A D; Jauregui, E [Universidad Veracruzana, (Mexico)

1997-12-31

In order to show an appropriate methodology for the climatic analysis of the wind, some of the recent results in the investigation of the field flow around the Laguna Verde Nuclear Power Station, at Veracruz State (Mexico,) through the angular correlation coefficients and contingency tables among the registered wind directions by a meteorological tower at the levels of 10 and 60 meters high are presented. Finally, by applying an objective analysis of the data some conclusions are obtained in connection with the local winds with the mesoscale systems. [Espanol] Con el objeto de mostrar una metodologia apropiada en el analisis climatico del viento, se presentan algunos resultados recientes en la investigacion del campo de flujo en los alrededores de la central nucleoelectrica de Laguna Verde, Veracruz (Mexico), a traves de los coeficientes de correlacion angulares y de tablas de contingencia entre las direcciones del viento registradas por una torre meteorologica en los niveles de 10 y 60 metros de altura. Finalmente, aplicando analisis objetivo de los datos, se obtienen algunas conclusiones sobre la conexion de los vientos locales con los sistemas de mesoescala.

Statistical analysis of the wind around a nuclear power plant; Analisis estadistico del viento alrededor de una central nucleoelectrica

Energy Technology Data Exchange (ETDEWEB)

Tejeda, A; Alvarez, Oscar; Contreras, A. D.; Jauregui, E. [Universidad Veracruzana, (Mexico)

1996-12-31

In order to show an appropriate methodology for the climatic analysis of the wind, some of the recent results in the investigation of the field flow around the Laguna Verde Nuclear Power Station, at Veracruz State (Mexico,) through the angular correlation coefficients and contingency tables among the registered wind directions by a meteorological tower at the levels of 10 and 60 meters high are presented. Finally, by applying an objective analysis of the data some conclusions are obtained in connection with the local winds with the mesoscale systems. [Espanol] Con el objeto de mostrar una metodologia apropiada en el analisis climatico del viento, se presentan algunos resultados recientes en la investigacion del campo de flujo en los alrededores de la central nucleoelectrica de Laguna Verde, Veracruz (Mexico), a traves de los coeficientes de correlacion angulares y de tablas de contingencia entre las direcciones del viento registradas por una torre meteorologica en los niveles de 10 y 60 metros de altura. Finalmente, aplicando analisis objetivo de los datos, se obtienen algunas conclusiones sobre la conexion de los vientos locales con los sistemas de mesoescala.

Cape Verde. A Country Guide Series Report from the AACRAO-AID Project.

Science.gov (United States)

Sevigny, Joseph A.

This report provides information on the education system of Cape Verde, and is designed to assist college admissions officers and registrars in the United States with the admission and placement of students from that country. The report contains general information on the geography, history, and people of Cape Verde, as well as more specific…

Calculation and analysis of hydrogen volume concentrations in the vent pipe rigid proposed for NPP-L V; Calculo y analisis de concentraciones volumetricas de hidrogeno en el tubo de venteo rigido propuesto para la CNLV

Energy Technology Data Exchange (ETDEWEB)

Gomez T, A. M.; Xolocostli M, V. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Lopez M, R.; Filio L, C. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico); Royl, P., E-mail: armando.gomez@inin.gob.mx [Karlsruhe Institute of Technology, Hermann-von-Helmholtz-Platz I, D-76344 Eggenstein-Leopoldshafen (Germany)

2014-10-15

In 2012 was modeled of primary and secondary container of the nuclear power plant of Laguna Verde (NPP-L V) for the CFD Gas-Flow code. These models were used to calculate hydrogen volume concentrations run release the reactor building in case of a severe accident. The results showed that the venting would produce detonation conditions in the venting level (level 33) and flammability at ground level of reload. One of the solutions to avoid reaching critical concentrations (flammable or detonable) inside the reactor building and thus safeguard the contentions is to make a rigid venting. The rigid vent is a pipe connected to the primary container could go to the level 33 of the secondary container and style fireplace climb to the top of the reactor building. The analysis of hydrogen transport inside the vent pipe can be influenced by various environmental criteria and factors vent, so a logical consequence of the 2012 analysis is the analysis of the gases transport within said pipe to define vent ideal conditions. For these evaluations the vent pipe was modeled with a fine mesh of 32 radial interior nodes and a coarse mesh of 4 radial interior nodes. With three-dimensional models were realized calculations that allow observing the influence of heat transfer in the long term, i.e. a complete analysis of exhaust (approx. 700 seconds). However, the most interesting results focus on the first milliseconds, when the H{sub 2} coming from the atmosphere of the primary container faces the air in the vent pipe. These first milliseconds besides allowing evaluating the detonation criteria in great detail in the different tubular sections similarly allow evaluating the pressure wave that occurs in the pipe and that at some point slows to the fluid on the last tubular section and could produce a detonation inside the pipe. Results are presented for venting fixed conditions, showing possible detonations into the pipe. (Author)

Fuel leak testing performance at NPP Jaslovske Bohunice

International Nuclear Information System (INIS)

Slugen, V.; Krnac, S.; Smiesko, I.

1995-01-01

The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR's. 1 tab., 2 figs., 3 refs

Fuel leak testing performance at NPP Jaslovske Bohunice

Energy Technology Data Exchange (ETDEWEB)

Slugen, V; Krnac, S [Slovak Technical Univ., Bratislava (Slovakia); Smiesko, I [Nuclear Powr Plant EBO, Jaslovske Bohuce (Slovakia)

1996-12-31

The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR`s. 1 tab., 2 figs., 3 refs.

Preparation for Ignalina NPP decommissioning

International Nuclear Information System (INIS)

Medeliene, D.

2004-01-01

Latest developments of atomic energy in Lithuania, works done to prepare Ignalina NPP for final shutdown and decommissioning are described. Information on decommissioning program for Ignalina NPP unit 1, decommissioning method, stages and funding is presented. Other topics: radiation protection, radioactive waste management and disposal. Key facts related to nuclear energy in Lithuania are listed

GRIP BARBADOS/CAPE VERDE RADIOSONDE V1

Data.gov (United States)

National Aeronautics and Space Administration — The GRIP Barbados/Cape Verde radiosonde data set consists of generally two soundings per day (06Z and 12Z) launched from Barbados, and one sounding per day (12Z)...

Krsko NPP Periodic Safety Review program

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Novsak, M.

2001-01-01

The need for conducting a Periodic Safety Review for the Krsko NPP has been clearly recognized both by the NEK and the regulator (SNSA). The PSR would be highly desirable both in the light of current trends in safety oversight practices and because of many benefits it is capable to provide. On January 11, 2001 the SNSA issued a decision requesting the Krsko NPP to prepare a program and determine a schedule for the implementation of the program for 'Periodic Safety Review of NPP Krsko'. The program, which is required to be in accordance with the IAEA safety philosophy and with the EU practice, was submitted for the approval to the SNSA by the end of March 2001. The paper summarizes Krsko NPP Periodic Safety Review Program [1] including implemented SNSA and IAEA Expert Mission comments.(author)

Living With Parasites in Palo Verde National Park

Directory of Open Access Journals (Sweden)

Eben Kirksey

2012-11-01

Full Text Available Bruno Latour has tried to bring a parliamentary democracy to the domain of nature. Wading through the swamps of Palo Verde, a national park in the Guanacaste Province of Costa Rica, and wandering onto neighbouring agricultural lands, I failed to find a central place where people were speaking for nature. Departing from a failed attempt to speak for another species (the fringe-toed foam frog, this paper considers how diverging values and obligations shape relationships in multi-species worlds. As spokespersons articulated competing visions of nature on the borderlands of Palo Verde, multiple social and ecological worlds went to war. The haunting specter of capital joined the fray—animating the movements of cattle, grasses with animal rhizomes, rice seeds, and flighty ducks across national borders and through fragmented landscapes. Amidst this warfare, the fringe-toed foam frog was just one tenacious parasite, a noisy agent eating at the table of another, which began to flourish in worlds designed with the well-being of others in mind. Cattails, charismatic birds, and a multitude of insects began interrupting human dreams and schemes. Final solutions to the problem of living with parasites failed in Palo Verde. Humans and parasites, who became para-selves of one another, maintained an abiding presence in the landscape.

ESTADO TRÓFICO DE UN LAGO TROPICAL DE ALTA MONTAÑA: CASO LAGUNA DE LA COCHA

Directory of Open Access Journals (Sweden)

Mery Liliana López Martínez

2015-01-01

Full Text Available Este artículo presenta los resultados de una investigación realizada con el fin de determinar el estado trófico de la laguna de La Cocha, cuerpo hídrico importante en Colombia y en el mundo, que hace parte del humedal Ramsar laguna de La Cocha, ecosistema que cumple distintas funciones y alberga una gran biodiversidad que se quiere proteger. Para lograr el propósito planteado, esta investigación se realizó entre enero y septiembre de 2013, determinando el estado trófico mediante los índices de Carlson, el índice desarrollado por la OCDE (Organización para la Cooperación y el Desarrollo Económico y el índice de Carlson modificado por Toledo. Los resultados permitieron clasificar a la laguna de La Cocha como oligotrófica y ultraoligotrófica, característica típica de lagos de alta montaña con bajos procesos de contaminación de origen aloctóno y autóctono.

Financial and organizational models of NPP construction projects

International Nuclear Information System (INIS)

Ivanov, Timur

2010-01-01

The recent evolution of financial and organizational models of NPP projects can be truly reputed to open a new page of the world market of NPP construction. The definition of the concrete model is based mostly on specific cooperation backgrounds and current terms and conditions under which the particular NPP project is being evolved. In this article the most commonly known strategies and schemes of financing structuring for export NPP construction projects are scrutinized. Special attention is paid to the analysis of BOO/BOT models which are based on the public-private partnership. Most BOO/BOT projects in the power sector has Power Purchase Agreements (PPA) as an integral part of them. The PPA key principles are studied here as well. The flexibility and adaptability of the public-private partnership models for financing and organization of the NPP projects contributes substantially to the competitiveness of the NPP projects especially under current economic conditions. (orig.)

External flood probabilistic safety analysis of a coastal NPP

International Nuclear Information System (INIS)

Pisharady, Ajai S.; Chakraborty, M.K.; Acharya, Sourav; Roshan, A.D.; Bishnoi, L.R.

2015-01-01

External events pose a definitive challenge to safety of NPP, solely due to their ability to induce common cause failures. Flooding incidents at Le Blayais NPP, France, Fort Calhoun NPP, USA and Fukushima Daiichi have pointed to the importance of external flooding as an important contributor to NPP risk. A methodology developed for external flood PSA of a coastal NPP vulnerable to flooding due to tsunami, cyclonic storm and intense local precipitation is presented in this paper. Different tasks for EFPSA has been identified along with general approach for completing each task

75 FR 48323 - Agency Information Collection Activities; Proposed Collection; Comment Request; Palos Verdes...

Science.gov (United States)

2010-08-10

..., quantity, and/or cooking method of fish species, (3) gather quantitative data that can be used to... anglers who fish in the Palos Verdes Shelf vicinity. Title: Palos Verdes Shelf Seafood Consumption Survey... deep for direct human contact; however, fish in the PV Shelf area bioaccumulate the contaminants...

Predisposal of Radioactive Waste from NPP 1000 MWe

International Nuclear Information System (INIS)

Suryantoro

2007-01-01

Predisposal of radioactive waste from NPP 1000 MW which was planned to be operated in 2016 has been conducted. In this study NPP applying PWR type was assumed. This assessment comprises all aspects of radioactive waste coming from NPP. One through cycle was chosen consequently no reprocessing step will be conducted. The assessment shows that technologically all radioactive waste treatment process rising from NPP operation has similarities to the existing radioactive waste process conducted by RWI which has lower scale of waste amount. (author)

O chá verde e suas ações como quimioprotetor

Directory of Open Access Journals (Sweden)

Wanderlei Schmitz

2005-12-01

Full Text Available O chá preto é responsável por 75% do chá consumido no mundo e o chá verde, por apenas 22%. O chá que era consumido como medicamento, passou a ser do gosto popular devido as suas característica organolépticas. Seus componentes flavonóides e catequinas apresentam uma série de atividades biológicas, antioxidante, quimioprotetora, antiinflamatória e anticarcinogênica. Vários estudos vêm sendo desenvolvidos por pesquisadores em varias regiões do mundo para comprovar estas atividades terapêuticas, objetivando compreender os mecanismos de ação do chá verde. Diante do acima citado, esta revisão tem por finalidade apresentar as varias linhas de pesquisa em andamento e os resultados já obtidos sobre o efeito quimioprotetor/antioxidante do chá verde.

Atividade das glicosidases na presença de chá verde e de chá preto

OpenAIRE

Pereira,L.L.S.; Souza,S.P.; Silva,M.C; Carvalho,G.A.; Santos,C.D.; Corrêa,A.D.; Abreu,C.M.P.

2010-01-01

Várias plantas têm sido consideradas produtos terapêuticos, dentre elas destacam-se os chás verde e preto, popularmente utilizados para controle da hiperglicemia e obesidade. Objetivou-se neste trabalho avaliar o potencial inibitório sobre as enzimas α-amilase, α e β-glicosidases e o teor de compostos fenólicos do chá verde e do chá preto. O teor de compostos fenólicos encontrados foram de 80,8 ± 0,43 mg g-1 no chá preto e 32,0 ± 0,12 mg g-1 no chá verde. O chá verde e o chá pr...

Operation safety at Ignalina NPP

International Nuclear Information System (INIS)

Zheltobriukh, G.

1999-01-01

An improvement of operational safety at Ignalina NPP covers: improvement of management structure and safety culture; symptom-based emergency operating procedures; staff training and full scope simulator; program of components ageing; metal inspection; improvement of fire safety. The first plan of Ignalina NPP Safety culture development for 1997 purposed to the SAR recommendation implementation was prepared and approved by the General Director

Treatment of NPP wastes using vitrification

International Nuclear Information System (INIS)

Sobolev, I.A.; Lifanov, F.A.; Stefanovsky, S.V.; Kobelev, A.P.; Savkin, A.E.; Kornev, V.I.

1998-01-01

Glass-based materials to immobilize various liquid and solid radioactive wastes generated at nuclear power plants (NPP) were designed. Glassy waste forms can be produced using electric melting including a cold crucible melting. Leach rate of cesium was found to be 10 -5 -10 -6 g/(cm 2 day) (IAEA technique). Volume reduction factor after vitrification reached 4-5. Various technologies for NPP waste vitrification were developed. Direct vitrification means feeding of source waste into the melter with formation of glassy waste form to be disposed. Joule heated ceramic melter, and cold crucible were tested. Process variables at treatment of Kursk, Chernobyl (RBMK), Kalinin, Novovoronezh (VVER) NPP wastes were determined. The most promising melter was found to be the cold crucible. Pilot plant based on the cold crucibles has been designed and constructed. Solid burnable NPP wastes are incinerated and slags are incorporated in glass. (author)

NPP electrical price and tariff in the world

International Nuclear Information System (INIS)

Mochamad Nasrullah and Sriyana

2010-01-01

Construction of a Nuclear Power Plant (NPP) is always become a controversial issue. Nuclear utility and other party which support the NPP present a calculation of NPP electricity cost too optimistic. However for utility and other party that contra to nuclear present a calculation of NPP electricity cost too pessimistic. This study present to reduce the controversy of nuclear cost. In this study, capital cost (Engineering Procurement Construction, EPC) was taken from Asian, America and Europe, operating and maintenance cost uses experience data of PLN, and nuclear fuel cost uses data year of 2008 with high price, low price and average price scenario. The methodological tools used to compare electricity generation cost was LEGECOST, a program developed by IAEA (International Atomic Energy Agency), while for electricity tariff- price calculation using a program developed by PLN research and development center. With the discount rate 10%, the result shows that the cheapest electricity generation cost of NPP is less than 40 mills/kWh, and average electricity tariff was 55 mills/kWh. In the Europe countries the electricity tariff more expensive than NPP in Asia. However generating cost and electricity tariff of NPP in United Stated of America (USA) less competitive because investment cost more expensive. Generating cost and electricity tariff was different at each country depend on salary, labor wage, materials price, construction specification, regulation related to NPP and environment aspect. (author)

Individual protection of NPP personnel

International Nuclear Information System (INIS)

Koshcheev, V.S.; Gol'dshtejn, D.S.; Chetverikova, Z.S.

1983-01-01

Specific features of NPP personnel individual protection are considered, mainly with respect to maintenance and repair works on various type reactors. The major concern is given to the selection and application reglamentations of the individual protection system (IPS), employment of sanitary locks, the organization of individual protection under the conditions of a heating microclimate. The ways are specified to the development and introduction of the most effective IPS and improvement of the entire NPP personnel individual protection system with respect to providing the necessary protection effect for maintaining high working capability of the personnel and minimizing the IPS impact on human organism functional systems. The accumulated experience in the personnel individual protection can be applied during construction and operation of NPP's in CMEA member-countries [ru

Safety culture at Mochovce NPP

International Nuclear Information System (INIS)

Markus, Jozef; Feik, Karol

2002-01-01

This article presents the approach of Mochovce NPP to the Safety culture. It presents activities, which have been taken by Mochovce NPP up to date in the area of Safety culture enhancement with the aim of getting the term into the subconscious of each employee, and thus minimising the human factor impact on occurrence of operational events in all safety areas. The article furthermore presents the most essential information on how the elements characterising a continuous progress in reaching the planned Safety culture goals of the company management have been implemented at Mochovce NPP, as well as the management's efforts to get among the best nuclear power plant operators in this area and to be an example for the others. (author)

Dissemination of Knowledge about NPP Instrumentation and Control Systems

International Nuclear Information System (INIS)

Yastrebenetsky, M.

2016-01-01

Full text: Instrumentation and control (I&C) systems are the most variable part in the nuclear power plants (NPP) comparatively with any other NPP systems. This statement is connected with the wide use of computers, rapid changes in information technologies, with the appearance of new computer complex electronic components, e.g., field programmable gate arrays (FPGA) and with appropriate point of their insertion into NPP I&C life cycle. The changes in NPP I&C systems require the dissemination of the knowledge about these systems. Lessons after Fukushima accident increase necessity of these actions. The elaboration and following dissemination of this knowledge took place in different directions: • Writing and issue of three new books about NPP I&C systems for specialists and for students which were issued in Ukrainian and USA public houses (the last book was issued in 2014); • Organization of five international scientific technical conferences, devoted to NPP I&C safety problems; • Elaboration of national (Ukrainian) standards and regulations pertaining to safety important NPP I&C systems (the last standard was issued in 2015) and participation in elaboration of international standards; • Lecturing for university students, NPP specialists and I&C designers. These actions in all directions are added to IAEA activity in the area NPP I&C systems (e.g., IAEA NP-T-3.12 “Core Knowledge on I&C systems in NPP”). (author

Probabilistic assessment of NPP safety under aircraft impact

International Nuclear Information System (INIS)

Birbraer, A.N.; Roleder, A.J.; Arhipov, S.B.

1999-01-01

Methodology of probabilistic assessment of NPP safety under aircraft impact is described below. The assessment is made taking into account not only the fact of aircraft fall onto the NPP building, but another casual parameters too, namely an aircraft class, velocity and mass, as well as point and angle of its impact with the building structure. This analysis can permit to justify the decrease of the required structure strength and dynamic loads on the NPP equipment. It can also be especially useful when assessing the safety of existing NPP. (author)

Reassessment of the 1892 Laguna Salada Earthquake: Fault Kinematics and Rupture Patterns

Czech Academy of Sciences Publication Activity Database

Rockwell, T.K.; Fletcher, J.M.; Teran, O.J.; Hernandez, A.P.; Mueller, K.J.; Salisbury, J.B.; Akciz, S.O.; Štěpančíková, Petra

2015-01-01

Roč. 105, č. 6 (2015), s. 2885-2893 ISSN 0037-1106 R&D Projects: GA MŠk LH12078 Institutional support: RVO:67985891 Keywords : paleoseismology * earthquake s * fault kinematics * Laguna Salada * Mexico Subject RIV: DB - Geology ; Mineralogy Impact factor: 2.311, year: 2015

NPP Bohunice experience with ASSET services

Energy Technology Data Exchange (ETDEWEB)

Klimo, J [Bohunice NPP (Slovakia)

1997-12-31

The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author).

NPP Bohunice experience with ASSET services

International Nuclear Information System (INIS)

Klimo, J.

1996-01-01

The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author)

Akkuyu NPP – the first Turkish NPP. The new history of the project

International Nuclear Information System (INIS)

Tzocheva, V.

2012-01-01

An overview is given to the Turkish energy sector and nuclear power plans. The project for the construction of the first NPP in Turkey is presented. The general parameters of the Project are: CAPEX: $ 20 bln; Project design: NPP-2006; (VVER- 1200); Number of units: 4; Total capacity: 4 800 MW; Construction period: 2014 – 2023; PPA period; 15 years, fixed price terms. An account of the activities during 2011, the Worley Parsons participation are presented and a tentative project schedule is given

Inspection Qualification Centre in NPP 'Kozloduy'

International Nuclear Information System (INIS)

Mikhovski, M.

2000-01-01

In May 1999 according to the working plan of the IAEA project RER 4/020 and the decision of the NPP the Inspection Qualification Centre (IQC) has been established in order to provide examination services in the NPP. During year 1999 IVC (AEA Technology) in the framework of the DTI project provides consulting and technical assistance to the NPP, IQC, Bulgarian Academy of Sciences and Regulatory Authorities in setting up the IQC infrastructure. Now IQC work as an independent inspection body B type. The IQC activities for the period 1999-2000 are presented and further tasks are outlined

Using NJOY99 and MCNP4B2 to Estimate the Radiation Damage Displacements per Atom per Second in Steel Within the Boiling Water Reactor Core Shroud and Vessel Wall from Reactor-Grade Mixed-Oxide/Uranium Oxide Fuel for the Nuclear Power Plant at Laguna Verde, Veracruz, Mexico

International Nuclear Information System (INIS)

Vickers, Lisa

2003-01-01

The government of Mexico has expressed interest in utilizing the Laguna Verde boiling water reactor (BWR) nuclear power plant for the disposition of reprocessed spent uranium oxide (UOX) fuel in the form of reactor-grade mixed-oxide (MOX) fuel. MOX fuel would replace spent UOX fuel as a fraction in the core from 18 to 30% depending on the fuel loading cycle. MOX fuel is expected to increase the neutron fluence, flux, fuel centerline temperature, reactor core pressure, and yield higher energy neutrons.There is concern that a core with a fraction of MOX fuel (i.e., increased 239 Pu wt%) would increase the radiation damage displacements per atom per second (dpa-s -1 ) in steel within the core shroud and vessel wall as compared to only conventional, enriched UOX fuel in the core. The evaluation of radiation damage within the core shroud and vessel wall is a concern because of the potentially adverse affect to personnel and public safety, environment, and operating life of the reactor.The primary uniqueness of this paper is the computation of radiation damage (dpa-s -1 ) using NJOY99-processed cross sections for steel within the core shroud and vessel wall. Specifically, the unique radiation damage results are several orders of magnitude greater than results of previous works. In addition, the conclusion of this paper was that the addition of the maximum fraction of one-third MOX fuel to the LV1 BWR core did significantly increase the radiation damage in steel within the core shroud and vessel wall such that without mitigation of radiation damage by periodic thermal annealing or reduction in operating parameters such as neutron fluence, core temperature, and pressure, it posed a potentially adverse affect to the personnel and public safety, environment, and operating life of the reactor

76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

Science.gov (United States)

2011-04-29

... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS... Plants: Supplement 43, Regarding Palo Verde Nuclear Generating Station,'' issued January 2011, discusses...

Secuencia didáctica en química verde

OpenAIRE

Cortés Rodríguez, Adriana Janneth

2017-01-01

Esta propuesta presenta los resultados del diseño e implementación de una secuencia didáctica cuya finalidad es adaptar los principios de la Química Verde (QV) en el ámbito escolar, a través de actividades específicas que se enmarcan dentro del diseño del Protocolo Verde o Practica Amigable para el Medio Ambiente. La metodología de investigación – acción desarrollada permitió la reflexión de los estudiantes sobre los principios de la QV en relación con la identificación del cambio de color, e...

Metamorphosis of NPP A1, V1, V2

International Nuclear Information System (INIS)

Dobak, D.; Moncekova, M.

2005-01-01

In this book the history of construction, commissioning and exploitation of NPP A1, NPP V1 and NPP V2 in Jaslovske Bohunice is presented on documentary photos. Vicinity around of these NPPs is presented, too

NPP A-1 decommissioning - Phase I

International Nuclear Information System (INIS)

Krstenik, A.; Blazek, J.

2000-01-01

Nuclear power plant A-1 with output 150 MW e , with metallic natural uranium fuelled, CO 2 cooled and heavy water moderated reactor had been prematurely finally shut down in 1977. It is necessary to mention that neither operator nor regulatory and other authorities have been prepared for the solution of such situation. During next two consecutive years after shutdown main effort of operator focused on technical and administrative activities which are described in the previous paper together with approach, condition and constraints for NPP A-1 decommissioning as well as the work and research carried out up to the development and approval of the Project for NPP A-1 decommissioning - I. phase. Subject of this paper is description of: (1) An approach to NPP A -1 decommissioning; (2) An approach to development of the project for NPP A-1 decommissioning; (3) Project - tasks, scope, objectives; (4) Mode of the Project realisation; (5) Progress achieved up to the 1999 year. (authors)

Monitoring program of surrounding of the NPP SE-EBO

International Nuclear Information System (INIS)

Dobis, L.; Kostial, J.

1997-01-01

The paper dealt with monitoring program of radiation control of surrounding of the NPP Bohunice, which has the aim: (1) to ensure the control of influence of work of the NPP Bohunice on the environment in their surrounding; (2) to ensure the back-ground for regular brief of control and supervisory organs about condition of the environment in surrounding of the NPP Bohunice; (3) to maintain the expected technical level of control of the NPP Bohunice and to exploit optimally the technical means; (4) to solicit permanently the data about the radioactivity of environment in surrounding of the NPP Bohunice for forming of files of the data; (5) to exploit purposefully the technical equipment, technical workers and to maintain their in permanent emergency and technical eligibility for the case of the breakdown; (6) to obtain permanently the files of the values for qualification of the reference levels. This program of monitoring includes the radiation control of surrounding of the NPP Bohunice, in the time of normal work of power-station's blocks, inclusively of all types of trouble-shooting and repairer works in surrounding of the NPP Bohunice, up to distance 20 km from power-station. The monitoring includes: outlets from the NPP Bohunice, monitoring of radiation characteristics in surrounding of the NPP Bohunice, (aerosols, fall-outs, soil), the links of food chains: (grass and fodder, milk, agriculture products), hydrosphere in surrounding (surface waters, drink water, bores of radiation control in complex of the NPP Bohunice, components of the hydrosphere), measurement of radiation from external sources (measurement of the dose rates, measurement of the doses [sk

Effects of past and future groundwater development on the hydrologic system of Verde Valley, Arizona

Science.gov (United States)

Garner, Bradley D.; Pool, D.R.

2013-01-01

Communities in central Arizona’s Verde Valley must manage limited water supplies in the face of rapidly growing populations. Developing groundwater resources to meet human needs has raised questions about the effects of groundwater withdrawals by pumping on the area’s rivers and streams, particularly the Verde River. U.S. Geological Survey hydrologists used a regional groundwater flow model to simulate the effects of groundwater pumping on streamflow in the Verde River. The study found that streamflow in the Verde River between 1910 and 2005 had been reduced as the result of streamflow depletion by groundwater pumping, also known as capture. Additionally, using three hypothetical scenarios for a period from 2005 to 2110, the study’s findings suggest that streamflow reductions will continue and may increase in the future.

Sociological investigations on Ignalina NPP and within its surroundings

International Nuclear Information System (INIS)

Chiuzhas, A.

1998-01-01

The purpose of this study was to determine the impact of Ignalina NPP and Visaginas town on the social territorial processes in the region and to reveal the impact of Ignalina NPP on the regional economic, social, demographic, political and cultural processes in the context of ecological and psychological affect. According to the results of this research three quarters of the inhabitants and the functionaries of local administration hold an opinion that operation of Ignalina NPP posses threat for the population and environment. Meanwhile they are sure that danger of Ignalina NPP is not critical. 21 - 35 % of the local administrators speak for the closure of Ignalina NPP , whereas half of Visaginas residents and three quarters of the local administrators indicate that operation of reactors is expedient. Over 90% of the population do not have sufficient information on the operation of Ignalina NPP. In the opinion of the rest Lithuanian people Ignalina NPP zone is related with the physical danger and the image of Visaginas residents as the 'others', 'strangers'. More than 90% of Ignalina NPP employees are Russian speaking, not native Lithuanians. The social relations of Visaginas with the environment are poor as a result of the situation of the town, lack of communications and cultural self isolation. (author)

Ageing management database development for PWR NPP steam generator

International Nuclear Information System (INIS)

Liu Hongyun; Xu Liangjun; Xiong Changhuai; Wang Xianyuan

2005-01-01

Steam generator (SG) is one of the key safe important equipment of NPP, which is covered by NPP aging management program. Steam Generator Aging Management Dabatase (SGAMDB) is developed to provide necessary information for SG aging management. RINPO is developing SGAMDB for domestic NPP. This system contains information and data about SG design, manufacture, operation and maintenance. The information include NPP fundamental data, SG design data, SG aging mechanism, SG operation data, SG ISI data, SG maintenance data and SG evaluation interface. The system runs at the intranet of Qinshan-1 NPP with B/S mode. It can provide information inquire and fundamental analysis for NPP SG aging team and SG aging researcher's. In addition, it provides necessary information and data for SG aging analysis and evaluation, such as all pressure test process and flaws of tubes, and collects the analysis results. (authors)

Principles of tariff determination for NPP electric power generation

International Nuclear Information System (INIS)

Ratnikov, B.E.; Gitel'man, L.D.; Artemov, Yu.N.; Fiantsev, V.S.

1988-01-01

Foundations of price-setting and order of accounting arrangement for NPP electric power are considered. NPP tariffs are established proceeding from standard costs of power generation. The standards are differentiated as to NPP groups, depending on technical, regional and natural geographic factors, taking into account the facility type, unit capacity and the number of similar NPP units. The conclusion is made that under conditions of NPP economic independence expansion and creation of prerequisites for going over to self-financing principles and also due to the qualitatively new stage of nuclear power generation development the level of efficiency, forseen by the tariffs, should be increased

Scenarios catalog for the graphical console for analysis of severe accidents visualization of OEs, NAEs and calculation of source term of the NPP-LV; Catalogo de escenarios para la consola grafica para analisis de accidentes severos visualizacion de OEs, NAEs y calculo del termino fuente de la CLV

Energy Technology Data Exchange (ETDEWEB)

Sandoval V, S. [Instituto Nacional de Electricidad y Energias Limpias, Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Mendoza R, M. E.; Tijerina S, F.; Garcia C, T., E-mail: manuel.mendoza@cfe.gob.mx [CFE, Central Nucleoelectrica Laguna Verde, Carretera Federal Cardel-Nautla Km 42.5, 91476 Municipio Alto Lucero, Veracruz (Mexico)

2016-09-15

A nuclear power plant is operated at all times within the design criteria of structures, systems and components, and according to the operation technical specifications. For different areas of work of a nuclear power plant is necessary to carry out practices in which is useful to have the prediction of the thermo-hydraulic and radiological progression of scenarios that imply exceeding that design bases, even reaching the damage of the fuel in different degree. During the exercises and drills of the External Plan of Emergency Response, the projection of doses is done to exercise the different tasks of the plan. To make the projection of doses is required to have the radiological source term of the scenario on which is practiced. Because of this, was identified the convenience of having a catalog of scenarios for which the radiological source term was calculated. In 2004, a first version of the catalog was produced for a power of 2027 MW, and in 2011 the catalog was updated for extended power conditions, 2317 MW. Both versions were made using the severe accident simulator MAAP-3B. That catalog consists of a form and an optical storage device. The form contains tables and figures in which the characteristics of the scenario to be practiced are searched and the electronic files of the corresponding radiological source term are located in the storage device. Due to the recent development of the graphical console for analysis of severe accidents, visualization of OEs, NAEs and calculation of the source term for the nuclear power plant of Laguna Verde (NPP-LV) CoGrAAS, the catalog printed was replaced by an electronic catalog for the CoGrAAS. The new catalog retains the philosophy of the previous catalog, constituted by a wide collection of scenarios that involve different circumstances and phenomena, that can be used to practice different tasks during training exercises or simulacrums, and combined with the following advantages: the scenario selection is made from an

Leningrad NPP and energetics of north-western Russia

International Nuclear Information System (INIS)

Belov, I.

2000-01-01

Problems of Leningrad NPP operating units modernization, their design service life finishing by year of 2010, are discussed. To assure safe operation of unit 1 investments in the amount of 30 mln. dol are necessary. Estimations suggest economic efficiency of the measures, permitting saving of 300 mln. dol worth of gas. Unfortunately, without a rise in tariff for electric power produced by NPP it seems impossible. It is recommended that substantiated tariffs are set for electric power produced by NPP starting from January, 2000. The measure is indispensable for raising investment funds intended for operating NPP modernization [ru

Groundwater resources of Mosteiros basin, island of Fogo, Cape Verde, West Africa

Science.gov (United States)

Heilweil, Victor M.; Gingerich, Stephen B.; Plummer, Niel; Verstraeten, Ingrid M.

2010-01-01

Groundwater resources in Cape Verde provide water for agriculture, industry, and human consumption. These resources are limited and susceptible to contamination. Additional groundwater resources are needed for continued agricultural development, particularly during times of drought, but increased use and (or) climatic change may have adverse effects on the quantity and quality of freshwater available. In volcanic island aquifers such as those of Cape Verde, a lens of fresh groundwater typically ?floats? upon a layer of brackish water at the freshwater/saltwater boundary, and increased pumping may cause salt water intrusion or other contamination. A recent U.S. Geological Survey study assessed baseline groundwater conditions in watersheds on three islands of Cape Verde to provide the scientific basis for sustainably developing water resources and minimizing future groundwater depletion and contamination.

Overview of Cernavoda NPP training programme

International Nuclear Information System (INIS)

Valache, Cornelia

2005-01-01

Full text: The paper presents a general assessment of Cernavoda NPP personnel training programme, highlighting the role of training in human performance improvement. Cernavoda NPP Personnel Training and Authorization Department (PTAD) is the one responsible for the training of Unit 1 and 2 staff. PTAD is structured in such a manner as to support and respond to all Cernavoda NPP training, qualification and authorization requirements. The training of personnel is continuously adapted based on IAEA Guides and INPO/WANO recommendations, to keep with world standards, based on the internal and external reviews. At Cernavoda NPP the Training Concept and the Training Programmes are based on SAT - Systematic Approach to Training. The Training Concept is established on a set of training documents (RD's, SI's, IDP's), which address all the SAT phases: Analysis, Design, Development, Implementation and Evaluation. The Training Programmes are structured on the initial and continuing personnel training. Their content and goals respond to the training specific needs for each plant major job family. In order to successfully support NPP training programmes, CNPP training center has upgraded classrooms with new presentation facilities and there are plans to expand the space of the building, to develop additional operator and maintenance skills facilities. There are also a number of general areas for improvement of PTAD activity, such as operators and maintenance training, initial and continuing training of both Unit 1 and 2 staff. By responding in a timely and completely manner to all plant training requirements PTAD will help in rising human performance of Cernavoda NPP personnel, supporting the safe, efficient and cost effective production of power. (author)

Organization of monitoring of agricultural products in NPP region

International Nuclear Information System (INIS)

Panteleev, L.I.; Spirin, E.V.; Sanzharova, N.I.

1990-01-01

Problem of organizing chemical and radiation monitoring of agricultural products in NPP region is considered. Attention is paid to monitoring during NPP siting and designing, to monitoring of radioactive contamination of agricultural products under normal NPP operation, emergency situations and decommissioning

New species of mayflies (Ephemeroptera) from Cape Verde

Czech Academy of Sciences Publication Activity Database

Soldán, Tomáš; Bojková, J.

2015-01-01

Roč. 3926, č. 4 (2015), s. 561-575 ISSN 1175-5326 Institutional support: RVO:60077344 Keywords : Cape Verde * Macaronesia * West Africa Subject RIV: EH - Ecology, Behaviour Impact factor: 0.994, year: 2015

Belene NPP

International Nuclear Information System (INIS)

Tsvetanov, P.

1990-01-01

The book presents the main results of the studies of the Bulgarian Academy of Sciences (BAS) on the construction of a new nuclear power plant at Belene on the Danube river. The programme of the studies comprises five areas: the socio-economic and energy development and the necessity of the commissioning; a technical project and design level of the equipment (safety, radioactivity control, waste disposal and economic efficiency of the power plant); the seismic properties of the construction site; the corresponding risk and design features of the plant; the ecological impacts of the NPP and public opinion. The studies in the different areas have been carried out by independent teams, fully responsible for the formulated topical conclusions. The general opinion of the BAS voiced in the book is that the construction of Belene NPP is not sufficiently substantiated and is considered unacceptable. 94 refs., 53 fig., 56 tabs. (R.Ts.)

Ceratopetalum (Cunoniaceae) fruits of Australasian affinity from the early Eocene Laguna del Hunco flora, Patagonia, Argentina.

Science.gov (United States)

Gandolfo, María A; Hermsen, Elizabeth J

2017-03-01

Radially symmetrical, five-winged fossil fruits from the highly diverse early Eocene Laguna del Hunco flora of Chubut Province, Patagonia, Argentina, are named, described and illustrated. The main goals are to assess the affinities of the fossils and to place them in an evolutionary, palaeoecological and biogeographic context. Specimens of fossil fruits were collected from the Tufolitas Laguna del Hunco. They were prepared, photographed and compared with similar extant and fossil fruits using published literature. Their structure was also evaluated by comparing them with that of modern Ceratopetalum (Cunoniaceae) fruits through examination of herbarium specimens. The Laguna del Hunco fossil fruits share the diagnostic features that characterize modern and fossil Ceratopetalum (symmetry, number of fruit wings, presence of a conspicuous floral nectary and overall venation pattern). The pattern of the minor wing (sepal) veins observed in the Patagonian fossil fruits is different from that of modern and previously described fossil Ceratopetalum fruits; therefore, a new fossil species is recognized. An apomorphy (absence of petals) suggests that the fossils belong within crown-group Ceratopetalum . The Patagonian fossil fruits are the oldest known record for Ceratopetalum . Because the affinities, provenance and age of the fossils are so well established, this new Ceratopetalum fossil species is an excellent candidate for use as a calibration point in divergence dating studies of the family Cunoniaceae. It represents the only record of Ceratopetalum outside Australasia, and further corroborates the biogeographic connection between the Laguna del Hunco flora and ancient and modern floras of the Australasian region. © The Author 2017. Published by Oxford University Press on behalf of the Annals of Botany Company.

Study on human factor at NPP

International Nuclear Information System (INIS)

Nopp, I.

1984-01-01

Factors affecting the reliabilty of the reactor control by an NPP operator are considered on the base of the Czechoslovakia NPP operating experience. The reliability level of NPP operators depends on objective factors (conditions and regime of labour) determining the labour productivity and on subjective ones (psychological morale, physical and mental abilities and occupational level of personnel). Problems of the effect of physical and mental abilities and professional level on the reliability of personnel are considered to be the most important ones. The effect of individual abilities and specific features of the human body on changes in his occupational abilities can be estimated only to a certain degree

Perspectives of NPP personnel training in the future?

International Nuclear Information System (INIS)

Khess, R.E.

1996-01-01

Problems of the NPP personnel education are discussed during radical reorganization of the state regulation of energy production and distribution when nuclear energetics will appears in the market conditions. Effective methods of the NPP personnel training developed by the corporation GPU Nuclear are given. Potentials of the application of simulators and computerized programs for increasing the NPP personnel education efficiency are considered

MORFOMETRÍA, HIDRODINÁMICA Y FÍSICO-QUÍMICA DEL AGUA DE LA LAGUNA DE CHAUTENGO, GUERRERO, MÉXICO

Directory of Open Access Journals (Sweden)

Rendón-Dircio JA

2012-02-01

Full Text Available Se realizó un estudio del comportamiento de las variables morfométricas, batimétricas, hidrodinámicas y físico-químicas de la Laguna de Chautengo, Guerrero, a partir de fotografías aéreas y trabajo de campo con muestreos bimensuales de variables morfométricas, hidrodinámicas y físico-químicas del agua. Los resultados indicaron que la laguna presentó marcadas variaciones anuales en su morfometría y batimetría. El área máxima estimada fue de 29.6 km2. La barra de la laguna es recta y está colonizada en un 36.8 % por comunidades de manglar, tiene una longitud de 10 km y una anchura media de 0.52 km. Las tres islas que presenta la laguna se ubican cerca de la desembocadura y tienen un área de 83,000, 3,680 y 61,440 m2 respectivamente. La variación vertical de la columna de agua fluctuó entre 6 y 12 cm diarios, presentándose el máximo nivel a las 18:00 y 0:00 h y el mínimo a las 6:00 h. Las corrientes presentaron un valor promedio de velocidad de 1.97 m/min. La temperatura media anual fue de 29.8 oC, con una variación entre la superficie y el fondo de 0.23 oC; la salinidad varió de 0.7 a 38 ‰; el oxígeno disuelto se registró en promedio en 4.71 mg/L, existiendo una diferencia del 8.7 % entre la superficie. La laguna presenta características de un cuerpo de agua somero y tropical en un proceso avanzado de evolución, pero con condiciones adecuadas para el desarrollo de la fauna y flora acuática. Este estudio servirá de base para el diseño de un plan de manejo sostenible de las pesquerías y acuicultura de la Laguna de Chautengo.

Integrated ageing management of Atucha NPP

International Nuclear Information System (INIS)

Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos; Sabransky, Mario

2013-01-01

Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

Integrated Ageing Management of Atucha NPP

International Nuclear Information System (INIS)

Ranalli, J.M.; Marchena, M.H.; Zorrilla, J.R.; Sabransky, M.

2012-01-01

Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor twice as big as Atucha I finishing a delayed construction . With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

Integrated ageing management of Atucha NPP

Energy Technology Data Exchange (ETDEWEB)

Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos, E-mail: ranalli@cnea.gov.ar [Gerencia Coordinacion Proyectos CNEA-NASA, Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Sabransky, Mario, E-mail: msabransky@na-sa.com.ar [Departamento Gestion de Envejecimiento, Central Nuclear Atucha I-II Nucleoelectrica Argentina S.A., Provincia de Buenos Aires (Argentina)

2013-07-01

Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

Palo Verde Generating Station, Units 4 and 5. License application, general information

International Nuclear Information System (INIS)

1978-01-01

A license application for two more Palo Verde reactors, Units 4 and 5, is presented. The two PWR reactors have a nominal net generating power each of 1,270 MW(e). Containments are steel-lined prestressed cylindrical structures with hemispherical domes. The reactors are replicas of Palo Verde 1, 2 and 3 (see DOCKETS 50528, 50529 and 50530) using the standard Combustion Engineering System 80 (see DOCKET-STN-50470)

Influencia de la dispersión del flujo en la remoción de coliformes fecales en las lagunas secundarias de estabilización de Masaya

Directory of Open Access Journals (Sweden)

S. Gámez

2006-08-01

Full Text Available Lagunas de estabilización de aguas residuales domésticas en Nicaragua diseñadas para que el efluente no contenga un NMP de CF mayor que el indicado en el Decreto 33-95 “Normativas para el control de la contaminación proveniente de las descargas de aguas residuales domésticas, industriales y agropecuarias” no producen un efluente con esa calidad. Se realizaron estudios, para conocer el por qué de esta situación, en dos lagunas secundarias de estabilización de la ciudad de Masaya. Una laguna cuenta con pantallas deflectoras y por tanto un número de dispersión mucho menor que la segunda. Los resultados son: a La laguna secundaria con pantallas deflectoras produce un efluente con menos variaciones y menor NMPCF/100 ml; b El valor del coeficiente de extinción bacterial es menor que el reportado en la literatura; c No se encontró evidencia que este valor estuviera influido por el número de dispersión de flujo de la laguna.

Chernobyl NPP decommissioning efforts - Past, Present and Future. Decommissioning Efforts on Chernobyl NPP site - Past, Present

International Nuclear Information System (INIS)

Kuchinskiy, V.

2017-01-01

Two unique large-scale projects are underway at the moment within the Chernobyl - Exclusion zone - Shelter object transformation into ecologically safe system and the decommissioning of 3 Chernobyl NPP Units. As a result of beyond design accident in 1986 the entire territory of the industrial site and facilities located on it was heavily contaminated. Priority measures were carried out at the damaged Unit under very difficult conditions to reduce the accident consequences and works to ensure nuclear and radiation safety are continuous, and the Unit four in 1986 was transformed into the Shelter object. Currently, works at the Shelter object are in progress. Under assistance of the International Community new protective construction was built above the existing Shelter object - New Safe Confinement, which will ensure the SO Safety for the long term - within up to 100 years. The second major project is the simultaneous decommissioning of Chernobyl NPP Units 1, 2 and 3. Currently existing Chernobyl NPP decommissioning Strategy has been continuously improved starting from the Concept of 1992. Over the years the following was analyzed and taken into account: the results of numerous research and development works, international experience in decommissioning, IAEA recommendations, comments and suggestions from the governmental and regulatory bodies in the fields of nuclear energy use and radioactive waste management. In 2008 the final decommissioning strategy option for Chernobyl NPP was approved, that was deferred gradual dismantling (SAFSTOR). In accordance with this strategy, decommissioning will be carried out in 3 stages (Final Shutdown and Preservation, Safe Enclosure, Dismantling). The SAFSTOR strategy stipulates: -) the preservation of the reactor, the primary circuit and the reactor compartment equipment; -) the dismantling of the equipment external in relation to the reactor; -) the safe enclosure (under the supervision); -) the gradual dismantling of the primary

Project No. 10 - Partial restoration of Ignalina NPP territory

International Nuclear Information System (INIS)

2000-01-01

At present Ignalina NPP territory makes a total of 2544 ha of land. Due to termination of construction activity development and due to the decision taken to shutdown unit 1 the need in such a territory fell off. For normal and safe operation of Ignalina NPP 1440 ha is enough, including 1237 ha for of Ignalina NPP administrative area and 203 ha for auxiliary objects. Ignalina NPP will have to rearrange territory, forestry that was damaged during the construction activities of the plant and to restore the damaged farmlands and to pass the rearranged forestry that belonged to the Ignalina NPP to the Ministry of Forestry. The total estimated cost of the project is about 1.042 M EURO

Caracterización de la composición y fluctuaciones en la densidad y diversidad de los ensambles planctónicos en cuatro humedales de Tarapacá

Directory of Open Access Journals (Sweden)

Esteban Quinan

2016-12-01

Full Text Available La limnología de los humedales interiores en Tarapacá presenta ciclos productivos altamente dependientes de las lluvias estivales y las condiciones fisicoquímicas del medio. Entre 2013 y 2015 se estudiaron ensambles planctónicos de dos lagunas de evaporación y dos quebradas, durante dos temporadas productivas y dos vegetativas, junto con esto se observaron las condiciones fisicoquímicas asociadas. Los resultados mostraron que el fitoplancton en general estuvo dominado por diatomeas y solo en una quebrada por algas verdes, mientras que el zooplancton presentó composiciones muy distintas entre las lagunas y entre las quebradas, con importantes variaciones temporales. En lagunas las densidades altas de zooplancton asociaron positivamente con sólidos disueltos totales y su diversidad inversamente con la temperatura, por su parte la diversidad de fitoplancton mantuvo una relación inversa con la riqueza de zooplancton.

Cabo Verde telemedicine program: initial results of nationwide implementation.

Science.gov (United States)

Latifi, Rifat; Dasho, Erion; Merrell, Ronald C; Lopes, Miguel; Azevedo, Vanda; Bekteshi, Flamur; Osmani, Kalterina L; Qesteri, Orland; Kucani, Julian; Lecaj, Ismet

2014-11-01

Telemedicine and e-health have been suggested as one solution for closing the health disparity gap between the developed world and the developing world. Yet evidence is lacking from current successful programs in the developing world and, in particular, from sub-Saharan Africa. The primary objective of our study was to present the preliminary results of our efforts in building the Integrated Telemedicine and e-Health Program for Cabo Verde (ITeHP-CV), with an emphasis on initial utilization and results. This is a prospective study of data collected while we worked to establish a fully functional, integrated national telemedicine network and virtual education network in Cabo Verde. We used the International Virtual e-Hospital Foundation strategic approach known as "initiate-build-operate-transfer" over a 26-month period (November 2011-December 2013). We describe herein the five main pillars of this process that have been implemented: (1) capacity building; (2) network development and deployment of equipment; (3) implementation of clinical telemedicine; (4) implementation of activities related to continuing medical education, delivered from within the country and from abroad; and (5) establishment and use of the electronic virtual library. Based on comprehensive technical and medical assessment of the country's needs, 10 fully functional telemedicine centers in all nine inhabited islands of the Republic of Cabo Verde have been established. RESULTS are presented under the five main pillars of capacity building, network deployment, implementation of clinical telemedicine, implementation of continuing medical education activities, and establishment of the electronic virtual library. The ITeHP-CV has been successfully launched, and the initial results are encouraging. The continuity of the program and sustainability are primary goals once the program is transferred fully to the Ministry of Health of Cabo Verde. A long-term follow-up study is required in order to ensure

Main principles of NPP project ecological expert investigation

International Nuclear Information System (INIS)

Dibobes, I.K.; Revina, S.K.; Glushkov, V.P.

1983-01-01

NPP project ecological expert investigation among the other objectives is to provide implementation of standards, rules and requirements as well as government decrees and international obligations of the USSR concerning the environment protection. The expert investigation takes into consideration both environment protection, regional, resources, ecological, demographic and economic aspects. The NPP siting and the local environment and resources state are estimated as well as the structure of utilization of the latter, the expected damage to the environment due to NPP construction and the measures directed towards the optimal using of natural resources. On the basis of the presented issues suggestions about NPP projects coordination with Goskomgidromet's institutions are given [ru

Procedure of generation of the ECP database for Laguna Verde; Procedimiento de generacion de base de datos ECP para Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Perusquia C, R [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1992-09-15

This procedure will be used by the personnel of the Discipline of Nuclear Analysis of the Reactor of CFE to execute PRESTO with the purpose of generating the base for the Estimate of the Position of critical bars during the start up (ECP Database). (Author)

Regulatory approach to NPP ageing in Bulgaria

International Nuclear Information System (INIS)

Vassilev, D.

2000-01-01

In this contribution summary information of Kozloduy NPP units is presented. The nuclear legislation, regulatory approach for managing safety aspects on NPP ageing, short term programme, complex programme PRG'97 ant other aspects of ageing management are discussed

Automatic control system at the ''Loviisa'' NPP

International Nuclear Information System (INIS)

Kukhtevich, I.V.; Mal'tsev, B.K.; Sergievskaya, E.N.

1980-01-01

Automatic control system of the Loviisa-1 NPP (Finland) is described. According to operation conditions of Finland power system the Loviisa-1 NPP must operate in the mode of week and day control of loading schedule and participate in current control of power system frequency and capacity. With provision for these requirements NPP is equipped with the all-regime system for automatic control functioning during reactor start-up, shut-down, in normal and transient regimes and in emergency situations. The automatic control system includes: a data subsystem, an automatic control subsystem, a discrete control subsystem including remote, a subsystem for reactor control and protection and overall station system of protections: control and dosimetry inside the reactor. Structures of a data-computer complex, discrete control subsystems, reactor control and protection systems, neutron flux control system, inside-reactor control system, station protection system and system for control of fuel element tightness are presented in short. Two-year experience of the NPP operation confirmed advisability of the chosen volume of automatization. The Loviisa-1 NPP operates successfully in the mode of the week and day control of supervisor schedule and current control of frequency (short-term control)

Mesa Verde--A Year-Round High School. A Descriptive Report of 1980-81.

Science.gov (United States)

Housden, Terry; Holmes, Lynda

Mesa Verde High School was constructed in 1974 and is the last high school built in the San Juan (California) Unified District. It serves students in grades 9 through 12 and has an open enrollment policy. Mesa Verde operates on a year-round schedule with students divided into three tracks. Basically, each track is in session for 9 weeks and then…

EMAS at Doel NPP

International Nuclear Information System (INIS)

Nolan, Peter; Thoelen, Els

1998-01-01

In October 1995, Doel NPP of Electrabel, Belgium opted to seek registration under the EC Eco-management and Audit Scheme (EMAS). A comprehensive environmental management system (EMS) has been introduced and implemented, encompassing all four PWRs and the supporting departments. A critical step was to seek certification from an accredited environmental auditing body against the International Standard ISO 14001. This provided the foundation for the publicly available environmental statement required by EMAS. The complications of achieving EMAS at a time when national and international standards were being re-formulated were successfully overcome and Doel NPP passed its EMAS audit in June 1997. (author)

Deposition and Accumulation of Emerging Contaminants in the Sediments of the Palos Verde Shelf, California

Science.gov (United States)

Deposition and Accumulation of Emerging Contaminants in the Sediments of the Palos Verde Shelf, California Mark G. Cantwell, David R. Katz, Julia Sullivan, Robert P. Eganhouse, Monique M. Perron, Robert M. Burgess The Palos Verdes shelf is located off the Southern California coa...

On psichological problem of NPP operation and control

International Nuclear Information System (INIS)

Mashin, V.A.

1994-01-01

The role of psichological factor as a reserve for increasing NPP safety connected with human factor is discussed. It is emphasized that the process of NPP personnel professional training should not be restricted by formation of a certain set of knowledge, skills and experience. It is necessary to initiate ability for constant self-developing. Control for assurance of effective interaction of the whole NPP personnel is an important problem

Bohunice V1 NPP upgrading programme

International Nuclear Information System (INIS)

Kerak, J.

2001-01-01

The paper describes whole process of Bohunice V1 NPP nuclear safety and operational reliability level increase which has been performed since units commissioning (1. unit in 1978, 2. unit in 1980), continued Small Reconstruction (1991 -1993) and finished Gradual Upgrading(1994 -2000). The main purpose is to last stage -Gradual upgrading of Bohunice V1 NPP. (author)

Cabo Verde, «Pousada» nos Caminhos do Atlântico. Interinfluências culturais num arquipélago miscigenado / Cape Verde, the «Pousada» of the Atlantico routes - cultural interinfluences in an interbred archipelago

Directory of Open Access Journals (Sweden)

José Silva Évora

2014-12-01

Full Text Available Descoberto entre 1460 e 1462, o Arquipélago de Cabo Verde, situado no Oceano Atlântico, constituiu ao longo de vários séculos, escala obrigatória dos navios que faziam as ligações atlânticas entre os portos das Américas, da Europa e da África Graças a sua situação privilegiada, o espaço cabo-verdiano não foi um mero ponto de reabastecimento, mas também um importante ponto de cruzamento de culturas e de raças. Pretende-se, neste texto, abordar o papel que Cabo Verde teve no Atlântico incidindo, particularmente, na dimensão cultural resultante do contacto entre povos e culturas provenientes de diferentes paragens que se fixaram no arquipélago ou que por aqui passaram. Procurar-se-á evidenciar não só a importância que Cabo Verde teve enquanto ponto de passagem obrigatória mas, sobretudo, as contribuições que mais marcadamente se denunciaram, isto é, os apports culturais que mais se acentuaram em Cabo Verde, como processos recebidos dos estrangeiros que por estas ilhas se cruzaram.The Archipelago of Cape Verde, discovered between 1460 and 1462, and situated in the Atlantic Ocean, had been considered for centuries one of the mandatory harbours of the ships that sailed across the Atlantic to the ports of America, Europe and Africa. Because of its strategic location, Cape Verdean anchorage was considered not only the supplying point, but also an important melting pot of races and cultures. It is intended to highlight the role of Cape Verde in the Atlantic focusing particularly on the cultural aspect, as a result of the influence of cultures and origins of people who had settled in or had passed by the archipelago. It is also aimed to underline the importance of Cape Verde as a mandatory gateway but, above all, to underline the remarkable contributions, such as the cultural “apports” by which Cape Verde were gripped, like processes brought by the foreigners who crossed these islands.

Chemometric characterization of alembic and industrial sugar cane spirits from cape verde and ceará, Brazil.

Science.gov (United States)

Pereira, Regina F R; Vidal, Carla B; de Lima, Ari C A; Melo, Diego Q; Dantas, Allan N S; Lopes, Gisele S; do Nascimento, Ronaldo F; Gomes, Clerton L; da Silva, Maria Nataniela

2012-01-01

Sugar cane spirits are some of the most popular alcoholic beverages consumed in Cape Verde. The sugar cane spirit industry in Cape Verde is based mainly on archaic practices that operate without supervision and without efficient control of the production process. The objective of this work was to evaluate samples of industrial and alembic sugar cane spirits from Cape Verde and Ceará, Brazil using principal component analysis. Thirty-two samples of spirits were analyzed, twenty from regions of the islands of Cape Verde and twelve from Ceará, Brazil. Of the samples obtained from Ceará, Brazil seven are alembic and five are industrial spirits. The components analyzed in these studies included the following: volatile organic compounds (n-propanol, isobutanol, isoamylic, higher alcohols, alcoholic grade, acetaldehyde, acetic acid, acetate); copper; and sulfates.

Verde urbano e processi ambientali: per una progettazione di paesaggio multifunzionale

Directory of Open Access Journals (Sweden)

Raffaele Pelorosso

2013-04-01

Full Text Available L’impermeabilizzazione delle superfici determina un’alterazione del sistema idrologico, con un incremento dei volumi e dei picchi dei deflussi delle acque meteoriche. Il fenomeno è destinato a progredire, sia per il contributo che vi deriva dalla costante crescita delle superfici urbanizzate (urban sprawl, sia per i cambiamenti climatici in atto, che accentuano la frequenza delle piogge critiche. Una serie di misure e tecniche (Best Management Practices, BMPs sono state sviluppate per la gestione sostenibile delle acque meteoriche urbane. Alcune  BMPs (es: verde pensile, bacini di detenzione/ritenzione, zone umide possono svolgere inoltre una funzione ecologica (divenendo habitat per specie animali e vegetali, di termoregolazione, estetica e di promozione del capitale sociale. È quindi necessario sperimentare metodologie di progettazione e gestione del verde urbano e periurbano, la cui multifunzionalità consente di perseguire la strada della sostenibilità ambientale. Su tale traccia, questo lavoro presenta un percorso metodologico orientato a valutare alcune strategie integrate di controllo dei deflussi urbani, attraverso l’aumento della permeabilità di alcune parti sensibili di città. Il verde, quindi, non è visto come semplice infrastruttura necessaria a soddisfare generici standard urbanistici, ma ne sono analizzate le funzionalità, in questa prima fase di carattere idrologico, ma che, in prospettiva, con la stessa armatura verde, esso può assumere un ruolo ecologico, sociale, di mitigazione del clima e di emissione di gas clima-alteranti.

Psychology of NPP operation safety

International Nuclear Information System (INIS)

Tret'yakov, V.P.

1993-01-01

The book is devoted to psychologic investigations into different aspects of NPP operative personnel activities. The whole set of conditions on which successful and accident-free personnel operation depends, is analysed. Based on original engineering and socio-psychologic investigations complex psychologic support for NPP personnel and a system of training and upkeep of operative personnel skills are developed. The methods proposed have undergone a practical examination and proved their efficiency. 154 refs., 12 figs., 9 tabs

Regulatory aspects of NPP safety

International Nuclear Information System (INIS)

Kastchiev, G.

1999-01-01

Extensive review of the NPP Safety is presented including tasks of Ministry of Health, Ministry of Internal Affairs, Ministry of Environment and Waters, Ministry of Defense in the field of national system for monitoring the nuclear power. In the frame of national nuclear safety legislation Bulgaria is in the process of approximation of the national legislation to that of EC. Detailed analysis of the status of regulatory body, its functions, organisation structure, responsibilities and future tasks is included. Basis for establishing the system of regulatory inspections and safety enforcement as well as intensification of inspections is described. Assessment of safety modifications is concerned with complex program for reconstruction of Units 1-4 of Kozloduy NPP, as well as for modernisation of Units 5 and 6. Qualification and licensing of the NPP personnel, Year 2000 problem, priorities and the need of international assistance are mentioned

From the chronicle of training of Dukovany NPP staff

International Nuclear Information System (INIS)

2005-01-01

The long way the Dukovany NPP had to go before the plant staff was fully qualified and skilled is described. First the training concept was prepared, then the necessary training facilities were set up, lecturers and instructors were hired and trained, training programmes and training materials were developed, and ultimately the first training course was launched in 1979. A training NPP was constructed and a full-scope simulator of the Dukovany NPP was set up. The current status of organization of NPP staff training by the CEZ utility is highlighted. (author)

Training center of Rovenskaya NPP. The experience of creation

International Nuclear Information System (INIS)

Fedorov, O.M.; Aristov, B.N.

1991-01-01

Experience in creation of a teaching-training centre at the Rovno NPP, which uses means available at unified NPPs, at most is discussed. The centre hardware complex functions include the event filing and providing for user-friendly interface with NPP technical personnel under training. The system of personnel training at the Rovno NPP teaching-training centre gives an opportunity to analyze accidents and emergency conditions more completely and carefully. The taching analysis of failures and accidents by a NPP operators using the complex of the teaching-training centre hardware sufficiently improves knowledge of particular accidents

Waterbirds and human-related threats to their conservation in Laguna Cuyutlán, Colima, México

Directory of Open Access Journals (Sweden)

Eric Mellink

2009-06-01

Full Text Available Laguna Cuyutlán, the only large wetland in a span of 1 150 km along the Pacific coast of México, has been neglected as to its importance for waterbird conservation. At least 25 waterbird species nest there, with some of their colonies being very relevant, and at least 61 waterbird species use the lagoon during their nonbreeding season. This lagoon has been subject to several structural modifications, including levees and artificial channels which connect it to the sea, while water supply from continental sources has diminished, although its role has not been assessed yet. Salt extraction and artisanal fishery, the main economic activities, do not seem to pose a threat to waterbirds. Among potential threats to this acquatic ecosystem, are the raw sewage discharges that exist near urban areas, and pesticides from the surrounding agricultural lands might reach the lagoon. Seemingly, the most serious threat comes from waterway development in connection with a re-gasification plant to be built, and planned future port expansion, which could potentially increase water levels and alter important habitats for nesting and foraging. We recommend that: the area be declared an Important Bird Area; the development of the re-gasification plant and future port includes a levee to prevent alterations in water level in the remaining sections of the lagoon; supply of exogenous chemicals and waste products be prevented and monitored; alleged benefits from water interchange between the lagoon and the sea through artificial channels should be re-evaluated; and the role of fresh water supplies to the lagoon should be paid attention to. Rev. Biol. Trop. 57 (1-2: 1-12. Epub 2009 June 30.Laguna Cuyutlán, el único humedal grande a lo largo de 1 150 km del Pacífico mexicano, no ha sido considerado un ecosistema natural importante para la conservación de aves acuáticas. Cuando menos 25 especies de aves acuáticas anidan ahí, y al menos 61 especies de aves acu

Correlation and Fishers’ Perception in Selected Sites in Laguna de Bay, Luzon Island, Philippines

Directory of Open Access Journals (Sweden)

Arthur J. Lagbas

2017-01-01

Full Text Available White goby (Glossogobius giuris Hamilton 1822 is an omnivorous, native fish species which can be found in Laguna de Bay and its tributaries, and in other bodies of water in the Philippines. Deteriorating water quality, unsustainable fishing practices, aquaculture and predation by introduced invasive species are threatening the population of white goby and other native fish species in Laguna de Bay. This study was conducted to correlate select physico-chemical parameters of lake water and zooplankton abundance, and to assess white goby population based on fishers’ perception. Water samples were collected in three sites in June, September and December 2014. Twenty one zooplankton species belonging to 12 families were identified. The most abundant and frequently encountered zooplankton species is Eurytemora affinis Poppe 1880. Zooplanktons were most abundant in June and lowest in September. Key informant interviews with local fishers revealed that white goby population was abundant in April to August while catch report showed that fish catch is abundant in June and least during December. The fish abundance in April to June could be attributed to high productivity especially in summer season. The fishers perceived that the population of white goby was declining mainly due to water pollution, aquaculture, and predation by invasive alien species. A multi-stakeholder sustainable watershed management should be adapted to improve the water quality and extinction of native fish species in Laguna de Bay.

Observation and modeling of NPP for Pinus elliottii plantation in subtropical China