WorldWideScience

Sample records for central reactor analisis

  1. 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

  2. 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

  3. ANALISIS TRANSIEN PADA PASSIVE COMPACT MOLTEN SALT REACTOR (PCMSR

    Directory of Open Access Journals (Sweden)

    M. Makrus Imron

    2015-04-01

    Full Text Available Penggunaan bahan bakar cair berupa garam LiF-BeF2-ThF4-UF4 pada Passive Compact Molten Salt Reactor (PCMSR meyebabkan pengendalian daya pada PCMSR dapat dilakukan dengan mengendalikan laju aliran bahan bakar dan pendingin. Sedangkan dari sistem keselamatan, penggunaan bahan bakar cair menjadikan PCMSR memiliki karakter keselamatan melekat (inherent safety yang baik. Pada penelitian ini telah dilakukan analisis transien PCMSR pada tiga kondisi, yaitu: ketika terjadi perubahan laju aliran bahan bakar, ketika terjadi perubahan laju aliran pendingin dan ketika terdapat kegagalan pada sistem pelepasan panas (loss of heat sink. Penelitian dilakukan dengan memodelkan reaktor pada kondisi tunak menggunakan paket program. Standart Reactor Analysis Code (SRAC. Selanjutnya dari keluaran paket program SRAC diperoleh data data yang meliputi fluks netron,konstanta grup, kontanta peluran prekusor netron, fraksi netron kasip untuk perhitungan transien. Penelitian ini menunjukkan bahwa penurunan laju aliran bahan bakar sebesar 50 % dari laju bahan bakar sebelumnya, menyebabkan daya pada PCMSR turun menjadi 78 % dari daya sebelumnya. Dan penurunan laju aliran pendingin sebesar 50 % dari laju pendingin sebelumnya, menyebabkan daya pada PCMSR turun menjadi 63 % dari daya sebelumnya. Sedangkan pada saat terjadi loss of heat sink daya PCMSR menunjukkan penurunan. Kata kunci: PCMSR, transien, daya, laju aliran.   The use of liquid fuels in the form of molten salts LiF-BeF2-ThF4-UF4 in Passive Compact Molten Salt Reactor (PCMSR makes power control at PCMSR can be done by controlling the flow rate of fuel and coolant. In addition, from safety systems aspect, the use of liquid fuels makes PCMSR has good inherent safety characteristics. In this study transient analysis has been carried out on three conditions of PCMSR, namely when the fuel flow rate is changing, when the coolant flow rate is changing and when there is loss of heat sink condition. This research is

  4. Analisis de la microbiota en suelos cultivados del Altiplano central

    OpenAIRE

    Sivila, R.; Hervé, Dominique

    2001-01-01

    Se estudio la poblacion microbina en una rotacion de cultivos con descanso, comun en el Altiplano Central boliviano. Se determino la presencia y densidad de cuatro grupos taxonomicos de microorganismos: bacterias; hongos, actinomicetos y esporas de las micorrizas arbusculares en el suelo rizosferico de cuatro cultivos de la rotacion (papa, quinua, cebada y avena); en las principales especies silvestres perennes (#Stipa ichu, Festuca dolichophylla, Baccharis incarum$) que colonizan las parcela...

  5. Transient Analysis of Generation IV quick reactors; Analisis de Transitorios en Reactores Rapidos de Generacion IV

    Energy Technology Data Exchange (ETDEWEB)

    Vazquez, M.; Martin-Fuertes, F.

    2013-07-01

    As a complement to the attached code 3D neutron-CIEMAT thermohydraulic added a module to simulate transient. Temporary kinetics is resolved by factoring flow in a spatial part and another storm. MCNP provides the reactivity and updated spatial function and COBRA-IV calculates the temperature distribution. Temporary dependence of amplitude is calculated using time delayed neutron Kinetic equations. As an example of application, examines a transient loss of flow in MYRRHA, a lead-cooled experimental reactor.

  6. 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)

  7. 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)

  8. 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.

  9. 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.

  10. THERMOS, district central heating nuclear reactors

    International Nuclear Information System (INIS)

    Patarin, L.

    1981-02-01

    In order to expand the penetration of uranium in the national energy balance sheet, the C.E.A. has been studying nuclear reactors for several years now, that are capable of providing heat at favourable economic conditions. In this paper the THERMOS model is introduced. After showing the attraction of direct town heating by nuclear energy, the author describes the THERMOS project, defines the potential market, notably in France, and applies the lay-out study to the Grenoble Nuclear Study Centre site with district communal heating in mind. The economic aspects of the scheme are briefly mentioned [fr

  11. Neutron analysis of the fuel of high temperature nuclear reactors; Analisis neutronico del combustible de reactores nucleares de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2014-10-15

    In this work a neutron analysis of the fuel of some high temperature nuclear reactors is presented, studying its main features, besides some alternatives of compound fuel by uranium and plutonium, and of coolant: sodium and helium. For this study was necessary the use of a code able to carry out a reliable calculation of the main parameters of the fuel. The use of the Monte Carlo method was convenient to simulate the neutrons transport in the reactor core, which is the base of the Serpent code, with which the calculations will be made for the analysis. (Author)

  12. Centralized digital computer control of a research nuclear reactor

    International Nuclear Information System (INIS)

    Crawford, K.C.

    1987-01-01

    A hardware and software design for the centralized control of a research nuclear reactor by a digital computer are presented, as well as an investigation of automatic-feedback control. Current reactor-control philosophies including redundancy, inherent safety in failure, and conservative-yet-operational scram initiation were used as the bases of the design. The control philosophies were applied to the power-monitoring system, the fuel-temperature monitoring system, the area-radiation monitoring system, and the overall system interaction. Unlike the single-function analog computers currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control-rod movements to conform with operator requests, automatically log the required physical parameters during reactor operation, perform the required system tests, and monitor facility safety and security. Reactor power control is based on signals received from ion chambers located near the reactor core. Absorber-rod movements are made to control the rate of power increase or decrease during power changes and to control the power level during steady-state operation. Additionally, the system incorporates a rudimentary level of artificial intelligence

  13. Analysis of pumping systems to large flows of cooling water in power plants; Analisis de sistemas de bombeo para grandes flujos de agua de enfriamiento en centrales termoelectricas

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez Sanchez, Ramon; Herrera Velarde, Jose Ramon; Gonzalez Sanchez, Angel [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)]. E-mail: rsanchez@iie.org.mx; jrhv@iie.org.mx; ags@iie.org.mx

    2010-11-15

    Accurate measurement of large water flows remains being a challenge in the problems of implementation of circulating water systems of power plants and other applications. This paper, presents a methodology for the analysis in pumping systems with high rates of water in power plants, as well as their practical application and results in pipelines water flow of a thermoelectrical power plant of 350 MW. In this power plant, the water flow per pipeline for a half of condenser oscillates around 7 m{sup 3}/s (14 m{sup 3}/s per power generating unit). In this analysis, we present the techniques used to measure large flows of water with high accurately, as well as the computational model for water circulating system using PIPE FLO and the results of practical application techniques. [Spanish] La medicion precisa de grandes flujos de agua, sigue siendo un reto en los problemas de aplicacion de sistemas de agua de circulacion de centrales termoelectricas, entre otras aplicaciones. En este articulo, se presenta una metodologia para el analisis de sistemas de bombeo con grandes flujos de agua en centrales termoelectricas, asi como, su aplicacion practica y los resultados obtenidos en los ductos de agua de circulacion de una central generadora con unidades de 350 MW. En esta central, los flujos por caja de agua oscilan alrededor de los 7 m{sup 3}/s (14 m{sup 3}/s por unidad generadora). En el analisis, se presentan las tecnicas utilizadas para medir con precision grandes flujos de agua (tubo de Pitot), asi como, el modelado del sistema de agua de circulacion por medio de un paquete computacional (PIPE FLO) y resultados obtenidos de la aplicacion de dichas tecnicas.

  14. Comparative analysis of power conversion cycles optimized for fast reactors of generation IV; Analisis comparativo de ciclos de conversion de potencia optimizados para reactores rapidos de generacion IV

    Energy Technology Data Exchange (ETDEWEB)

    Perez Pichel, G. D.

    2011-07-01

    For the study, which is presented here, has been chosen as the specific parameters of each reactor, which are today the three largest projects within generation IV technology development: ESFR for the reactor's sodium, LEADER for the lead reactor's and finally, GoFastR in the case of reactor gas-cooled.

  15. AZTLAN platform: Mexican platform for analysis and design of nuclear reactors; AZTLAN platform: plataforma mexicana para el analisis y diseno de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Edif. 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Francois L, J. L.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco No. 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)

    2014-10-15

    The Aztlan platform Project is a national initiative led by the Instituto Nacional de Investigaciones Nucleares (ININ) which brings together the main public houses of higher studies in Mexico, such as: Instituto Politecnico Nacional, Universidad Nacional Autonoma de Mexico and Universidad Autonoma Metropolitana in an effort to take a significant step toward the calculation autonomy and analysis that seeks to place Mexico in the medium term in a competitive international level on software issues for analysis of nuclear reactors. This project aims to modernize, improve and integrate the neutron, thermal-hydraulic and thermo-mechanical codes, developed in Mexican institutions, within an integrated platform, developed and maintained by Mexican experts to benefit from the same institutions. This project is financed by the mixed fund SENER-CONACYT of Energy Sustain ability, and aims to strengthen substantially to research institutions, such as educational institutions contributing to the formation of highly qualified human resources in the area of analysis and design of nuclear reactors. As innovative part the project includes the creation of a user group, made up of members of the project institutions as well as the Comision Nacional de Seguridad Nuclear y Salvaguardias, Central Nucleoelectrica de Laguna Verde (CNLV), Secretaria de Energia (Mexico) and Karlsruhe Institute of Technology (Germany) among others. This user group will be responsible for using the software and provide feedback to the development equipment in order that progress meets the needs of the regulator and industry; in this case the CNLV. Finally, in order to bridge the gap between similar developments globally, they will make use of the latest super computing technology to speed up calculation times. This work intends to present to national nuclear community the project, so a description of the proposed methodology is given, as well as the goals and objectives to be pursued for the development of the

  16. 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

  17. The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

    2001-07-01

    Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

  18. Neutronics and thermohydraulics of the reactor C.E.N.E.-Part I; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte I

    Energy Technology Data Exchange (ETDEWEB)

    Caro, R; Ahnert, C; Naudin, A E; Martinez Fanegas, R; Minguez, E; Rovira, A

    1976-07-01

    In this report the analysis of neutronics (both statics and kinetics), of the 10 MWt swimming pool reactor C.E.N.E, is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking, carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

  19. Neutronics and thermohydraulics of the reactor C.E.N.E. Part II; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte II

    Energy Technology Data Exchange (ETDEWEB)

    Caro, R

    1976-07-01

    In this report the analysis of neutronics thermohydraulics and shielding of the 10 HWt swimming pool reactor C.E.N.E is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

  20. Analisi matematica

    CERN Document Server

    Canuto, Claudio

    2014-01-01

    Il presente testo intende essere di supporto ad un secondo insegnamento di Analisi Matematica in quei corsi di studio (quali ad esempio Ingegneria, Informatica, Fisica) in cui lo strumento matematico parte significativa della formazione dell'allievo. I concetti e i metodi fondamentali del calcolo differenziale ed integrale in più variabili, le serie di funzioni e le equazioni differenziali ordinarie sono presentati con l'obiettivo primario di addestrare lo studente ad un loro uso operativo, ma critico. L'impostazione didattica dell'opera ricalca quella usata nel testo parallelo di Analisi Matematica I. La modalità di presentazione degli argomenti ne permette un uso flessibile e modulare. Lo stile adottato privilegia la chiarezza e la linearità dell'esposizione. Il testo organizzato su due livelli di lettura. Uno, più essenziale, permette allo studente di cogliere i concetti indispensabili della materia, di familiarizzarsi con le relative tecniche di calcolo e di trovare le giustificazioni dei principali r...

  1. Development of a methodology of analysis of instabilities in BWR reactors; Desarrollo de una metodologia de analisis de inestabilidades en reactores PWR

    Energy Technology Data Exchange (ETDEWEB)

    Garcia-Fenoll, M.; Abarca, A.; Barrachina, T.; Miro, R.; Verdu, G.

    2012-07-01

    This paper presents a methodology of analysis of the reactors instabilities of BWR type. This methodology covers of modal analysis of the point operation techniques of signal analysis and simulation of transients, through 3D Coupled RELAP5/PARCSv2.7 code.

  2. Fuel burn analysis of a sodium fast reactor with KANEXT and Serpent; Analisis de quemado de combustible de un reactor rapido de sodio con KANEXT y SERPENT

    Energy Technology Data Exchange (ETDEWEB)

    Lopez S, R. C.; Francois L, J. L., E-mail: rcarlos.lope@gmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2015-09-15

    The fast reactors cooled by sodium are one of the options considered in the Generation IV. Since most of the reactors of Fourth Generation are still in development stage, is necessary to have efficient and reliable computational tools, this in order to obtain accurate results in reasonable computational times. In this paper is introduced and describes the deterministic code KANEXT (KArlsruhe Neutronic EXtended Tool) and is compared against a Monte Carlo code of more diffusion: Serpent. KANEXT, being a modular code requires the interaction of different modules to perform a job, this interaction of modules is described in this article. The parameters to be compared are the results of the neutron multiplication effective factor and the evolution of isotopes during the burning. The mentioned comparison is carried out for a fast reactor cooled by sodium of relatively small size compared to commercial size reactors. In this paper the particularities of the reactor are described, important for the analysis such as geometry, enrichments, reflector, etc. The considerations in the implementation in both codes are also described, as are simplifications, length of the burning steps, possible solutions of the Bateman equations for the burning fuel in Serpent and the solution options for transport (P3) and diffusion (P1) in KANEXT. The results show good correspondence between Serpent and KANEXT, which give confidence to continue using KANEXT as the main tool. Respect to computation time, time saving is evident with the use of deterministic codes instead of Monte Carlo codes, in this particular case, the time savings using KANEXT is about 98.5% of the time used by Serpent. (Author)

  3. Analysis and application of a simulator of a nuclear reactor AP-600; Analisis y aplicacion de un simulador de un reactor nuclear AP-600

    Energy Technology Data Exchange (ETDEWEB)

    Medina S, V. S. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Salazar S, E., E-mail: medina_victor@comunidad.unam.mx [UNAM, Facultad de Ingenieria, Division de Ingenieria Electrica, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (MX)

    2011-11-15

    In front of the resurgence of interest in the nuclear power production, several national organizations have considered convenient to have highly specialized human resources in the technologies of nuclear reactors of III + and IV generation. For this task, the intensive and extensive applications of the computation should been considered, as the virtual instrumentation. The present work analyzes the possible applications of a nuclear simulator provided by the IAEA with base in the design of the reactor AP-600, using a focusing of modular model developed in FORTRAN. One part of the work that was made with the simulator includes the evaluation of 21 transitory events of operation, including the recreation of the accident happened in the nuclear power plant of Three Mile Island in 1979, comparing the actions flow and the answer of the systems under the intrinsic security of a III + generation reactor. The impact that had the mentioned accident was analyzed in the growing of the nuclear energy sector and in the public image with regard to the nuclear power plants. An application for this simulator was proposed, its use as tool for the instruction in the nuclear engineering courses using it to observe the operation of the different security systems and its interrelation inside the power plant as well as a theoretical/practical approach for the student. (Author)

  4. Statistical analysis about corrosion in nuclear power plants; Analisis estadistico de la corrosion en centrales nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

    Nowadays, it has been carried out the investigations related with the structure degradation mechanisms, systems or and components in the nuclear power plants, since a lot of the involved processes are the responsible of the reliability of these ones, of the integrity of their components, of the safety aspects and others. This work presents the statistics of the studies related with materials corrosion in its wide variety and specific mechanisms. These exist at world level in the PWR, BWR, and WWER reactors, analysing the AIRS (Advanced Incident Reporting System) during the period between 1993-1998 in the two first plants in during the period between 1982-1995 for the WWER. The factors identification allows characterize them as those which apply, they are what have happen by the presence of some corrosion mechanism. Those which not apply, these are due to incidental by natural factors, mechanical failures and human errors. Finally, the total number of cases analysed, they correspond to the total cases which apply and not apply. (Author)

  5. ANALISIS TOTAL PRODUCTIVE MAINTENANCE PADA LINE 8/CARBONATED SOFT DRINK PT COCA-COLA BOTTLING INDONESIA CENTRAL JAVA

    Directory of Open Access Journals (Sweden)

    Darminto Pujotomo

    2012-02-01

    Full Text Available PT. Coca-Cola Bottling Indonesia (CCBI Central Java merupakan salah satu perusahaan produsen minuman ringan yang terkemuka di Indonesia, dengan dua jenis kelompok produk yang dihasilkan yaitu minuman karbonasi/Carbonated Soft Drink (Coca-Cola, Sprite, dan Fanta dan non-karbonasi (Frestea dan Ades. Dalam usaha untuk mempertahankan mutu dan meningkatkan produktifitas, salah satu faktor yang harus diperhatikan adalah masalah perawatan fasilitas/mesin produksi.  Makalah ini membahas mengenai penyebab dan akibat yang ditimbulkan oleh breakdown mesin terjadi pada Line 8/Carbonated Soft Drink, khususnya pada conveyor, filler machine, dan bottle washer machine. Untuk mendapatkan mesin yang dapat terjaga keterandalannya dibutuhkan suatu konsep yang baik. Total Productive Maintenance (TPM merupakan sebuah konsep yang baik untuk merealisasikan hal tersebut. Konsep ini, selain melibatkan semua personil dalam perusahaan, juga bertujuan untuk merawat semua fasilitas produksi yang dimiliki perusahaan.Data yang digunakan merupakan data breakdown conveyor, filler machine, dan bottle washer machine dari ME Monthly Report PT.CCBI selama bulan Januari-Desember 2005 khususnya line 8. Selain itu makalah ini juga membahas performance maintenance PT. Coca-Cola Bottling Indonesia-Central Java, dengan memperhitungkan nilai Mean Time Beetwen Failure (MTBF, Mean Time To Repair (MTTR, serta Availability mesin, dengan menggunakan data record Line 8 selama bulan Mei 2006 sampai bulan Juli 2006. Sehingga nantinya akan diketahui informasi keadaan aktual dari perusahaan tentang sistem perawatannya, khususnya pada Line 8/Carbonated Soft Drink apakah baik atau buruk. Kata kunci : Total Production Maintenance, Conveyor, Filler Machine, Bottle Washer Machine, Performance Maintenance   PT. Coca-Cola Bottling Indonesia (CCBI-Central Java represent one of notable light beverage producer company in Indonesia, with two product group type yielded is carbonated beverage/Carbonated Soft

  6. Hydraulic analysis of emergency core cooling system of reactor RP-10; Analisis hidraulico del sistema de refrigeracion de emergencia del nucleo del reactor RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo Padilla, Alberto; Moreyra, Geraldo Lazaro; Nieto Malpartida, Manuel [Instituto Peruano de Energia Nuclear, Lima (Peru)]. E-mail: agallardo@ipen.gob.pe; glazaro@ipen.gob.pe; mnieto@ipen.gob.pe

    2002-07-01

    For design of the Emergency Core Cooling System (ECCS) of reactor RP-10 from Peru is very important the hydraulic analysis of this system. In this paper, based on a basic design of the ECCS are showed the conservation equations, the parabolic movement, being deduced from them the equations to evaluate regarding the time the variables to consider in the design: level of the emergency water in the reserve tank, flow, reaches of sprinkle, etc. In this analysis is considered a quasi-stationary flow for simplify the calculation. The developed model was implemented in a computer program denominated ECCSRP10, in language Fortran 77, whose results are shown in form graph. From analysis of results we can conclude that for the system of pipe of the ECCS the appropriate diameter is of 2 in., and that the maximum flow possible to give is of 5 m{sup 3}/h for to assure a minimum time of refrigeration of 150000 seconds. Experimental tests were made in a prototype of the pipe system being demonstrated that the obtained results of the simplified calculation agree with the values registered with a global approach of 10%. (author)

  7. Analisis Kinerja Keuangan Bank Sebelum Dan Sesudah Diakuisisi Oleh Investor Asing: Studi Empiris Pada Bank Central Asia Dan Bank Niaga

    Directory of Open Access Journals (Sweden)

    Yen Sun

    2011-11-01

    Full Text Available Banking industry is one of the most influence factors in the economy growth of one country. However, during 1997-1998 Indonesia banking industry went through hard times because of economic crisis. After that years, many banks were liquidated and restructured. The interesting part is through the restructuring process, several bank acquired by foreign investor and became the foreign-domestic bank. In 2010, some of those banks were in the 10 biggest banks in Indonesia based on asset. Hence, the writer interesting to compare the bank’s financial performance before and after being acquired using two banks as samples of empirical study. Data is based on financial statements published by the companies and Central Bank of Indonesia in 1995-1996, and 2003-2004. Two sample of banks have been selected based on several criteria, they are BCA and Bank Niaga. To analyse their financial performance, several analysis tools will be using, specifically CAMELS (CAR, NPL, NIM, BOPO, LDR minus mangement and sensitivity. The result of the study observed that after being acquired, financial performance of BCA and Niaga Bank is getting better in CAR, NIM, BOPO, but NPL and LDR is less favorable for BCA and so NPL is less favorable for Niaga Bank. Moreover, in terms of profitability analysis, both banks shows better performance. While, the result of credit analysis indicates that the credit risk for both banks is in the stable range at CCC.

  8. Maintainability considerations for the central cell in WITAMIR-I, a conceptual design of a tandem mirror fusion power reactor

    International Nuclear Information System (INIS)

    Sviatoslavsky, I.N.

    1980-10-01

    The concepts for maintaining the central cell reactor components for WITAMIR-I are described. WITAMIR-I is a conceptual tandem mirror fusion power reactor utilizing thermal barriers designed by the University of Wisconsin-Madison. Unique solutions to the difficult problems of routine blanket replacement and maintenance are proposed. Solutions are also proposed for maintaining the central cell coils and the shield

  9. Development of a central PC-based system for reactor signal monitoring and analysis

    International Nuclear Information System (INIS)

    Karim, A.; Ansari, S.A.; Rauf Baig, A.

    1998-01-01

    A personal computer based system was developed for on-line monitoring, signal processing and display of important reactor parameters of the Pakistan Research Reactor-1. The system was designed for assistance to both reactor operator and users. It performs three main functions. The first is the centralized radiation monitoring in and around the reactor building. The computer acquires signals from radiation monitoring channels and continuously displays them on distributed monitors. Trend monitoring and alarm generation is also done. In case of any abnormal condition the radiation level data is automatically stored in computer memory for detailed off-line analysis. In the second part the computer does the performance testing of nuclear instrumentation channels by signal statistical analysis, and generates alarm in case the channel standard deviation error exceeds the permissible error. Mean values of important nuclear signals are also displayed on distributed monitors as a part of reactor safety parameters display system. The third function is on-line computation of reactor physics parameters of the core which are important from operational and safety points-of-view. The signals from radiation protection system and nuclear instrumentation channels in the reactor were interfaced with the computer for this purpose. The development work was done under an IAEA research contract as a part of coordinated research programme. (author)

  10. Physical start up of the Dalat nuclear research reactor with the core configuration having a central neutron trap

    International Nuclear Information System (INIS)

    Pham Duy Hien; Ngo Quang Huy; Vu Hai Long; Tran Khanh Mai

    1994-01-01

    After the reactor has reached physical criticality with the core configuration exempt from central neutron trap on 1 November 1983, the core configuration with a central neutron trap has been arranged in the reactor and the reactor has reached physical criticality with this core configuration at 17h48 on 18 December 1983. The integral worths of different control rods are determined with accuracy. 2 refs., 24 figs., 18 tabs

  11. Household appliance data collection and market survey in central and eastern european countries; Raccolta dati e analisi del mercato sugli apparecchi elettrodomestici nei paesi dell'Europa centrale e orientale

    Energy Technology Data Exchange (ETDEWEB)

    Presutto, M. [ENEA, Funzione Centrali Studi, Centro Ricerche Ispra, Vercelli (Italy); Ricci, A. [Istituto di Studi per l' Integrazione dei Sistemi, Rome (Italy); Meli, L. [ANIE, Federazione delle Imprese Elettrotecniche ed Elettroniche, International Affaires Direction, Milan (Italy)

    2001-07-01

    Since 1995 the European Commission, through the SAVE programme, and the Economic Commission for Europe of the United Nations, through the Energy Efficiency 2000 Project, jointly sponsored the so called SACHA projects in Central and Eastern European Countries regarding major household appliances. Consistently, the main objective of the projects was to analyse and interpret the situation of refrigerators, freezers and washing machines in seven CEEC, so as to increase the knowledge and understanding of the issues at stake in the area of energy efficiency and environmental friendliness, and therefore to identify possible scenarios of improvement. This paper describes the work accomplished and the results achieved in this context, focusing more on the data collection and market survey moments and illustrates, with an abundant series of exhibits, the quantitative picture resulting form the analyses carried out. Possibility exists for replication in Latin America, where ENEA and Italian experience could be fruitfully applied. Reliable and complete information is in fact one of the prerequisites to overcome potential barriers and facilitate a successful enforcement of any energy efficiency policy. Effective implementation and regional harmonisation are necessary, even if projects can facilitate the fulfilment of these goals as it provides a consolidated methodology and an integrated scheme for basic data collection and analysis. [Italian] A partire dal 1995 la Commissione Europea e la Commissione Economica per l'Europa delle Nazioni Unite hanno congiuntamente promosso lo studio dei piu' importanti apparecchi domestici nei paesi dell'Europa centrale ed orientale. Principale obiettivo di questi progetti, piu' noti come progetti con SACHA, dall'acronimo del titolo, era analizzare e soprattutto interpretare la situazione dei frigoriferi, congelatori e lavatrici in sette PECO, per migliorare da un lato la conoscenza e la comprensione delle problematiche

  12. Thermal analysis of the heat recuperator of a combined cycle thermoelectric central; Analisis termico del recuperador de calor de una central termoelectrica de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Romero Paredes, Hernando; Sanchez, I; Lazcano, L C; Ambriz, Juan Jose; Alvarez, M [Universidad Autonoma Metropolitana-Iztapalapa, Mexico, D. F. (Mexico); Gonzalez, O [Comision Federal de Electricidad, Tula (Mexico)

    1997-12-31

    The thermoelectric centrals of the combined cycle type (Brayton Cycle and Rankine Cycle) present a series of opportunities to increase the efficiency of the combined cycle or of the generated power. This paper shows the methodology for the performance of energy balances in a heat recuperator (H. R.), typically employed in the combined cycle stations operating in Mexico, for the assessment of the energy harnessing in the different sections conforming a H. R. The effect of the installation of evaporative coolers and/or an absorption cooling system at the gas turbine compressor intake on the steam generation in the heat recuperator, is evaluated. This extra generation of steam is quantified for its potential use in the same absorption refrigeration system. From the assessment, it follows up that the steam generation in the H.R. is inversely proportional to the ambient temperature and that, although the increased amount of steam generated can not be harnessed in total by the steam turbine, the remaining fraction is good enough to cover the heat demand for the operation of the refrigeration system. [Espanol] Las centrales termoelectricas del tipo ciclo combinado (ciclo Brayton y ciclo Rankine) presentan un conjunto de oportunidades para incrementar la eficiencia del ciclo combinado o bien la potencia generada. En el presente trabajo se expone la metodologia para realizar los balances de energia en un recuperador de calor (R.C.) tipicamente utilizado en las Centrales de Ciclo Combinado (CCC) que operan en Mexico, para evaluar el aprovechamiento de la energia en las diferentes secciones que conforman un R.C. Se evalua el efecto que tiene la instalacion de enfriadores evaporativos y/o un sistema de enfriamiento por absorcion en la succion del compresor de la turbina de gas sobre la generacion de vapor en el recuperador de calor. Se cuantifica esta generacion extra de vapor para su posible utilizacion en el mismo sistema de refrigeracion por absorcion. De la evaluacion se

  13. Thermal analysis of the heat recuperator of a combined cycle thermoelectric central; Analisis termico del recuperador de calor de una central termoelectrica de ciclo combinado

    Energy Technology Data Exchange (ETDEWEB)

    Romero Paredes, Hernando; Sanchez, I.; Lazcano, L. C.; Ambriz, Juan Jose; Alvarez, M. [Universidad Autonoma Metropolitana-Iztapalapa, Mexico, D. F. (Mexico); Gonzalez, O. [Comision Federal de Electricidad, Tula (Mexico)

    1996-12-31

    The thermoelectric centrals of the combined cycle type (Brayton Cycle and Rankine Cycle) present a series of opportunities to increase the efficiency of the combined cycle or of the generated power. This paper shows the methodology for the performance of energy balances in a heat recuperator (H. R.), typically employed in the combined cycle stations operating in Mexico, for the assessment of the energy harnessing in the different sections conforming a H. R. The effect of the installation of evaporative coolers and/or an absorption cooling system at the gas turbine compressor intake on the steam generation in the heat recuperator, is evaluated. This extra generation of steam is quantified for its potential use in the same absorption refrigeration system. From the assessment, it follows up that the steam generation in the H.R. is inversely proportional to the ambient temperature and that, although the increased amount of steam generated can not be harnessed in total by the steam turbine, the remaining fraction is good enough to cover the heat demand for the operation of the refrigeration system. [Espanol] Las centrales termoelectricas del tipo ciclo combinado (ciclo Brayton y ciclo Rankine) presentan un conjunto de oportunidades para incrementar la eficiencia del ciclo combinado o bien la potencia generada. En el presente trabajo se expone la metodologia para realizar los balances de energia en un recuperador de calor (R.C.) tipicamente utilizado en las Centrales de Ciclo Combinado (CCC) que operan en Mexico, para evaluar el aprovechamiento de la energia en las diferentes secciones que conforman un R.C. Se evalua el efecto que tiene la instalacion de enfriadores evaporativos y/o un sistema de enfriamiento por absorcion en la succion del compresor de la turbina de gas sobre la generacion de vapor en el recuperador de calor. Se cuantifica esta generacion extra de vapor para su posible utilizacion en el mismo sistema de refrigeracion por absorcion. De la evaluacion se

  14. Analisis Statistika dengan SPSS

    OpenAIRE

    Mustari, Kahar

    2012-01-01

    Buku ini membahas tentang berbagai model analisis statistika yang dapat digunakan dalam berbagai bidang penelitian. Pembahasan buku ini dilengkapi pula dengan penerapan analisis statistika yang menggunakan program SPSS versi 20 sehingga memudahkan pembaca untuk menerapkannya. Oleh karena itu, buku ini penting dibaca oleh mahasiswa atau peneliti yang melakukan pengolahan data penelitian.

  15. Development of a central PC-based system for reactor signal monitoring and analysis

    International Nuclear Information System (INIS)

    Karim, A.; Ansari, S.A.; Baig, A.R.

    1996-05-01

    A personal computer based system was developed for on-line monitoring, signal processing and display of important parameters of the Pakistan Reactor-1. The system was designed for assistance to both reactor operator and users. It performs three main functions. The first is the centralized radiation monitoring in and around the reactor building. The computer acquires signals from radiation monitoring channels and continuously displays them on distributed monitors. Trend monitoring and alarm generation is also done. In case of any abnormal condition the radiation level data is automatically stored in computer memory for detailed off-line analysis. In the second part the computer does the performance testing of nuclear instrumentation channels by signal statistical analysis and generates alarm in case the channel standard deviation error exceeds the permissible error. Mean values of important nuclear signals are also displayed on distributed monitors as a part of reactor safety parameters display system. The third function is on-line computation of reactor physics parameters of the core which are important from operational and safety point-of-view. The signals from radiation protection system and nuclear instrumentation channels in the reactor were interfaced with the computer for this purpose. The development work was done under an IAEA research contract as a part of coordinated research programme. (author) 12 figs

  16. ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI

    Directory of Open Access Journals (Sweden)

    Azizul Khakim

    2015-10-01

    Full Text Available ABSTRAK ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI. Bulk shielding merupakan fasilitas yang terintegrasi dengan reaktor Kartini yang berfungsi sebagai penyimpanan sementara bahan bakar bekas. Fasilitas ini merupakan fasilitas yang termasuk dalam struktur, sistem dan komponen (SSK yang penting bagi keselamatan. Salah satu fungsi keselamatan dari sistem penanganan dan penyimpanan bahan bakar adalah mencegah kecelakaan kekritisan yang tak terkendali dan membatasi naiknya temperatur bahan bakar. Analisis keselamatan paling kurang harus mencakup analisis keselamatan dari sisi neutronik dan termo hidrolik Bulk shielding. Analisis termo hidrolik ditujukan untuk memastikan perpindahan panas dan proses pendinginan bahan bakar bekas berjalan baik dan tidak terjadi akumulasi panas yang mengancam integritas bahan bakar. Code tervalidasi PARET/ANL digunakan untuk analisis pendinginan dengan mode konveksi alam. Hasil perhitungan menunjukkan bahwa mode pendinginan konvekasi alam cukup memadai dalam mendinginkan panas sisa tanpa mengakibatkan kenaikan temperatur bahan bakar yang signifikan. Kata kunci: Bulk shielding, bahan bakar bekas, konveksi alam, PARET.   ABSTRACT THERMAL HYDRAULIC SAFETY ANALYSIS OF BULK SHIELDING KARTINI REACTOR. Bulk shielding is an integrated facility to Kartini reactor which is used for temporary spent fuels storage. The facility is one of the structures, systems and components (SSCs important to safety. Among the safety functions of fuel handling and storage are to prevent any uncontrolable criticality accidents and to limit the fuel temperature increase. Safety analyses should, at least, cover neutronic and thermal hydraulic calculations of the bulk shielding. Thermal hydraulic analyses were intended to ensure that heat removal and the process of the spent fuels cooling takes place adequately and no heat accumulation that challenges the fuel integrity. Validated code, PARET/ANL was used for analysing the

  17. 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)

  18. Flow of ideal fluid through a central region of a nuclear reactor wire-spaced fuel subassembly

    International Nuclear Information System (INIS)

    Schmid, J.

    1991-04-01

    The results are given of calculations of the flow of an ideal fluid through the central region of a nuclear reactor wire-spaced fuel subassembly. The computer code used is briefly described. (author). 10 figs., 4 refs

  19. Experimental facilities for PEC reactor design central channel test loop: CPC-1 - thermal shocks loop: CEDI

    International Nuclear Information System (INIS)

    Calvaresi, C.; Moreschi, L.F.

    1983-01-01

    PEC (Prova Elementi di Combustibile: Fuel Elements Test) is an experimental fast sodium-cooled reactor with a power of 120 MWt. This reactor aims at studying the behaviour of fuel elements under thermal and neutron conditions comparable with those existing in fast power nuclear facilities. Given the particular structure of the core, the complex operations to be performed in the transfer cell and the strict operating conditions of the central channel, two experimental facilities, CPC-1 and CEDI, have been designed as a support to the construction of the reactor. CPC-1 is a 1:1 scale model of the channel, transfer-cell and loop unit of the channel, whereas CEDI is a sodium-cooled loop which enables to carry out tests of isothermal endurance and thermal shocks on the group of seven forced elements, by simulating the thermo-hydraulic and mechanical conditions existing in the reactor. In this paper some experimental test are briefy discussed and some facilities are listed, both for the CPC-1 and for the CEDI. (Auth.)

  20. Reference equilibrium core with central flux irradiation facility for Pakistan research reactor-1

    International Nuclear Information System (INIS)

    Israr, M.; Shami, Qamar-ud-din; Pervez, S.

    1997-11-01

    In order to assess various core parameters a reference equilibrium core with Low Enriched Uranium (LEU) fuel for Pakistan Research Reactor (PARR-1) was assembled. Due to increased volume of reference core, the average neutron flux reduced as compared to the first higher power operation. To get a higher neutron flux an irradiation facility was created in centre of the reference equilibrium core where the advantage of the neutron flux peaking was taken. Various low power experiments were performed in order to evaluate control rods worth and neutron flux mapping inside the core. The neutron flux inside the central irradiation facility almost doubled. With this arrangement reactor operation time was cut down from 72 hours to 48 hours for the production of the required specific radioactivity. (author)

  1. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  2. Split core experiments; Part I. Axial neutron flux distribution measurements in the reactor core with a central horizontal reflector

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P; Raisic, N; Obradovic, D; Jovanovic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-05-01

    A series of critical experiments were performed on the RB reactor in order to determine the thermal neutron flux increase in the central horizontal reflector formed by a split reactor core. The objectives of these experiments were to study the possibilities of improving the thermal neutron flux characteristics of the neutron beam in the horizontal beam tube of the RA research reactor. The construction of RA reactor enables to split the core in two, to form a central horizontal reflector in front of the beam tube. This is achieved by replacing 2% enriched uranium slugs in the fuel channel by dummy aluminium slugs. The purpose of the first series of experiments was to study the gain in thermal neutron component inside the horizontal reflector and the loss of reactivity as a function of the lattice pitch and central reflector thickness.

  3. 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)

  4. The approximate thermal-model-testing method for non-stationary temperature fields in central zones of fast reactor assemblies

    International Nuclear Information System (INIS)

    Mikhin, V.I.; Matukhin, N.M.

    2000-01-01

    The approach to generalization of the non-stationary heat exchange data for the central zones of the nuclear reactor fuel assemblies and the approximate thermal-model-testing criteria are proposed. The fuel assemblies of fast and water-cooled reactors with different fuel compositions have been investigated. The reason of the non-stationary heat exchange is the fuel-energy-release time dependence. (author)

  5. Gas dynamics in the central cavity of HYLIFE-II reactor

    International Nuclear Information System (INIS)

    Chen, X.M.; Schrock, V.E.; Peterson, P.F.; Colella, P.

    1992-01-01

    In a HYLIFE-II ICF reactor, the microfusion of the D-T capsule in the center of the chamber produces X-rays that can ablate a thin layer off the liquid blanket which protects the first structural wall Thisablated material will implode toward the center line of the central cavity due to the initial vacuum and cylindrical geometry, and then rebound back to the liquid blanket vent through it and exert a pressure ''impulse'' onto the structural wall. The initial ablation occurs in a very short period with very small characteristic length and the implosion and rebounding processes feature very high pressures and temperatures. The proper design of the chamber relies on the reasonably accurate analysis of the gas dynamics in the central cavity and the gas-liquid interaction. In this paper, a second order Godunov numerical method is used to solve the compressible flow equations in the central cavity. The rarefaction and shock phenomena are very well captured by the numerical calculation. The equation of state for Flibe vapor is used in the calculation along with the parameters for the HYLIFE-II design. Since the radiation transport has not yet been included in the current calculations, the vapor possesses higher energy and therefore temperature. The total mass vaporized will also be underestimated in the later time of the calculation. The incorporation of a radiation calculation into this code is our next goal

  6. Review of operational experience with the gas-cooled Magnox reactors of the United Kingdom Central Electricity Generating Board

    International Nuclear Information System (INIS)

    Cave, L.; Clarke, A.W.

    1984-01-01

    The paper provides a review, which is mainly of a statistical nature, of 260 reactor years of operating experience which the (United Kingdom) Central Electricity Generating Board (CEGB) has obtained with its gas-cooled, graphite moderated Magnox reactors. The main emphasis in the review is on safety rather than on availability. Data are provided on the overall incidence and frequencies of faults and it is shown that the plant items which are predominantly responsible for recorded faults are the gas circulators and the turbo-alternators. Analysis of the reactor trip experience shows that the incidence of events which necessitate an automatic shutdown of the reactor has been about one per reactor year and that of other events leading to a reactor trip has not been much higher (1.4 per reactor year). As would be expected from the length of the operating experience, some relatively rare events have occurred (expected frequency 10 -2 per reactor year, or less) but on each occasion the reactor shutdown system and decay heat removal systems functioned satisfactorily. No overheating of, or damage to, the fuel occurred as a result of these rare events or of other, more frequent, faults. Analysis of the trend of failure rates has shown an improvement with time in nearly all safety-related items and external inspection of the primary coolant circuits has shown no significant deterioration with time. However, some derating of the reactors has been necessary to reduce the effects of oxidation of mild steel in CO 2 , in order to obtain optimum service lives. In spite of major differences between the systems, a comparison of the failure rates of analogous systems and plant items in PWRs and the Magnox reactors show a considerable similarity. Overall, the review of CEGB's operational experience with its Magnos reactors has shown that the frequencies of faults in systems and plant items has been satisfyingly low. (author)

  7. Centralized Reliability Data Organization (CREDO) assessment of critical component unavailability in liquid metal reactors

    International Nuclear Information System (INIS)

    Koger, K.H.; Haire, M.J.; Humphrys, B.L.; Manneschmidt, J.F.; Setoguchi, K.; Nakai, R.

    1988-01-01

    The Centralized Reliability Data Organization (CREDO) is the largest repository of liquid metal reactor (LMR) component reliability data in the world. It is jointly sponsored by the US Dept. of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The CREDO data base contains information on a population of more than 20,000 components and approximately 1500 event records. A conservative estimation is that the total component operating hours is approaching 2.2 billion hours. The work reported here focuses on the availability information contained in CREDO and the development of availability critical items lists. That is, individual components are ranked in prioritized lists from worst to best performers from an availability standpoint. Availability as used here is an inherent characteristics of the component and is not necessarily related to plant operability. A major observation is that a few components have a much higher unavailability factor than the average. The top fifteen components contribute 93%, 77%, and 87% of the total system unavailability for EBR-II, FFTF, and JOYO respectively. Critical components common to all three sites are mechanical pumps and electromagnetic pumps. Application of resources to these components with the highest unavailability will have the greatest effect on overall availability. All three sites demonstrate that low maintainability (i.e., long repair times), rather than unreliability (i.e., high failure rates), are the main contributors, by about a two-to-one margin, to liquid metal system unavailability

  8. Neutron Environment Characterization of the Central Cavity in the Annular Core Research Reactor *

    Directory of Open Access Journals (Sweden)

    Parma Edward J.

    2016-01-01

    Full Text Available Characterization of the neutron environment in the central cavity of the Sandia National Laboratories' Annular Core Research Reactor (ACRR is important in order to provide experimenters with the most accurate spectral information and maintain a high degree of fidelity in performing reactor experiments. Characterization includes both modeling and experimental efforts. Building accurate neutronic models of the ACRR and the central cavity “bucket” environments that can be used by experimenters is important in planning and designing experiments, as well as assessing the experimental results and quantifying uncertainties. Neutron fluence characterizations of two bucket environments, LB44 and PLG, are presented. These two environments are used frequently and represent two extremes in the neutron spectrum. The LB44 bucket is designed to remove the thermal component of the neutron spectrum and significantly attenuate the gamma-ray fluence. The PLG bucket is designed to enhance the thermal component of the neutron spectrum and attenuate the gamma-ray fluence. The neutron characterization for each bucket was performed by irradiating 20 different activation foil types, some of which were cadmium covered, resulting in 37 different reactions at the peak axial flux location in each bucket. The dosimetry results were used in the LSL-M2 spectrum adjustment code with a 640-energy group MCNP-generated trial spectrum, self-shielding correction factors, the SNLRML or IRDFF dosimetry cross-section library, trial spectrum uncertainty, and trial covariance matrix, to generate a least-squares adjusted neutron spectrum, spectrum uncertainty, and covariance matrix. Both environment character-izations are well documented and the environments are available for use by experimenters.

  9. Genusa Bepu methodologies for the safety analysis of BWRs; Metodologias Bepu de Genusa para el analisis de seguridad de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Trueba, M.; Garcia, J.; Goodson, C.; Ibarra, L.

    2016-08-01

    This article describes the BEPU methodologies developed by General Electric-Hitachi (GEH) for the evaluation of the BWR reactor safety analysis based on the TRACG best-estimate code. These methodologies are applicable to a wide range of events, operational transients (AOO), anticipated transients without scram (ATWS), loss of coolant accidents (LOCA) and instability events; to different BWR types operating commercially. General Electric (GE( designs and other vendors, including Generation III+ESBWR; to the new operation strategies, and to all types of BWR fuel. Their application achieves, among other benefits, a better understanding of the overall plant response and an improvement in margins to the operating limits; thus, the increase of flexibility in reactor operation and reduction in generation costs. (Author)

  10. Adoption of in-vessel retention concept for VVER-440/V213 reactors in Central European Countries

    Energy Technology Data Exchange (ETDEWEB)

    Matejovic, Peter, E-mail: peter.matejovic@ivstt.sk [Inzinierska Vypoctova Spolocnost (IVS), Jana Holleho 5, 91701 Trnava (Slovakia); Barnak, Miroslav; Bachraty, Milan; Vranka, Lubomir [Inzinierska Vypoctova Spolocnost (IVS), Jana Holleho 5, 91701 Trnava (Slovakia); Berky, Robert [Integrita a Bezpecnost Ocelovych Konstrukcii, Rybnicna 40, 831 07 Bratislava (Slovakia)

    2017-04-01

    Highlights: • Design of in-vessel retention concept for VVER-440/V213 reactors. • Thermal loads acting on the inner reactor surface. • Structural response of reactor pressure vessel. • External reactor vessel cooling. - Abstract: An in-vessel retention (IVR) concept was proposed for standard VVER-440/V213 reactors equipped with confinement made of reinforced concrete and bubbler condenser pressure suppression system. This IVR concept is based on simple modifications of existing plant technology and thus it was attractive for plant operators in Central European Countries. Contrary to the solution that was adopted before at Loviisa NPP in Finland (two units of VVER-440/V213 reactor with steel confinement equipped with ice condenser), the coolant access to the reactor pressure vessel from flooded cavity is enabled via closable hole installed in the centre of thermal shield of the reactor lower head instead of lowering this massive structure in the case of severe accident. As a consequence, the crucial point of this IVR concept is narrow gap between torispherical lower head and thermal and biological shield. Here the highest thermal flux is expected in the case of severe accident. Thus, realistic estimation of thermal load and corresponding deformations of reactor wall and their impact on gap width for coolant flow are of primarily importance. In this contribution the attention is paid especially to the analytical support with emphasis to the following points: 1) {sup ∗}Estimation of thermal loads acting on the inner reactor surface; 2) {sup ∗}Estimation of structural response of reactor pressure vessel (RPV) with emphasis on the deformation of outer reactor surface and its impact on the annular gap between RPV wall and thermal/biological shield; 3) {sup ∗}Analysis of external reactor vessel cooling. For this purpose the ASTEC code was used for performing analysis of core degradation scenarios, the ANSYS code for structural analysis of reactor vessel

  11. Analisis Cadangan Devisa Indonesia

    Directory of Open Access Journals (Sweden)

    Lusia Bunga Uli

    2016-09-01

    Full Text Available Abstract This study aims to determine the relationship between variables export, import, and exchange rate against Foreign Exchange Reserves in Indonesia. The data used in the empirical study of a sequence of data monthly time of year 2011.01 through 2014.12 from Bank Indonesia and the Central Statistics Agency (BPS. The analysis tool used is Auto Regression Vector Model (VAR. The results of this study indicate that the one-way relationship between the variables of foreign reserves and export. Then one-way relationship between exchange rate and exports. Lastly, there is a two-way relationship between imports and foreign exchange reserves, two-way relationship between exchange rate and foreign exchange reserves, two-way relationship between imports and exports, two-way relationship between the exchange rate and imports. The results also showed foreign exchange reserves are significantly influenced by the movement itself at a probability of 1 %. Export variable negative and not significantly affect the foreign exchange reserves. While imports of positive and not significant to the foreign exchange reserves. Foreign Exchange Reserves Indonesia is positively influenced by the exchange rate and not significant. Keywords: Foreign exchange reserves, exports, imports, exchange rate   Abstrak. Penelitian ini bertujuan untuk mengetahui seberapa keterkaitan antar variabel ekspor, impor, dan nilai tukar rupiah terhadap Cadangan Devisa Indonesia. Data yang digunakan dalam kajian empiris ini merupakan data runtutaan waktu bulanan dari tahun 2011.01 sampai 2014. 12 yang berasal dari Bank Indonesia dan Badan Pusat Statistik (BPS. Alat analisis yang digunakan yaitu Vector Autoregression Model (VAR. Hasil dari penelitian ini menunjukkan bahwa hubungan searah antara variabel cadangan devisa ke ekspor. Lalu hubungan searah antara kurs terhadap ekspor Terakhir, terdapat hubungan dua arah antara impor dan cadangan devisa, hubungan dua arah antara kurs dan cadangan

  12. Analysis of radiological accident emissions of a lead-cooled experimental reactor. LEADER Project; Analisis radiologico de las emisiones en caso de accidente de un reactor experimental refrigerado por plomo. Proyecto LEADER

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Salcedo, F.; Cortes Martin, A.

    2013-07-01

    The LEADER project develops a conceptual level industrial size reactor cooled lead and a demonstration plant of this technology. The project objectives are to define the characteristics and design to installation scale reactor using available technologies and short-term components and assess safety aspects conducting a preliminary analysis of the impact of the facility.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

  14. 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)

  15. The Centralized Reliability Data Organization (CREDO); an advanced nuclear reactor reliability, availability, and maintainability data bank and data analysis center

    International Nuclear Information System (INIS)

    Knee, H.E.

    1991-01-01

    The Centralized Reliability Data Organization (CREDO) is a data bank and data analysis center, which since 1985 has been jointly sponsored by the US Department of Energy's (US DOE's) Office of Technology Support Programs and Japan's Power Reactor and Nuclear Fuel Development Corporation (PNC). It focuses on reliability, availability and maintainability (RAM) data for components (e.g. valves, pumps, etc.) operating in advanced nuclear reactor facilities. As originally intended, the purpose of the CREDO system was to provide a centralized source of accurate, up-to-date data and information for use in RAM analyses necessary for meeting DOE's data needs in the areas of advanced reactor safety assessments, design and licensing. In particular, creation of the CREDO system was considered an essential element needed to fulfill the DOE Breeder Reactor Safety Program's commitment of 'identifying and exploiting areas in which probabilistic methods can be developed and used in making reactor safety Research and Development choices and optimizing designs of safety systems'. CREDO and its operation are explained. (author)

  16. Adaptation and implementation of the TRACE code for transient analysis in designs lead cooled fast reactors; Adaptacion y aplicacion del codigo TRACE para el analisis de transitorios en disenos de reactores rapidos refrigerados por plomo

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro, A.; Ammirabile, L.; Martorell, S.

    2015-07-01

    Lead-Cooled Fast Reactor (LFR) has been identified as one of promising future reactor concepts in the technology road map of the Generation IVC International Forum (GIF)as well as in the Deployment Strategy of the European Sustainable Nuclear Industrial Initiative (ESNII), both aiming at improved sustainability, enhanced safety, economic competitiveness, and proliferation resistance. This new nuclear reactor concept requires the development of computational tools to be applied in design and safety assessments to confirm improved inherent and passive safety features of this design. One approach to this issue is to modify the current computational codes developed for the simulation of Light Water Reactors towards their applicability for the new designs. This paper reports on the performed modifications of the TRACE system code to make it applicable to LFR safety assessments. The capabilities of the modified code are demonstrated on series of benchmark exercises performed versus other safety analysis codes. (Author)

  17. Economical analysis to utilize MTR fuel elements using silicides in research reactors; Analisis economico sobre el uso de elementos combustibles MTR a base de siliciuros en reactores de investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Bergallo, Juan E; Novara, Oscar E; Adelfang, Pablo [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Combustibles Nucleares

    2000-07-01

    According to international programs on reducing enrichment in research reactors and the necessity to maintain their operation, new fuel elements have been developed in order to meet both objectives. Thus, U-Si alloy fuel elements for research reactors are becoming of greater interest for the international markets. It became necessary to make an economic study about the convenience of introducing this type of fuel elements in the RA-3 reactor and to know the potentiality of this fuel. The economical behavior of the reactor operation has been evaluated comparing the actual U{sub 3}O{sub 8} nuclear fuel cycle with U{sub 3}Si{sub 2} nuclear fuels. Results obtained show that the main economical factor to determine the change of fuels is the cost of fabrication, and the change is advisable up to an 80% difference. The other factors related to the cost of nuclear fuel cycle are not relevant or have real minor impacts. (author)

  18. A conceptual design of the International Thermonuclear Experimental Reactor for the Central Solenoid

    International Nuclear Information System (INIS)

    Heim, J.R.; Parker, J.M.

    1990-01-01

    Conceptual design of the International Thermonuclear Experimental Reactor (ITER) superconducting magnet system is nearing completion by the ITER Design Team, and one of the Central Solenoid (CS) designs is presented. The CS part of this magnet system will be a vertical stack of eight modules, approximately 16 m high, each having a approximate dimensions of: 4.1-m o.d., 2.8-m i.d., 1.9-m h. The peak field at the bore is approximately 13.5 T. Cable-in-conduit conductor with Nb 3 Sn composite wire will be used to wind the coils. The overall coil fabrication will use the insulate-wind-react-impregnate method. Coil modules will be fabricated using double-pancake coils with all splice joints located in the low-field region on the outside of the coils. All coils will be structurally graded with high-strength steel reinforcement which is co-wound with the conductor. We describe details of the CS coil design and analysis

  19. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  20. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  1. Qualification of the WIMS lattice code, for the design, operation and accident analysis of nuclear reactors; Calificacion del programa WIMS de calculo neutronico para diseno, seguimiento de operacion y analisis de accidentes de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lerner, A M [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina)

    1997-12-31

    A basic problem in nuclear reactor physics in that of the description of the neutron population behaviour in the multiplicative medium of a nuclear fuel. Due to the magnitude of the physical problem involved and the present degree of technological evolution regarding computing resources, of increasing complexity and possibilities, the calculation programs or codes have turned to be a basic auxiliary tool in reactor physics. In order to analyze the global problem, several aspects should be taken into consideration. The first aspect to be considered is that of the availability of the necessary nuclear data. The second one is the existence of a variety of methods and models to perform the calculations. The final phase for this kind of analysis is the qualification of the computing programs to be used, i.e. the verification of the validity domain of its nuclear data and the models involved. The last one is an essential phase, and in order to carry it on great variety of calculations are required, that will check the different aspects contained in the code. We here analyze the most important physical processes that take place in a nuclear reactor cell, and we consider the qualification of the lattice code WIMS, that calculates the neutronic parameters associated with such processes. Particular emphasis has been put in the application to natural uranium fuelled reactor, heavy water cooled and moderated, as the Argentinean power reactors now in operation. A wide set of experiments has been chosen: a.-Fresh fuel in zero-power experimental facilities and power reactors; b.-Irradiated fuel in both types of facilities; c.-Benchmark (prototype) experiments with loss of coolant. From the whole analysis it was concluded that for the research reactors, as well as for the heavy water moderated power reactors presently operating in our country, or those that could operate in a near future, the lattice code WIMS is reliable and produces results within the experimental values and

  2. Determination of nitrogen in wheat flour through Activation analysis using Fast neutron flux of a Thermal nuclear reactor; Determinacion de nitrogeno en harina de trigo mediante analisis por activacion empleando el flujo de neutrones rapidos de un reactor nuclear termico

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, T

    1976-07-01

    In this work is done a technical study for determining Nitrogen (protein) and other elements in wheat flour Activation analysis, with Fast neutrons from a Thermal nuclear reactor. Initially it is given an introduction about the basic principles of the methods of analysis. Equipment used in Activation analysis and a brief description of the neutron source (Thermal nuclear reactor). The realized experiments for determining the flux form in the irradiation site, the half life of N-13 and the interferences due to the sample composition are included too. Finally, the obtained results by Activation and the Kjeldahl method are tabulated. (Author)

  3. Sargent-IV Project. Development of new methodologies for safety analysis of Generation IV reactors; Proyecto SARGEB-IV. Desarrollo de nuevas metodologias de analisis de seguridad para reactores de Generacion IV

    Energy Technology Data Exchange (ETDEWEB)

    Queral, C.; Gallego, E.; Jimenez, G.

    2013-07-01

    The main result of this paper is the proposal for the addition of new ingredients in the safety analysis methodologies for Generation-IV reactors that integrates the features of probabilistic safety analysis within deterministic. This ensures a higher degree of integration between the classical deterministic and probabilistic methodologies.

  4. Application of the integrated analysis of safety (IAS) to sequences of Total loss of feed water in a PWR Reactor; Aplicacion del Analisis Integrado de Seguridad (ISA) a Secuencias de Perdidas Total de Agua de Alimentacion en un Reactor PWR

    Energy Technology Data Exchange (ETDEWEB)

    Moreno Chamorro, P.; Gallego Diaz, C.

    2011-07-01

    The main objective of this work is to show the current status of the implementation of integrated analysis of safety (IAS) methodology and its SCAIS associated tool (system of simulation codes for IAS) to the sequence analysis of total loss of feedwater in a PWR reactor model Westinghouse of three loops with large, dry containment.

  5. Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca

    International Nuclear Information System (INIS)

    Novakovic, M.

    1961-12-01

    The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO 2 with beryllium cladding, cooled by CO 2 under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO 2 . This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment

  6. Comparative analysis of results between CASMO, MCNP and Serpent for a suite of Benchmark problems on BWR reactors; Analisis comparativo de resultados entre CASMO, MCNP y SERPENT para una suite de problemas Benchmark en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli M, J. V.; Vargas E, S.; Gomez T, A. M. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Reyes F, M. del C.; Del Valle G, E., E-mail: vicente.xolocostli@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, UP - Adolfo Lopez Mateos, Edif. 9, 07738 Mexico D. F. (Mexico)

    2014-10-15

    In this paper a comparison is made in analyzing the suite of Benchmark problems for reactors type BWR between CASMO-4, MCNP6 and Serpent code. The Benchmark problem consists of two different geometries: a fuel cell of a pin and assembly type BWR. To facilitate the study of reactors physics in the fuel pin their nuclear characteristics are provided to detail, such as burnt dependence, the reactivity of selected nuclide, etc. With respect to the fuel assembly, the presented results are regarding to infinite multiplication factor for burning different steps and different vacuum conditions. Making the analysis of this set of Benchmark problems provides comprehensive test problems for the next fuels generation of BWR reactors with high extended burned. It is important to note that when making this comparison the purpose is to validate the methodologies used in modeling for different operating conditions, if the case is of other BWR assembly. The results will be within a range with some uncertainty, considering that does not depend on code that is used. Escuela Superior de Fisica y Matematicas of Instituto Politecnico Nacional (IPN (Mexico) has accumulated some experience in using Serpent, due to the potential of this code over other commercial codes such as CASMO and MCNP. The obtained results for the infinite multiplication factor are encouraging and motivate the studies to continue with the generation of the X S of a core to a next step a respective nuclear data library is constructed and this can be used by codes developed as part of the development project of the Mexican Analysis Platform of Nuclear Reactors AZTLAN. (Author)

  7. Analysis of the problems of induced draft fans in a carbo-electric power station; Analisis de la problematica de ventiladores de tiro inducido de una central carboelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Diaz Sanchez, Valentin de Jesus; Vital Flores, Francisco [LAPEM, Comision Federal de Electricidad (Mexico)

    2007-11-15

    The induced draft fans of the 350 MW units of a Thermo-electric power plant presented problems consisting of the failure of the capacity of gases extraction, together with the presence of cracks in the blades; this condition was observed since the stage of putting into service. Consequently, losses have been originated in the availability in two units, as well as, losses due to the manufacture of new impellers, which also originated that, in some cases, that the measures of the impellers, locally manufactured, differed from the originals, resulting in differences in the unit's efficiency. [Spanish] Los ventiladores tiro inducido de las unidades de 350 MW de una Central Termoelectrica presentaban una problematica consistente en la falla de capacidad de extraccion de gases, aunado a la presencia de fracturas en las aspas de los impulsores, esta condicion se observo desde la etapa de puesta en servicio. En consecuencia se han ocasionado perdidas de disponibilidad en dos unidades, asi como tambien, perdidas debido a la fabricacion de nuevos impulsores, lo que tambien origino que, en algunos casos, las medidas de los impulsores, fabricados localmente, diferian de los originales, dando como resultado diferencias en la eficiencia de las unidades.

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

    Energy Technology Data Exchange (ETDEWEB)

    Campos Gonzalez, Rina Margarita

    2007-07-15

    This work consists of the integration of three models previously developed which are described widely in Literature: model of the thermo-hydraulic channel, model of the modal neutronic and the model of the recirculation bows. The tool used for this connection of models is the PVM system, Parallel Virtual Machine that allowed paralleling the model by means of the concept of distributed computation. The purpose of making this connection of models is the one of obtaining a more complete tool than better represents the real configuration and the phenomenology of the nucleus of a BWR reactor, thus obtaining better results. In addition to maintaining the flexibility to improve the resulting model at any time, since the very complex or sophisticated models are difficult to improve being impossible to modify the equations they use and can include variables that are not of primary importance in the tackled problem or that mask relations among variables due to the excess of results. Also maintaining the flexibility for adding component of models or systems of the BWR reactor, all of this following the modeling needs. The Swedish Ringhals power plant was chosen to characterize the resulting connected model for counting on a Stability Benchmark that offers the opportunity to count on real plant data. Besides that in case 9 of cycle 14 of this Benchamark oscillations outside phase appeared, which are from great interest because the detection systems that register the average of the power of the nucleus do not detect them. Additionally in this work the model of the recirculation bows as an independent module is obtained in an individual way, since this model belongs to another work and works connected to the reactor vessel. The model of the recirculation bows is able to model several transients of interest, as it is shown in the Appendix A of this work, among which are found the tripping of recirculation pumps or the transference at low or high velocity of them. The scope of the

  9. Capture programs, analysis, data graphication for the study of the thermometry of the TRIGA Mark III reactor core; Programas de captura, analisis y graficado de datos para el estudio de la termometria del nucleo del reactor TRIGA Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Paredes G, L.C

    1991-05-15

    This document covers the explanation of the capture programs, analysis and graphs of the data obtained during the measurement of the temperatures of the instrumented fuel element of the TRIGA Mark III reactor and of the coolant one near to this fuel, using the conversion card from Analogic to Digital of 'Data Translation', and using a signal conditioner for five temperature measurers with the help of thermo par type K, developed by the Simulation and Control of the nuclear systems management department, which gives a signal from 0 to 10 Vcd for an interval of temperature of 0 to 1000 C. (Author)

  10. Adaptation and implementation of the TRACE code for transient analysis on designs of cooled lead fast reactors; Adaptacion y aplicacion del codigo TRACE para el analisis de transitorios en disenos de reactores rapidos refrigerados por plomo

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro, A.; Ammirabile, L.; Martorell, S.

    2014-07-01

    The article describes the changes implemented in the TRACE code to include thermodynamic tables of liquid lead drawn from experimental results. He then explains the process for developing a thermohydraulic model for the prototype ALFRED and analysis of a selection of representative transient conducted within the framework of international research projects. The study demonstrates the applicability of TRACE code to simulate designs of cooled lead fast reactors and exposes the high safety margins are there in this technology to accommodate the most severe transients identified in their security study. (Author)

  11. Determination of the flows profile in the role of power in the central thimble of TRIGA Mark III Reactor; Determinacion del perfil de flujos en funcion de la potencia en el dedal central del Reactor Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Garcia F, A.

    2010-07-01

    The overall objective of the thesis project is to determine the flow profiles sub cadmic and epi cadmic in the central thimble to different powers and operation times of TRIGA Mark III Reactor, using activation foils as detectors. In the reactor operation, it is necessary to know the neutron flow profile for to realize other tasks as: the radioisotopes production, research in reactors physics and fuel burning. The distribution of the neutron flow, accurately reflects what is happening in the reactor core, plus the flows value in this distribution is directly related to the power generated. For this reason it is performed the sub cadmic flow measurement with energies between 0 and 0.4 eV (energy of the cadmium cut E{sub cd} approx 0.4 eV) and epi cadmic flow with energies greater than 0.4 eV, in the central thimble powers to the powers of 10, 100 W, 1, 10 100 Kw and 1 MW. The method used is known as flakes activation, which is to be arranged by placing flakes ( 3 mm of diameter and 0.0508 mm of thickness) of a given material (either Au, In, Cu, Mn, etc.) into an aluminum tube outside diameter equal to 6.35 mm, alternating flakes with lids covered and discovered of cadmium (3.4 mm of diameter and 0.508 mm of thickness) and separated by lucite pieces of 3 mm of diameter and 25.4 mm in length. After irradiating the flakes for some time, is measured the gamma activity of each of them, using a hyper pure germanium detector of high resolution. Already known gamma activity, proceed to calculate the epi cadmic and sub cadmic flows using a computer program in Fortran language, called Caflu. (Author)

  12. Definition and Analysis of Heavy Water Reactor Benchmarks for Testing New Wims-D Libraries; Definicion y Analisis de Benchmarks de Reactores de Agua Pesada para Pruebas de Nuevas Bibliotecas de Datos Wims-D

    Energy Technology Data Exchange (ETDEWEB)

    Leszczynski, Francisco [Comision Nacional de Energia Atomica, Centro Atomico Bariloche (Argentina)

    2000-07-01

    This work is part of the IAEA-WIMS Library Update Project (WLUP). A group of heavy water reactor benchmarks have been selected for testing new WIMS-D libraries, including calculations with WIMSD5B program and the analysis of results.These benchmarks cover a wide variety of reactors and conditions, from fresh fuels to high burnup, and from natural to enriched uranium.Besides, each benchmark includes variations in lattice pitch and in coolants (normally heavy water and void).Multiplication factors with critical experimental bucklings and other parameters are calculated and compared with experimental reference values.The WIMS libraries used for the calculations were generated with basic data from JEF-2.2 Rev.3 (JEF) and ENDF/B-VI iNReleaseln 5 (E6) Results obtained with WIMS-86 (W86) library, included with WIMSD5B package, from Windfrith, UK with adjusted data, are included also, for showing the improvements obtained with the new -not adjusted- libraries.The calculations with WIMSD5B were made with two methods (input program options): PIJ (two-dimension collision probability method) and DSN (one-dimension Sn method, with homogenization of materials by ring).The general conclusions are: the library based on JEF data and the DSN meted give the best results, that in average are acceptable.

  13. Analysis of the thorium inclusion in the fuel of a fast reactor cooled by lead; Analisis de la inclusion de torio en el combustible de un reactor rapido enfriado por plomo

    Energy Technology Data Exchange (ETDEWEB)

    Juarez M, L. C.; Francois L, J. L., E-mail: lcjm@ier.unam.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico)

    2017-09-15

    In the present work, we first verified a model of the European reactor cooled with lead (ELFR). The calculations were made with the code Monte Carlo serpent 2.27 and the library of cross sections Jeff-3.1. For this verification, three neutron parameters were compared: the evolution of the neutron multiplication factor, the Doppler constant and the effect of the vacuum fraction of the refrigerant, obtaining a good approximation with the reference values. Subsequently, the inclusion of thorium as a fertile material within the fuel was analyzed and the same neutron parameters were compared with the original fuel. The evolution of criticality for the case of thorium fuel differs significantly with respect to that of the original fuel (without thorium); this is due mainly to the breeding of the fissile isotope {sup 233}U. Therefore, is possible to have a longer fuel cycle, favoring the availability factor of the plant, without compromising the performance of the reactor since both the Doppler constant and the effect of the vacuum fraction of the refrigerant show a similar tendency to those of the original fuel, being negative in both cases. (Author)

  14. Determination of the energy spectrum of the neutrons in the central thimble of the reactor core TRIGA Mark III; Determinacion del espectro de energia de los neutrones en el dedal central del nucleo del reactor Triga Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Parra M, M. A.

    2014-07-01

    This thesis presents the neutron spectrum measurements inside the core of the TRIGA Mark III reactor at 1 MW power in steady-state, with the bridge placed in the center of the swimming pool, using several metallic threshold foils. The activation detectors are inserted in the Central Thimble of the reactor core, all the foils are irradiated in the same position and irradiation conditions (one by one). The threshold detectors are made of different materials such as: Au{sup 197}, Ni{sup 58}, In{sup 115}, Mg{sup 24}, Al{sup 27}, Fe{sup 58}, Co{sup 59} and Cu{sup 63}, they were selected to cover the full range the energies (10{sup -10} to 20 MeV) of the neutron spectrum in the reactor core. After the irradiation, the activation detectors were measured by means of spectrometry gamma, using a high resolution counting system with a hyper pure Germanium crystal, in order to obtain the saturation activity per target nuclide. The saturation activity is one of the main input data together with the initial spectrum, for the computational code SANDBP (hungarian version of the code SAND-II), which through an iterative adjustment, gives the calculated spectrum. The different saturation activities are necessary for the unfolding method, used by the computational code SANDBP. This research work is very important, since the knowledge of the energetic and spatial distribution of the neutron flux in the irradiation facilities, allows to characterize properly the irradiation facilities, just like, to estimate with a good precision various physics parameters of the reactor such as: neutron fluxes (thermal, intermediate and fast), neutronic dose, neutron activation analysis (NAA), spectral indices (cadmium ratio), buckling, fuel burnup, safety parameters (reactivity, temperature distribution, peak factors). In addition, the knowledge of the already mentioned parameters can give a best use of reactor, optimizing the irradiations requested by the users for their production process or

  15. Analysis of the accident at Fukushima Daiichi nuclear power plant in an A BWR reactor; Analisis del accidente de la planta nucleoelectrica de Fukushima Daiichi en un reactor tipo ABWR

    Energy Technology Data Exchange (ETDEWEB)

    Escorcia O, D. [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Salazar S, E., E-mail: daniel.escorcia.ortiz@gmail.com [UNAM, Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (Mexico)

    2016-09-15

    The present work aims to recreate the accident occurred at the Fukushima Daiichi nuclear power plant in Japan on March 11, 2011, making use of an academic simulator of forced circulation of the A BWR reactor provided by the IAEA to know the scope of this simulator. The simulator was developed and distributed by the IAEA for academic purposes and contains the characteristics and general elements of this reactor to be able to simulate transients and failures of different types, allowing also to observe the general behavior of the reactor, as well as several phenomena and present systems in the same. Is an educational tool of great value, but it does not have a scope that allows the training of plant operators. To recreate the conditions of the Fukushima accident in the simulator, we first have to know what events led to this accident, as well as the actions taken by operators and managers to reduce the consequences of this accident; and the sequence of events that occurred during the course of the accident. Differences in the nuclear power plant behavior are observed and interpreted throughout the simulation, since the Fukushima plant technology and the simulator technology are not the same, although they have several elements in common. The Fukushima plant had an event that by far exceeded the design basis, which triggered in an accident that occurred in the first place by a total loss of power supply, followed by the loss of cooling systems, causing a level too high in temperature, melting the core and damaging the containment accordingly, allowing the escape of hydrogen and radioactive material. As a result of the simulation, was determined that the scope of the IAEA academic simulator reaches the entrance of the emergency equipment, so is able to simulate almost all the events occurred at the time of the earthquake and the arrival of the tsunami in the nuclear power plant of Fukushima Daiichi. However, due to its characteristics, is not able to simulate later

  16. Determination of the flows profile in the role of power in the central thimble of TRIGA Mark III Reactor

    International Nuclear Information System (INIS)

    Garcia F, A.

    2010-01-01

    The overall objective of the thesis project is to determine the flow profiles sub cadmic and epi cadmic in the central thimble to different powers and operation times of TRIGA Mark III Reactor, using activation foils as detectors. In the reactor operation, it is necessary to know the neutron flow profile for to realize other tasks as: the radioisotopes production, research in reactors physics and fuel burning. The distribution of the neutron flow, accurately reflects what is happening in the reactor core, plus the flows value in this distribution is directly related to the power generated. For this reason it is performed the sub cadmic flow measurement with energies between 0 and 0.4 eV (energy of the cadmium cut E cd ∼ 0.4 eV) and epi cadmic flow with energies greater than 0.4 eV, in the central thimble powers to the powers of 10, 100 W, 1, 10 100 Kw and 1 MW. The method used is known as flakes activation, which is to be arranged by placing flakes ( 3 mm of diameter and 0.0508 mm of thickness) of a given material (either Au, In, Cu, Mn, etc.) into an aluminum tube outside diameter equal to 6.35 mm, alternating flakes with lids covered and discovered of cadmium (3.4 mm of diameter and 0.508 mm of thickness) and separated by lucite pieces of 3 mm of diameter and 25.4 mm in length. After irradiating the flakes for some time, is measured the gamma activity of each of them, using a hyper pure germanium detector of high resolution. Already known gamma activity, proceed to calculate the epi cadmic and sub cadmic flows using a computer program in Fortran language, called Caflu. (Author)

  17. Sensitiveness Analysis of Neutronic Parameters Due to Uncertainty in Thermo-hydraulic parameters on CAREM-25 Reactor; Analisis de Sensibilidad de los Parametros Neutronicos ante Incertezas en los Parametros Termohidraulicos en el Reactor CAREM-25

    Energy Technology Data Exchange (ETDEWEB)

    Serra, Oscar [Comision Nacional de Energia Atomica, Centro Atomico Bariloche (Argentina)

    2000-07-01

    Some studies were done about the effect of the uncertainty in the values of several thermo-hydraulic parameters on the core behaviour of the CAREM-25 reactor.By using the chain codes CITVAP-THERMIT and the perturbation the reference states, it was found that concerning to the total power, the effects were not very important, but were much bigger for the pressure.Furthermore were hardly significant in the presence of any perturbation on the void fraction calculation and the fuel temperature.The reactivity and the power peaking factor had highly important changes in the case of the coolant flow.We conclude that the use of this procedure is adequate and useful to our purpose.

  18. Analysis of an accident type sbloca in reactor contention AP1000 with 8.0 Gothic code; Analisis de un accidente tipo Sbloca en la contencion del reactor AP1000 con el codigo Gothic 8.0

    Energy Technology Data Exchange (ETDEWEB)

    Goni, Z.; Jimenez Varas, G.; Fernandez, K.; Queral, C.; Montero, J.

    2016-08-01

    The analysis is based on the simulation of a Small Break Loss-of-Coolant-Accident in the AP1000 nuclear reactor using a Gothic 8.0 tri dimensional model created in the Science and Technology Group of Nuclear Fision Advanced Systems of the UPM. The SBLOCA has been simulated with TRACE 5.0 code. The main purpose of this work is the study of the thermo-hydraulic behaviour of the AP1000 containment during a SBLOCA. The transients simulated reveal close results to the realistic behaviour in case of an accident with similar characteristics. The pressure and temperature evolution enables the identification of the accident phases from the RCS point of view. Compared to the licensing calculations included in the AP1000 Safety Analysis, it has been proved that the average pressure and temperature evolution is similar, yet lower than the licensing calculations. However, the temperature and inventory distribution are significantly heterogeneous. (Author)

  19. Effects of generation and optimization of libraries of effective sections in the analysis of transient in PWR reactors; Efectos de generacion y optimizacion de librerias de secciones eficaces en el analisis de transitorios en reactores PWR

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez-Cervera, S.; Garcia Herranz, N.; Cuervo, D.; Ahnert, C.

    2014-07-01

    In this paper evaluates the impact that has a certain mesh on a transient in a PWR reactor in the expulsion of a control bar. Have been used for this purpose the coupled codes neutronic and Thermo-hydraulic COBAYA3/COBRA-TF. This objective has been chosen the OECD/NEA PWR MOX/UO{sub 2} rod ejection transient benchmark provides isotopic compositions and defined geometric configurations that allow the use of codes lattice to generate own bookstores. The code used for this transport has been the code APOLLO2.8. The results show large discrepancies when using the benchmark library or libraries own by comparing them to the other participants solutions. The source of these discrepancies is the nodal effective sections provided in the benchmark. (Author)

  20. Design optimization of the Laguna Verde nuclear power station fuel recharge; Optimacion del diseno de recargas de combustible para la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cortes Campos, Carlos Cristobal [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico)

    1991-12-31

    It is described, in general terms, the procedure that is followed to accomplish the optimization of the recharge design, and an example is shown where this procedure was applied for the analysis of the type BWR reactor of Unit No. 1 of the Laguna Verde Nuclear Power Station. [Espanol] Se describe en terminos generales el procedimiento que se sigue para realizar la optimacion del diseno de recargas, y se muestra un ejemplo en el que se utilizo dicho procedimiento para el analisis del reactor tipo BWR de la unidad 1, de la Central Laguna Verde (CLV).

  1. Design optimization of the Laguna Verde nuclear power station fuel recharge; Optimacion del diseno de recargas de combustible para la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cortes Campos, Carlos Cristobal [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico)

    1992-12-31

    It is described, in general terms, the procedure that is followed to accomplish the optimization of the recharge design, and an example is shown where this procedure was applied for the analysis of the type BWR reactor of Unit No. 1 of the Laguna Verde Nuclear Power Station. [Espanol] Se describe en terminos generales el procedimiento que se sigue para realizar la optimacion del diseno de recargas, y se muestra un ejemplo en el que se utilizo dicho procedimiento para el analisis del reactor tipo BWR de la unidad 1, de la Central Laguna Verde (CLV).

  2. Determination of the energy spectrum of the neutrons in the central thimble of the reactor core TRIGA Mark III

    International Nuclear Information System (INIS)

    Parra M, M. A.

    2014-01-01

    This thesis presents the neutron spectrum measurements inside the core of the TRIGA Mark III reactor at 1 MW power in steady-state, with the bridge placed in the center of the swimming pool, using several metallic threshold foils. The activation detectors are inserted in the Central Thimble of the reactor core, all the foils are irradiated in the same position and irradiation conditions (one by one). The threshold detectors are made of different materials such as: Au 197 , Ni 58 , In 115 , Mg 24 , Al 27 , Fe 58 , Co 59 and Cu 63 , they were selected to cover the full range the energies (10 -10 to 20 MeV) of the neutron spectrum in the reactor core. After the irradiation, the activation detectors were measured by means of spectrometry gamma, using a high resolution counting system with a hyper pure Germanium crystal, in order to obtain the saturation activity per target nuclide. The saturation activity is one of the main input data together with the initial spectrum, for the computational code SANDBP (hungarian version of the code SAND-II), which through an iterative adjustment, gives the calculated spectrum. The different saturation activities are necessary for the unfolding method, used by the computational code SANDBP. This research work is very important, since the knowledge of the energetic and spatial distribution of the neutron flux in the irradiation facilities, allows to characterize properly the irradiation facilities, just like, to estimate with a good precision various physics parameters of the reactor such as: neutron fluxes (thermal, intermediate and fast), neutronic dose, neutron activation analysis (NAA), spectral indices (cadmium ratio), buckling, fuel burnup, safety parameters (reactivity, temperature distribution, peak factors). In addition, the knowledge of the already mentioned parameters can give a best use of reactor, optimizing the irradiations requested by the users for their production process or research projects. (Author)

  3. 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)

  4. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

    The requirements for OLTP database systems are becoming ever more demanding. Domains such as finance and computer games increasingly mandate that developers be able to encode complex application logic and control transaction latencies in in-memory databases. At the same time, infrastructure...... engineers in these domains need to experiment with and deploy OLTP database architectures that ensure application scalability and maximize resource utilization in modern machines. In this paper, we propose a relational actor programming model for in-memory databases as a novel, holistic approach towards......-level function calls. In contrast to classic transactional models, however, reactors allow developers to take advantage of intra-transaction parallelism and state encapsulation in their applications to reduce latency and improve locality. Moreover, reactors enable a new degree of flexibility in database...

  5. Advances in the development of the Mexican platform for analysis and design of nuclear reactors: AZTLAN Platform; Avances en el desarrollo de la plataforma mexicana para analisis y diseno de reactores nucleares: AZTLAN Platform

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico); Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico)

    2017-09-15

    The AZTLAN platform project: development of a Mexican platform for the analysis and design of nuclear reactors, financed by the SENER-CONACYT Energy Sustain ability Fund, was approved in early 2014 and formally began at the end of that year. It is a national project led by the Instituto Nacional de Investigaciones Nucleares (ININ) and with the collaboration of Instituto Politecnico Nacional (IPN), the Universidad Autonoma Metropolitana (UAM) and Universidad Nacional Autonoma de Mexico (UNAM) as part of the development team and with the participation of the Laguna Verde Nuclear Power Plant, the National Commission of Nuclear Safety and Safeguards, the Ministry of Energy and the Karlsruhe Institute of Technology (Kit, Germany) as part of the user group. The general objective of the project is to modernize, improve and integrate the neutronic, thermo-hydraulic and thermo-mechanical codes, developed in Mexican institutions, in an integrated platform, developed and maintained by Mexican experts for the benefit of Mexican institutions. Two years into the process, important steps have been taken that have consolidated the platform. The main results of these first two years have been presented in different national and international forums. In this congress, some of the most recent results that have been implemented in the platform codes are shown in more detail. The current status of the platform from a more executive view point is summarized in this paper. (Author)

  6. An examination of reliability critical items in liquid metal reactors: An analysis by the Centralized Reliability Data Organization (CREDO)

    International Nuclear Information System (INIS)

    Humphrys, B.L.; Haire, M.J.; Koger, K.H.; Manneschmidt, J.F.; Setoguchi, K.; Nakai, R.; Okubo, Y.

    1987-01-01

    The Centralized Reliability Data Organization (CREDO) is the largest repository of liquid metal reactor (LMR) component reliability data in the world. It is jointly sponsored by the US Department of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The CREDO data base contains information on a population of more than 21,000 components and approximately 1300 event records. A conservative estimation is that the total component operating hours is approaching 3.5 billion hours. Because data gathering for CREDO concentrates on event (failure) information, the work reported here focuses on the reliability information contained in CREDO and the development of reliability critical items lists. That is, components are ranked in prioritized lists from worst to best performers from a reliability standpoint. For the data contained in the CREDO data base, FFTF and JOYO show reliability growth; EBR-II reveals a slight unreliability growth for those components tracked by CREDO. However, tabulations of events which cause reactor shutdowns decrease with time at each site

  7. ANALISIS PENYEBAB BANJIR KALI JUANA

    Directory of Open Access Journals (Sweden)

    Teguh Marhendi

    2017-04-01

    Full Text Available Kali Juana yang berada di Kabupaten Pati dan Kudus serta sebagian kecil di Kabupaten Grobogan dan Blora, merupakan kawasan banjir. Kejadian banjir di Kali Juana, sudah menjadi rutinitas setiap musim hujan.Dari Januari sampai bulan Mei 2016tercatat terjadi 11 kejadian banjir dibeberapa wilayah, seperti Kecamatan Kaliwungu, Undaan dan Mejobo (Kab. Kudus serta Pati, Margorejo dan Juwana (Kab. Pati. Kali Juana merupakan bifurkasi Kali Serang pada Pintu Wilalung, yang berfungsi sebagai pintu pengatur banjir (dibangun pada zaman Belanda tahun 1918, melalui Kali Babalan menuju ke Kali Juana. Tulisan inidimaksudkan untuk menganalisis penyebab kejadian banjir di Kali Juana. Analisis dilakukan dengan melakukan kajani dan analisis hujan serta mekanisme aliran. Hasil analisis menunjukkan bahwa kondisi Kali Juana dari pertemuan Kali Logung di pintu Wilalung sampai hilir telah mengalami pendangkalan akibat kemiringan dasar atau topografi yang landai, dan mengakibatkan mudah terjadi sedimentasi sehingga mengurangi kapasitas pengaliran. Hal ini menyebabkan luapan banjir sering menggenangi wilayah Kabupaten Kudus dan Pati.

  8. A central European training course on reactor physics and kinetics - the 'Eugene Wigner Course' - Organisers view

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.; Matejka, K.; Sklenka, L.; Miglierini, M.; Sukods, C.

    2004-01-01

    Initiated by the 5th Framework Program of the European Commission, the European Nuclear Engineering Network (ENEN) is preparing the future European Nuclear Education schemes, degrees and requirements. To fully utilize the benefits of international cooperation and to promote the knowledge of students in nuclear engineering a 2.5 weeks course has been held, both in spring 2003 and 2004. The main emphasis of the course is to perform reactor physics and kinetics experiments on three different research- and training reactors in three different locations (Vienna, Prague, Budapest). The experimental work is preceded by theoretical lectures aiming to prepare the students for the experiments (Bratislava). The students' work will be evaluated, and upon success the students will get a certificate. The finally accepted credit (ECTS) value will be determined by the students' home university. The ENEN-recommended value is between 6 and 8 ECTS. The more detailed description of the course will be given in the full paper. (author)

  9. Characterization of the malignity of tumors in the central nervous system utilizing the correlation dimension analysis; Caracterizacion de la malignidad de tumores del sistema nervioso central utilizando analisis de dimension de correlacion

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, D.; Zambrano, C.; Martin L, M. [Departamento de Fisica y Centro de Resonancia Magnetica. Facultad de Ciencias, Universidad Central de Venezuela, A.P. 47586, Caracas 1041-A (Venezuela)

    1998-12-31

    In the present work it is proposed a method for the characterization of the irregularities present in the edges of malignant leisure of central nervous system over axial images generated through Nuclear magnetic Resonance by images. Through the use of techniques of digital images processing was possible to locate, extract and generate temporal series. These temporal series were utilized using the correlation dimension concept for producing a parameter which takes different values depending of the leisure type. It is demonstrated that this type of analysis suffers in a very acceptable form independently of the errors which can be generate by the fact that in the practice of temporal series obtained they are composed by a reduced number of points. (Author)

  10. Characterization of the malignity of tumors in the central nervous system utilizing the correlation dimension analysis; Caracterizacion de la malignidad de tumores del sistema nervioso central utilizando analisis de dimension de correlacion

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, D; Zambrano, C; Martin L, M [Departamento de Fisica y Centro de Resonancia Magnetica. Facultad de Ciencias, Universidad Central de Venezuela, A.P. 47586, Caracas 1041-A (Venezuela)

    1999-12-31

    In the present work it is proposed a method for the characterization of the irregularities present in the edges of malignant leisure of central nervous system over axial images generated through Nuclear magnetic Resonance by images. Through the use of techniques of digital images processing was possible to locate, extract and generate temporal series. These temporal series were utilized using the correlation dimension concept for producing a parameter which takes different values depending of the leisure type. It is demonstrated that this type of analysis suffers in a very acceptable form independently of the errors which can be generate by the fact that in the practice of temporal series obtained they are composed by a reduced number of points. (Author)

  11. ANALISIS LITERASI EKONOMI

    Directory of Open Access Journals (Sweden)

    Peter Garlans Sina

    2012-10-01

    Full Text Available Abstract: Analysis of Economic Literacy. The aim of this research is as an effort to increase economic literacy for individuals and households who want to achieve prosperity. Therefore, the obligation of improving the economic literacy needs to be done in a well-planned manner and come from the strong intention to learn in order to improve the economic literacy. It could have an effect on the assets accumulation, a better debt management, as a protection, as well as to increase savings and managing spending intelligently.   Keyword: economic literacy, asset, debt, protection, saving, spending   Abstrak: Analisis Literasi Ekonomi. Tulisan ini bertujuan sebagai upaya meningkatkan literasi ekonomi bagi individu maupun rumah tangga yang menginginkan mencapai kesejahteraan. Oleh karena itu, kewajiban meningkatkan literasi ekonomi perlu dilakukan secara terencana dan diawali dari niat untuk belajar meningkatkan literasi ekonomi karena dapat berefek pada akumulasi aset, pengelolaan utang yang tepat, proteksi, meningkatkan tabungan dan cerdas mengelola pengeluaran.   Kata kunci: literasi ekonomi, aset, utang, proteksi, menabung, pengeluaran

  12. Determination of the neutrons energy spectrum in the central thimble of the reactor core TRIGA Mark III; Determinacion del espectro de energia de los neutrones en el dedal central del nucleo del reactor TRIGA Mark III

    Energy Technology Data Exchange (ETDEWEB)

    Parra M, M. A.; Luis L, M. A. [Universidad Autonoma Metropolitana, Unidad Azcapotzalco, Division de Ciencias Basicas, Av. San Pablo No. 180, Col. Reynosa Tamaulipas, 02200 Mexico D. F. (Mexico); Raya A, R.; Cruz G, H. S., E-mail: roberto.raya@inin.gob.mx [ININ, Departamento del Reactor, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    This work presents the measurement of the neutrons spectrum in energies in the central thimble of the reactor TRIGA Mark III to a power of 1 MW in stationary state, with the core in the center of the pool. To achieve this objective, several thin sheets were irradiated (one at the time) in the same position of the core. The activation probes were selected in such a way that covered the energy range (1 x 10{sup -10} to 20 MeV) of the neutrons spectrum in the reactor core, for this purpose thin sheets were used of {sup 197}Au, {sup 58}Ni, {sup 115}In, {sup 24}Mg, {sup 27}Al, {sup 58}Fe, {sup 59}Co and {sup 63}Cu. After the irradiation, the high energy gamma emissions of the activated thin sheets were measured by means of gamma spectrometry, in a counting system of high resolution, with a Hyper pure Germanium detector, obtaining this way the activity induced in the thin sheets whose magnitude is proportional to the intensity of the neutrons flow, this activity together to a theoretical initial spectrum are the main entrance data of the computational code SANDBP (Hungarian version of the code Sand-II) that uses the unfolding method for the calculation of the spectrum. (Author)

  13. Numerical calculation procedure for criticality parameters of the two-zone reflected reactor with flat central zone

    International Nuclear Information System (INIS)

    Bosevski, T.; Strugar, P.

    1966-10-01

    In determining the criticality parameters of a two-zone reactor with flat central zone one encounters a numerical problem requiring the solution of a system of two non-linear equations. To solve them the Newton method, which proved convenient, was used n this work. By comparing our results with those reported one obtains about 5% smaller values of both the radius of the flat zone and of the radial buckling of the outer zone. This discrepancy probably results from some approximations used in solving the same system of equations used in solving the same system of equations where the procedure form was applied, whereas the calculation time is by one order of magnitude smaller

  14. Effect of removal of a central thimble on coolant flow distribution in a research reactor fuel element

    International Nuclear Information System (INIS)

    Green, W.J.

    1977-01-01

    Using two twice full-size models of a HIFAR research reactor fuel element, experiments have been performed to determine how the flow distribution of coolant gas through the element in a transfer flask is affected by removal of the central instrumentation thimble. With the thimble present, experimental flow results agree with theoretical predictions. Over the range of total flowrates considered, mass flow apportioning among the five annular channels was independent of annular channel Reynolds number (in the range 3500 to 10,500) and ranged between 13% and 27% of the total flowrate. For the case with the thimble removed, interesting experimental flow characteristics were obtained which could not have been predicted. Flow apportioning among the annular channels was found to be uniquely dependent upon total flowrate and ranged between 3% and 8% for the experimental conditions investigated (annular channel Reynolds numbers in the range 800 to 4000). (Author)

  15. Determination of the neutrons energy spectrum in the central thimble of the reactor core TRIGA Mark III

    International Nuclear Information System (INIS)

    Parra M, M. A.; Luis L, M. A.; Raya A, R.; Cruz G, H. S.

    2013-10-01

    This work presents the measurement of the neutrons spectrum in energies in the central thimble of the reactor TRIGA Mark III to a power of 1 MW in stationary state, with the core in the center of the pool. To achieve this objective, several thin sheets were irradiated (one at the time) in the same position of the core. The activation probes were selected in such a way that covered the energy range (1 x 10 -10 to 20 MeV) of the neutrons spectrum in the reactor core, for this purpose thin sheets were used of 197 Au, 58 Ni, 115 In, 24 Mg, 27 Al, 58 Fe, 59 Co and 63 Cu. After the irradiation, the high energy gamma emissions of the activated thin sheets were measured by means of gamma spectrometry, in a counting system of high resolution, with a Hyper pure Germanium detector, obtaining this way the activity induced in the thin sheets whose magnitude is proportional to the intensity of the neutrons flow, this activity together to a theoretical initial spectrum are the main entrance data of the computational code SANDBP (Hungarian version of the code Sand-II) that uses the unfolding method for the calculation of the spectrum. (Author)

  16. Central Reactivity Measurements on Assemblies 1 and 3 of the Fast Reactor FR0

    International Nuclear Information System (INIS)

    Londen, S.O.

    1966-01-01

    The reactivity effects of small samples of various materials have been measured, by the period method at the core centre of Assemblies 1 and 3 of the fast zero power reactor FR0. For some materials the reactivity change as a function of sample size has also been determined experimentally. The core of Assembly 1 consisted only of uranium enriched to 20 % whereas the core of Assembly 3 was diluted with 30 % graphite. The results have been compared with calculated values obtained with a second-order transport-theoretical perturbation model and using differently shielded cross sections depending upon sample size. Qualitative agreement has generally been found, although discrepancies still exist. The spectrum perturbation caused by the experimental arrangement has been analyzed and found to be rather important

  17. Central Reactivity Measurements on Assemblies 1 and 3 of the Fast Reactor FR0

    Energy Technology Data Exchange (ETDEWEB)

    Londen, S O

    1966-01-15

    The reactivity effects of small samples of various materials have been measured, by the period method at the core centre of Assemblies 1 and 3 of the fast zero power reactor FR0. For some materials the reactivity change as a function of sample size has also been determined experimentally. The core of Assembly 1 consisted only of uranium enriched to 20 % whereas the core of Assembly 3 was diluted with 30 % graphite. The results have been compared with calculated values obtained with a second-order transport-theoretical perturbation model and using differently shielded cross sections depending upon sample size. Qualitative agreement has generally been found, although discrepancies still exist. The spectrum perturbation caused by the experimental arrangement has been analyzed and found to be rather important.

  18. PENERAPAN ANALISIS SWOC DALAM RENCANA STRATEGIS PENDIDIKAN

    Directory of Open Access Journals (Sweden)

    Hardianto -

    2018-01-01

    Full Text Available Analisis SWOC merupakan salah satu langkah yang bisa diambil dalam membuat sebuah rencana strategis pendidikan. Analisis ini dilakukan untuk melihat secara mendalam situasi internal dan eksternal organisasi. Situasi internal yang dilihat adalah kekuatan (Strenghts dan kelemahan (Weaknesses organisasi pendidikan. Situasi eksternal berupa peluang (Opportinities dan tantangan (Challenges. Untuk membuat sebuah rencana strategis yang baik dapat dilakukan dengan menganalisis setiap kekuatan, kelemahan, peluang dan tantangan. Teknik kartu salju (snow card bisa digunakan dalam melakukan analisis SWOC. Hasil analisis tersebut nantinya akan melahirkan kombinasi strategi kekuatan-peluang, kekuatan-tantangan, kelemahan-peluang dan kelemahan-tantangan.

  19. 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)

  20. Chemical processes of coal for use in power plants. Part 1: Approximate analysis and associated indexes of pulverized coal; Procesos quimicos del carbon para su uso en centrales termoelectricas. Parte 1: Analisis aproximado e indices asociados del carbon pulverizado

    Energy Technology Data Exchange (ETDEWEB)

    Altamirano-Bedolla, J. A.; Manzanares-Papayanopoulos, E.; Herrera-Velarde, J. R. [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)]. E-mail: emp@iie.org.mx

    2010-11-15

    The usage of hydrocarbons, such as natural gas, oil products and coal, will be the main source of energy to the mankind for next generations. Therefore, the actual research and technological developments point out to employ with high efficiency those fuels. The main interests are to release most of the energy as possible and to guide the combustion reactions. It is well known that during the combustion process of coal, the chemical energy is converted to thermal energy, which it allows the steam production, and therefore to produce energy through an electric generator. The main interest of the work presented here is to study the behavior of the coal combustion processes in function of the approximate analysis and some associate indices of that analysis, to point out the optimization of the coal usage as main fuel in electrical power generation plants. [Spanish] El uso de hidrocarburos como son el gas natural, los derivados del petroleo y el carbon mineral, continuara siendo en las proximas decadas la principal fuente de energia de la humanidad. Por consiguiente, la investigacion cientifica y los desarrollos tecnologicos actualmente se enfocan en emplear de manera mas eficiente dichos combustibles, satisfaciendo entre otros factores, dos intereses principales: liberar la mayor cantidad de energia, reduciendo al minimo el material combustible no quemado, y direccionar las reacciones del proceso de combustion para minimizar la cantidad de productos no deseados resultantes de la reaccion. A traves de los procesos quimicos de combustion del carbon, se transforma la energia quimica a energia termica, lo que permite la produccion de vapor para a su vez impulsar una turbina la cual esta acoplada a un generador electrico. El objetivo del presente trabajo es el estudio del comportamiento de los procesos quimicos que se llevan a cabo durante las reacciones de combus-tion del carbon en funcion del analisis aproximado y de los indices asociados resultantes de dicho analisis; lo

  1. Physical start up of the Dalat nuclear research reactor with the core configuration having a central neutron trap; Khoi dong vat ly lo phan ung hat nhan Da Lat voi cau hinh vung hoat co bay notron

    Energy Technology Data Exchange (ETDEWEB)

    Hien, Pham Duy; Huy, Ngo Quang; Long, Vu Hai; Mai, Tran Khanh [Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    After the reactor has reached physical criticality with the core configuration exempt from central neutron trap on 1 November 1983, the core configuration with a central neutron trap has been arranged in the reactor and the reactor has reached physical criticality with this core configuration at 17h48 on 18 December 1983. The integral worths of different control rods are determined with accuracy. 2 refs., 24 figs., 18 tabs.

  2. Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

    Energy Technology Data Exchange (ETDEWEB)

    Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

    1963-10-15

    defectos hallados: Reactor de Elk River. Se descubrieron grietas en parte del revestimiento superficial del recipiente del reactor; ello obligo a efectuar una serie de investigaciones y analisis, asi como ciertas reparaciones y modificaciones del recipiente. La insuficiente capacidad de separacion de vapor obligo a sustituir y modificar algunas piezas metalicas en el interior del recipiente del reactor. Central nucleoelectrica de Hallam. Debido al arrastre de helio, hubo que modificar los circuitos secundarios de sodio. La falla de un tubo del intercambiador de calor intermedio (sodio-sodio) obligo a llevar a cabo una serie de analisis para descubrir su causa y extraer y reparar el intercambiador. Central nucleoelectrica de Piqua. Durante la limpieza de las tuberias con agentes quimicos, se dallaron varias valvulas que fue preciso reparar o sustituir. Las fugas en el circuito del refrigerante organico y del vapor secundario provocaron demoras repetidas. Una vez concluidas las reparaciones e introducidas las modificaciones necesarias, se comprobo que las caracteristicas de rendimiento reales de cada uno de los tres reactores se ajustaban estrictamente a las previstas en el proyecto. (author) [Russian] Fakticheskij opyt, nakoplennyj vo vremya predehkspluatatsionnykh ispytanij trekh yadernykh ehnergeticheskikh ustanovok, postroennykh po demonstratsionnoj programme ehnergeticheskikh reaktorov Komissii po atomnoj ehnergii Soedinennykh Shtatov, pozvolyaet sdelat' nekotorye obobshcheniya v otnoshenii ehtoj fazy stroitel'stva i ehkspluatatsii ustanovok. Tri ustanovki, a imenno Ehlk-riverskij reaktor (ERR), Khehllemskaya yadernaya ehnergeticheskaya ustanovka (HNPF) i Pikuaskaya yadernaya ehnergeticheskaya ustanovka (PNPF), predstavlyayut tri razlichnykh tipa reaktorov: reaktor s kipyashej vodoj s estestvennoj tsirkulyatsiej, natrievo-grafitovyj reaktor i reaktor s organicheskim teplonositelem i zamedlitelem sootvetstvenno. Period predehkspluatatsionnykh ispytanij okhvatyvaet vremya

  3. Analisis Semiotik Sajak Bulang Cahaya

    Directory of Open Access Journals (Sweden)

    Junaidi Junaidi

    2014-11-01

    Full Text Available Penelitian ini bertujuan menggali makna tanda yang terdapat dalam sajak Bulang Cahaya karya Rida K Liamsi. Untuk menggali makna itu, pendekatan analisis semiotik Roland Barthes digunakan. Hasil penelitian menunjukkan bahwa sajak ini berisi tanda-tanda bersumber dari kosa kata Melayu lama. Sajak ini juga berisi simbol-simbol yang berkaitan dengan kehidupan orang Melayu. Penggunaan kata-kata Melayu lama dan simbol Melayu memperkuat setting Melayu dalam sajak ini. Analisis makna menunjukkan bahwa seseorang merasakan kedukaan sangat mendalam ketika cintanya harus berakhir, tetapi ia terus merasakan kerinduan dengan kekasihnya yang telah pergi. Mitos cinta yang terdapat dalam pusinya adalah orang tahu bahwa putus cinta itu menyakitkan tetapi orang tetap saja jatuh cinta.

  4. Secondary organic aerosol formation from ambient air in an oxidation flow reactor in central Amazonia

    Science.gov (United States)

    Palm, Brett B.; de Sá, Suzane S.; Day, Douglas A.; Campuzano-Jost, Pedro; Hu, Weiwei; Seco, Roger; Sjostedt, Steven J.; Park, Jeong-Hoo; Guenther, Alex B.; Kim, Saewung; Brito, Joel; Wurm, Florian; Artaxo, Paulo; Thalman, Ryan; Wang, Jian; Yee, Lindsay D.; Wernis, Rebecca; Isaacman-VanWertz, Gabriel; Goldstein, Allen H.; Liu, Yingjun; Springston, Stephen R.; Souza, Rodrigo; Newburn, Matt K.; Lizabeth Alexander, M.; Martin, Scot T.; Jimenez, Jose L.

    2018-01-01

    Secondary organic aerosol (SOA) formation from ambient air was studied using an oxidation flow reactor (OFR) coupled to an aerosol mass spectrometer (AMS) during both the wet and dry seasons at the Observations and Modeling of the Green Ocean Amazon (GoAmazon2014/5) field campaign. Measurements were made at two sites downwind of the city of Manaus, Brazil. Ambient air was oxidized in the OFR using variable concentrations of either OH or O3, over ranges from hours to days (O3) or weeks (OH) of equivalent atmospheric aging. The amount of SOA formed in the OFR ranged from 0 to as much as 10 µg m-3, depending on the amount of SOA precursor gases in ambient air. Typically, more SOA was formed during nighttime than daytime, and more from OH than from O3 oxidation. SOA yields of individual organic precursors under OFR conditions were measured by standard addition into ambient air and were confirmed to be consistent with published environmental chamber-derived SOA yields. Positive matrix factorization of organic aerosol (OA) after OH oxidation showed formation of typical oxidized OA factors and a loss of primary OA factors as OH aging increased. After OH oxidation in the OFR, the hygroscopicity of the OA increased with increasing elemental O : C up to O : C ˜ 1.0, and then decreased as O : C increased further. Possible reasons for this decrease are discussed. The measured SOA formation was compared to the amount predicted from the concentrations of measured ambient SOA precursors and their SOA yields. While measured ambient precursors were sufficient to explain the amount of SOA formed from O3, they could only explain 10-50 % of the SOA formed from OH. This is consistent with previous OFR studies, which showed that typically unmeasured semivolatile and intermediate volatility gases (that tend to lack C = C bonds) are present in ambient air and can explain such additional SOA formation. To investigate the sources of the unmeasured SOA-forming gases during this campaign

  5. Secondary organic aerosol formation from ambient air in an oxidation flow reactor in central Amazonia

    Directory of Open Access Journals (Sweden)

    B. B. Palm

    2018-01-01

    Full Text Available Secondary organic aerosol (SOA formation from ambient air was studied using an oxidation flow reactor (OFR coupled to an aerosol mass spectrometer (AMS during both the wet and dry seasons at the Observations and Modeling of the Green Ocean Amazon (GoAmazon2014/5 field campaign. Measurements were made at two sites downwind of the city of Manaus, Brazil. Ambient air was oxidized in the OFR using variable concentrations of either OH or O3, over ranges from hours to days (O3 or weeks (OH of equivalent atmospheric aging. The amount of SOA formed in the OFR ranged from 0 to as much as 10 µg m−3, depending on the amount of SOA precursor gases in ambient air. Typically, more SOA was formed during nighttime than daytime, and more from OH than from O3 oxidation. SOA yields of individual organic precursors under OFR conditions were measured by standard addition into ambient air and were confirmed to be consistent with published environmental chamber-derived SOA yields. Positive matrix factorization of organic aerosol (OA after OH oxidation showed formation of typical oxidized OA factors and a loss of primary OA factors as OH aging increased. After OH oxidation in the OFR, the hygroscopicity of the OA increased with increasing elemental O : C up to O : C ∼ 1.0, and then decreased as O : C increased further. Possible reasons for this decrease are discussed. The measured SOA formation was compared to the amount predicted from the concentrations of measured ambient SOA precursors and their SOA yields. While measured ambient precursors were sufficient to explain the amount of SOA formed from O3, they could only explain 10–50 % of the SOA formed from OH. This is consistent with previous OFR studies, which showed that typically unmeasured semivolatile and intermediate volatility gases (that tend to lack C = C bonds are present in ambient air and can explain such additional SOA formation. To investigate the sources of the

  6. Analisis Industri Ritel Di Indonesia

    OpenAIRE

    Soliha, Euis

    2008-01-01

    This article presents an overview the analisys of retail industry in Indonesia.Retail industry in Indonesia grow rapidly. Industrial presence of modern retailbasically exploits public shopping pattern especially middle-weight and to which donot want to mill around in traditional market. Analysis Five Forces is used toanalysis retail industry. Analysis five force is bargaining power of buyers,bargaining power of suppliers, threat of new entrants, threat of new substituteproducts, and rivalry a...

  7. 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)

  8. ANALISIS POSITIONING RESTORAN CEPAT SAJI

    Directory of Open Access Journals (Sweden)

    Osa Omar Sharif

    2017-04-01

    Full Text Available Penelitian ini bertujuan untuk meneliti positioning restoran cepat saji McDonald's, Kentucky Fried Chicken, California Fried Chicken, A&W, dan Texas Chicken. Penelitian dilakukan di Kota Bandung dengan mengambil sebanyak 400 responden. Analisis yang digunakan dalam penelitian ini adalah analisis multidimensional scaling, analisis memberikan gambaran positioning dari restoran cepat saji yang ditampilkan dalam perceptual map. Restoran cepat saji yang memiliki layanan paling baik adalah McD dan yang memiliki layanan paling buruk adalah CFC. Restoran cepat saji yang memiliki rasa makanan paling enak adalah McD dan yang memiliki rasa makanan tidak enak adalah CFC. KFC dinilai paling ideal karena selalu berhasil menduduki peringkat satu dan dua jika dilihat dari sudut pandang restoran cepat saji yang lain. Pesaing terdekat McD adalah KFC. McD mendapatkan ranking pertama dari segi atribut layanan, kebersihan, variasi makanan, dan rasa makanan. Dengan posisi seperti ini McD seharusnya tetap menjaga kualitas layanan, kebersihan, variasi makanan, dan rasa makanan agar konsumen tetap memilih untuk datang ke McD. KFC sebaiknya tetap menjaga suasana yang membuat konsumen nyaman akan suasana di dalam atau diluar restoran

  9. Final results of the cadmium and spectral ratios obtained inside of the fuel rod positioned in the central position of the IPEN/MB-01 nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bitelli, Ulysses d' Utra; Mura, Luiz Ernesto C.; Santos, Diogo Feliciano dos, E-mail: ubitelli@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Lambiasi, Beatriz G.N. [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

    2015-07-01

    The spectral ratios are very important to determine some nuclear reactors parameters such as reaction rates, fuel lifetime, etc and some safety operational conditions. This study aims to determine the spectral ratios in 2 (two) spatial positions located inside the core of the Nuclear Reactor IPEN/MB-01. These places are at the central position of the nuclear reactor core in an asymptotic neutron flux region. The experiment consists in inserting different activation foil detectors inside an experimental fuel rod. The experimental rod is assembled at the central position of the reactor core. Activation neutron foil detectors of different elements such as {sup 197}Au, {sup 238}U, {sup 45}Sc, {sup 58}Ni, {sup 24}Mg, {sup 47}Ti and {sup 115m}In were used to cover a large range of neutron spectrum. Saturation activity per target nucleus was obtained by gamma spectrometry using a HPGe system. The experimental cadmium ratios compared with values computed by MCNP-4C code show good agreement. (author)

  10. ANALISIS PERBAIKAN SISTEM PENTANAHAN TELEKOMUNIKASI

    Directory of Open Access Journals (Sweden)

    Umar Umar

    2015-04-01

    Hasil dari penelitian ini adalah perbaikan sistem pentanahan site Kampung Baru dengan menggunakan konfigurasi single point connection window (SPCW, untuk mengamankan sistem telekomunikasi dari kebocoran arus dan petir serta imbasnya.  Perbaikan sistem pentanahan di site Kampung Baru menggunakan banyak elektroda yang membentuk persegi dikarenakan topografi tempat di sana yang memungkinkan dan efektif adalah menggunakan sistem tersebut. Berdasarkan hasil analisis dan perhitungan perbaikan sistem di site Kampung Baru, didapatkan nilai perhitungan sistem pentanahan adalah 1.34 Ohm serta pengukurannya 1.21-1.25 Ohm.

  11. Interaction of CREDO [Centralized Reliability Data Organization] with the EBR-II [Experimental Breeder Reactor II] PRA [probabilistic risk assessment] development

    International Nuclear Information System (INIS)

    Smith, M.S.; Ragland, W.A.

    1989-01-01

    The National Academy of Sciences review of US Department of Energy (DOE) class 1 reactors recommended that the Experimental Breeder Reactor II (EBR-II), operated by Argonne National Laboratory (ANL), develop a level 1 probabilistic risk assessment (PRA) and make provisions for level 2 and level 3 PRAs based on the results of the level 1 PRA. The PRA analysis group at ANL will utilize the Centralized Reliability Data Organization (CREDO) at Oak Ridge National Laboratory to support the PRA data needs. CREDO contains many years of empirical liquid-metal reactor component data from EBR-II. CREDO is a mutual data- and cost-sharing system sponsored by DOE and the Power Reactor and Nuclear Fuels Development Corporation of Japan. CREDO is a component based data system; data are collected on components that are liquid-metal specific, associated with a liquid-metal environment, contained in systems that interface with liquid-metal environments, or are safety related for use in reliability/availability/maintainability (RAM) analyses of advanced reactors. The links between the EBR-II PRA development effort and the CREDO data collection at EBR-II extend beyond the sharing of data. The PRA provides a measure of the relative contribution to risk of the various components. This information can be used to prioritize future CREDO data collection activities at EBR-II and other sites

  12. Semiotika Teks: Sebuah Pendekatan Analisis Teks

    Directory of Open Access Journals (Sweden)

    Yasraf Amir Piliang

    2004-12-01

    tanda-tanda yang membentuk apa yang disebut sebagai ‘teks’. Analisis teks, menurut Roland Barthes, akan menghasilkan makna denotatif, yakni makna tanda yang bersifat eksplisit, dan makna konotatif, yaitu makna tanda lapis kedua yang bersifat implisit.

  13. Risk analysis; Analisis de riesgos

    Energy Technology Data Exchange (ETDEWEB)

    Baron, J H; Nunez McLeod, J; Rivera, S S [Universidad Nacional de Cuyo, Mendoza (Argentina). Instituto de Capacitacion Especial y Desarrollo de Ingenieria Asistida por Computadora (CEDIAC)

    1997-07-01

    This book contains a selection of research works performed in the CEDIAC Institute (Cuyo National University) in the area of Risk Analysis, with specific orientations to the subjects of uncertainty and sensitivity studies, software reliability, severe accident modeling, etc. This volume presents important material for all those researches who want to have an insight in the risk analysis field, as a tool to solution several problems frequently found in the engineering and applied sciences field, as well as for the academic teachers who want to keep up to date, including the new developments and improvements continuously arising in this field. [Spanish] Este libro contiene una seleccion de trabajos de investigacion realizados dentro del Instituto de Capacitacion Especial y Desarrollo de la Ingenieria Asistida por Computadora en el area del analisis de riesgos, con una orientacion hacia el estudio de incertidumbres y sensibilidad, confiabilidad de software, modelacion de accidentes severos, etc. Este volumen recoge un material de indudable importancia e interes para todos aquellos investigadores y profesionales que desean incursionar en este campo del analisis de riesgos como herramienta para la solucion de problemas frecuentemente encontrados en la ingenieria y las ciencias aplicadas, asi como para los academicos que desean mantenerse al dia, conociendo los nuevos desarrollos y tecnicas que constantemente aparecen en su area.

  14. Analisis Kebijakan dan Efektivitas Organisasi

    Directory of Open Access Journals (Sweden)

    Amir Syarifudin Kiwang

    2015-05-01

    Full Text Available Penerapan Peraturan Gubernur Nusa Tenggara Timur Nomor 8 Tahun 2011 tentang Organisasi dan Tata Kerja Unit Pelaksana Teknis Pendidikan dan Pelatihan Koperasi dan Usaha Mikro Kecil dan Menengah pada Dinas Koperasi dan Usaha Mikro Kecil dan Menengah Provinsi Nusa Tenggara Timur adalah dalam rangka untuk meningkatkan efektivitas kerja organisasi pada UPT Diklat Koperasi dan UMKM. Penelitian ini berusaha untuk melihat dampak kebijakan organisasi terhadap efektivitas organisasi dengan menggunakan enam elemen variabel dari kebijakan dan praktik manajemen. Keenam elemen tersebut adalah penetapan tujuan strategis, pencarian dan pemanfaatan sumber daya, lingkungan prestasi, proses komunikasi, kepemimpinan dan pengambilan keputusan, serta adaptasi dan inovasi organisasi. Penelitian kualitatif ini menggunakan pendekatan studi kasus. Teknik analisis data yang digunakan adalah analisis data model Miles dan Huberman, yang terdiri atas reduksi data, display/penyajian data, dan kesimpulan/verifikasi. Hasil penelitian menunjukkan bahwa efektivitas organisasi pada UPT Diklat koperasi dan UMKM belum berjalan secara baik, hal ini dapat dilihat dari beberapa hal antara lain, belum adanya tenaga spesialisasi pengelola diklat dan tenaga khusus (sarjana di bidang perkoperasian dan kondisi lingkungan kerja (lingkungan prestasi pada UPT Diklat koperasi dan UMKM yang belum efektif. Penempatan pegawai juga belum tepat, mutasi ke UPT Diklat Koperasi dan UMKM tidak memperhatikan latar belakang pendidikan dan spesialisasi/keahlian pegawai sehingga membutuhkan waktu dalam proses penyesuaian serta menurunkan jumlah pelaksanaan diklat dikarenakan keterbatasan alokasi dana.

  15. ANALISIS DAYA SAING KEDELAI INDONESIA

    Directory of Open Access Journals (Sweden)

    Sarwono Sarwono

    2014-09-01

    Full Text Available RCA (Revealed Comparative Advantage index of soybean in Indonesia from 1983 up to 2013 is less than one, mostly. It means that the competitiveness of soybean in Indonesia is low. The purpose of this study is to analyze the factors influence the soybean competitiveness. OLS (Ordinary Least Square was used as the analysis method. Hypotheses test based on that analysis model is not bias, so that, classic divergence test is needed. It is for getting the Best Linier Unbiased Estimator (BLUE appraisal. T statistic and F statistic were also applied. The result of this research shows that production and export have positive and significant influence. In addition, exchange rate and government policy do not influence the Indonesia soybean competitiveness.Indeks RCA (Revealed Comparative Advantage kedelai Indonesia dari tahun 1983-2013 kecenderungan bernilai kurang dari satu yang berarti daya saing kedelai Indonesia rendah.Penelitian ini bertujuan untuk menganalisis faktor-faktor yang mempengaruhi daya saing kedelai Indonesia.Metode analisis yang digunakan adalah Ordinary Least Square (OLS.Pengujian hipotesis berdasarkan model analisis tersebut tidak bias maka perlu dilakukan uji penyimpangan klasik yang tujuannya agar diperoleh penaksiran yang bersifat Best Linier Unbiased Estimator (BLUE.Pengujian statistik menggunakan uji t statistikdan uji f statistik.Hasil penelitian ini menunjukkan bahwa produksi dan ekspor berpengaruh secara positif dan signifikan terhadap daya saing kedelai Indonesia. Nilai tukar rupiah dan kebijakan pemerintah tidak berpengaruh terhadap daya saing kedelai Indonesia.

  16. Analisis Harmonisa Inverter PWM Satu Fasa

    OpenAIRE

    Rejeki Simanjorang

    2008-01-01

    Pada tesis ini dianalisis harmonisa inverter PWM satu fasa. Inverter PWM satu fasa yang akan ditinjau adalah inverter satu fasa jembatan penuh (konvensional) dan inverter komposit. Analisis difokuskan pada penentuan pola penyaklaran yang optimum agar pembangkitan harmonisa dan switching losses inverter rendah. Untuk menentukan pola penyaklaran optimum maka dilakukan analisis yang berbasis pada rangkaian ekivalen harmonisa inverter satu fasa. Dengan menggunakan pola penyaklaran optimum, kedua ...

  17. 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

  18. Preliminary analysis of the inclusion of security passive systems to reduce the impact of accidents in nuclear power plants; Analisis preliminar de la inclusion de sistemas pasivos de seguridad para reducir el impacto de accidentes en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez J, J.; Morales S, J. B. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Espinosa P, G., E-mail: jersonsanchez@gmail.com [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (MX)

    2011-11-15

    In this work is presented a conceptual analysis of possible benefits and limitations that potentially represents the introduction of security passive systems to reduce the events impact of very low probability and high risk to the systems of radioactive material confinement of a light water reactor. These events are related with the possibility that a hydrogen explosion is presented as consequence of the accumulation of the same hydrogen in the contention of the reactor, in a scenario of severe accident. This accumulated hydrogen can be liberated in the reactor building or primary contention, where the conditions of their atmosphere make but prone the combustion. The catalytic recombination represents a viable option for the hydrogen concentrations decrease and because this recombination is highly exothermic, is important to analyze and to know if the recombined vapor to high temperature can be used in combination with vapor injectors that in turn, they are passive systems. In the following sections an explanation is presented about the use of the mentioned systems, as well as some results on the behavior of the vapor injectors. (Author)

  19. ANALISIS IMPOR BERAS DI INDONESIA

    Directory of Open Access Journals (Sweden)

    Ratih Kumala Sari

    2014-10-01

    Full Text Available Abstrak ___________________________________________________________________ Salah satu kebijakan pemerintah untuk memenuhi kebutuhan beras yaitu dengan menggenjot produksi beras dalam negeri. Namun dengan semakin meningkatnya jumlah penduduk akan meningkatkan permintaan terhadap beras dan upaya peningkatan produktivitas dalam negeri tidak dapat memenuhi kebutuhan beras dalam negeri. Sehingga untuk menutupi kekurangan tersebut pemerintah mengambil keputusan untuk melakukan impor beras dari negara lain. Akan tetapi pada kenyataannya impor beras dilakukan ketika data statistik menunjukkan bahwa Indonesia sedang mengalami surplus beras. Penelitian ini bertujuan untuk mengetahui faktor-faktor apa saja yang mempengaruhi impor beras di Indonesia. Metode analisis yang digunakan adalah analisis regresi linier berganda dengan model Error Correction Model (ECM. Berdasarkan hasil penelitian disimpulkan bahwa secara parsial maupun secara bersama-sama produksi beras, konsumsi beras, harga beras dalam negeri dan nilai tukar rupiah terhadap dollar AS berpengaruh dan signifikan terhadap impor beras di Indonesia. Abstract ___________________________________________________________________ One of the government’s policy to fulfill the need of rice is to boost the domestic production. However, by increasing the population, the demand of rice will also increase and the effort of increasing the domestic productivity cannot supply domestic rice need. So, to cover the shortage the government make decision to import rice from other countries. Yet, in fact importing rice is occurred when the statistical data showed that the supply of rice in Indonesia is surplus. The purpose of this research is necessary to study the factors which influence the import of rice in Indonesia. The analysis method used is multiple linear regression analysis model with Error Correction Model (ECM. Based on the research proven that partially or jointly the production, the consumption, the

  20. Spectrographic Determination of Impurities in Ceramic Materials for Nuclear Fusion Reactors. I. Analysis of Alumina; Determinacion Espectrografica de impurezas en materiales ceramicos para fusion nuclear. I.- Analisis de alumina

    Energy Technology Data Exchange (ETDEWEB)

    Rucandio, M I; Roca, M; Melon, A

    1990-07-01

    The determination of minor and trace elements in the aluminium oxide considered as possible ceramic material in thermonuclear fusion reactors has been studied. The concentration ranges are 0.1 - 0.3 * for Ca, Si and Y, and at the ppm level for Co, Cr, Fe, Hf, K, Li, Mg, Mn, Na, Ni, Se, Ta, Ti, V and Zr. Atomic emission spectroscopy with direct current ore excitation and photographic detection has been employed. For Hf, Mg, Ta, Ti, V and Zr the use of 40% of copper fluoride as a carrier and of Nb as lnternal standard provide suitable sensitivities and precessions, while for the rest of elements the bent results are obtained with graphite powder in different proportions and Rb or Sn as internal standard. (Author) 7 refs.

  1. Spectrographic Determination of Impurities in Ceramic Materials for Nuclear fusion Reactors. II. Analysis of Magnesium Aluminate; Determinacion Espectrografia de Impurezas en materiales Ceramicos para Fusion Nuclear. II. Analisis de Aluminato de Magnesio

    Energy Technology Data Exchange (ETDEWEB)

    Rucandio, M I; Roca, M; Melon, A

    1990-07-01

    The determination of minor and trace elements in the magnesium aluminate, considered as possible material in thermonuclear fusion reactors, has been studied. The concentration ranges are 0.1 - 0.3 % for Ca, SI and Y, and at the ppm level for Co, Cr, Fe, Hf, K, Li, Mn, Na, Ni, Se, Ta, Ti, V and Zr. Atomic emission spectroscopy with direct current are excitation and photographic detection has been employed. For Hf, Ta and Zr the use of 40% of copper fluoride as a carrier and of Nb as internal standard provide suitable sensitivities and precessions, while for the rest of elements the best results are obtained with graphite powder in different proportions and Rb or Sn as internal standard. (Author)4 refs.

  2. 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)

  3. 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)

  4. Analysis of the noise of the jet pumps of the Unit 2 of the Laguna Verde nuclear power plant; Analisis de ruido de las bombas de chorro de la Unidad 2 de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Castillo D, R.; Ortiz V, J.; Ruiz E, J.A. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Calleros M, G. [CFE, Central Nucleoelectrica de Laguna Verde, Alto Lucero, Veracruz (Mexico)]. E-mail: rcd@nuclear.inin-mx

    2004-07-01

    The use of the analysis of noise for the detection of badly functioning of the components of a BWR it is a powerful tool in the determination of abnormal conditions of operation, during the life of a nuclear plant of power. From the eighties, some nuclear reactors have presented problems related with the jet pumps and the knots of the recirculation. The Regulatory Commission of the United States, in the I E bulletin 80-07, recommended to carry out a periodic supervision of the pressure drop of the jet pumps, to prevent structural failures. In this work, methods of analysis of noise are used for the detection of abnormal conditions of operation of the jet pumps of a BWR. Signals are analysed to low and high frequency of pressure drop with the NOISE software that is in development. The obtained results show the behavior of the jet pumps of jet 6 and 11 before and after a partial blockade in their throats where the pump 6 return to their condition of previous operation and the pump 11 present a new fall of pressure, inside the limit them permissible of operation. The methodology of the analysis of noise demonstrated to be an useful tool for the badly functioning detection, and you could apply to create a database to supervise the dynamic behavior of the jet pumps of an BWR. (Author)

  5. Analisis Value Chain Di Industri Otomotif

    OpenAIRE

    Hendri, Hendri

    2017-01-01

    Penelitian ini untuk menganalisis industri otomotif. Tujuan dari penelitian ini adalah untuk menganalisis dan mengetahui aktivitas dan kondisi internal proses industri manufaktur dengan menggunakan value chain guna masukan dimasa akan datang bagi industri otomotif secara khusus. Value Chain merupakan rantai nilai yang dapat mengetahui kekuatan Perusahaan, keuntungan dan kesuksesan dari rantai aktivitas dalam Perusahaan atau industri manufaktur.Metode analisis menggunakan Statistika Deskript...

  6. Optimization of the Co-Digestion of Catch Crops with Manure Using a Central Composite Design and Reactor Operation

    DEFF Research Database (Denmark)

    Molinuevo-Salces, Beatriz; Ahring, Birgitte Kiær; Uellendahl, Hinrich

    2015-01-01

    , an improvement of 1.46 times compared to manure alone. Adaptation to OSR was observed, and no ammonia or volatile fatty acid-mediated inhibition was detected. The results prove that it is feasible to use catch crops as co-substrate for manure-based biogas production, obtaining a stable process with significantly...... CH4/g volatile solids (VS) were obtained for OSR and IR in co-digestion, respectively. OSR co-digestion was chosen for semi-continuous reactor experiments. The addition of 50 % of OSR to manure (on VS basis) in semi-continuous anaerobic digestion resulted in a methane yield of 348 ml CH4/g VS...

  7. Power Nuclear Reactors: technology and innovation for development in future; Centrales Nucleares de Potencia: tecnologias actuales e innovaciones para el futuro

    Energy Technology Data Exchange (ETDEWEB)

    Suarez Antola, R [Universidad Catolica del Uruguay, Montevideo(Uruguay); Ministerio de Industria Energia y Minerria, Montevideo(Uruguay)

    2009-07-01

    The conference is about some historicals task of the fission technology as well as many types of Nuclear Reactors. Enrichment of fuel, wastes, research reactors and power reactors, a brief advertisment about Uruguay electric siystem and power generation, energetic worldwide, proliferation, safety reactors, incidents, accidents, Three-Mile Island accident, Chernobil accident, damages, risks, classification and description of Power reactors steam generation, nuclear reactor cooling systems, future view.

  8. Nuclear policies in Central Europe. Environmental policy and enlargement of the European Union: Austria's policies towards Nuclear Reactors in neighboring countries

    International Nuclear Information System (INIS)

    Getzner, M.

    2003-01-01

    Austria's anti-nuclear policies are rooted in the successful anti-nuclear referendum on the Zwentendorf nuclear power plant (Lower Austria) in 1978 and the great impact of the Chernobyl catastrophe on Austria in 1986. Since about 1990, official Austria has pursued anti-nuclear policies not only at home but also abroad. In particular, reactors in Central and Eastern European Countries (CEEC) are the focal points of Austria's foreign anti-nuclear policies. Strategies include increasing nuclear safety, promoting energy efficiency and sustainable energy sources (such as renewable resources), and extending international legal frameworks to account for nuclear safety. Involvement in domestic energy issues in other countries is not an easy task, and while Austrian policy makers have had some success in increasing awareness of nuclear safety in Europe, they have also made a number of strategic mistakes. Notwithstanding real and substantiated concerns regarding nuclear safety, Austrian policies have lost credibility during recent years. This book explores the history and the development of Austrian anti-nuclear policies, and discusses the political economy of such policies. Particular emphasis is laid on the 2002 referendum against the Temelin reactor in the neighboring Czech Republic. (orig.)

  9. Reactor core and initially loaded reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

    In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

  10. Development of a numerical code for the analysis of the linear stability of the U1 and U2 reactors of the CNLV; Desarrollo de un codigo numerico para el analisis de estabilidad lineal de los reactores de las U1 y U2 de la CNLV

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa P, G.; Estrada P, C.E. [Universidad Autonoma Metropolitana-Iztapalapa, 09000 Mexico D.F. (Mexico); Nunez C, A.; Amador G, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico)

    2001-07-01

    The computer code ANESLI-1 developed by the CNSNS and UAM-I, has the main goal of making stability analysis of nuclear reactors of the BWR type, more specifically, the reactors of the U1 and U2 of the CNLV. However it can be used for another kind of applications. Its capacity of real time simulator, allows the prediction of operational transients, and conditions of dynamic steady states. ANESLI-1 was developed under a modular scheme, which allows to extend or/and to improve its scope. The lineal stability analysis predicts the instabilities produced by the wave density phenomenon. (Author)

  11. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  12. Analisis Kinerja Local Area Network Menggunakan Router.

    OpenAIRE

    Hutahaean, Yosua

    2012-01-01

    Perangkat internetworking menawarkan komunikasi di antara segmen Local Area Network (LAN). Ada empat tipe utama perangkat internetworking ini: repeater, bridge, router, dan gateway. Perangkat ini dibedakan atas dasar system lapisan Open System Interconnection (OSI) yang digunakan, berfungsi sebagai media komunikasi dari LAN ke LAN. Pada Tugas Akhir ini penulis tertarik untuk membahas analisis kinerja Local Area Network (LAN) menggunakan Router yang menggunakan sistem antrian M/M/1 dimana j...

  13. ANALISIS KONDISI TERAS REAKTOR DAYA MAJU AP1000 PADA KECELAKAAN SMALL BREAK LOCA

    Directory of Open Access Journals (Sweden)

    Andi Sofrany Ekariansyah

    2015-06-01

    Full Text Available ABSTRAK ANALISIS KONDISI TERAS REAKTOR DAYA MAJU AP1000 PADA KECELAKAAN SMALL BREAK LOCA. Kecelakaan yang diakibatkan oleh kehilangan pendingin (loss of coolant accident / LOCA dari sistem reaktor merupakan kejadian dasar desain yang tetap diantisipasi dalam desain reaktor daya yang mengadopsi teknologi Generasi II hingga IV. LOCA ukuran kecil (small break LOCA memiliki dampak yang lebih signifikan terhadap keselamatan dibandingkan LOCA ukuran besar (large break LOCA seperti terlihat pada kejadian Three-Mile Island (TMI. Fokus makalah adalah pada analisis small break LOCA pada reaktor daya maju Generasi III+ yaitu AP1000 dengan mensimulasikan tiga kejadian pemicu yaitu membukanya katup Automatic Depressurization System (ADS secara tak disengaja, putusnya salah satu pipa Direct Vessel Injection (DVI secara double-ended, dan putusnya pipa lengan dingin dengan diameter bocoran 10 inci. Metode yang digunakan adalah simulasi kejadian pada model AP1000 yang dikembangkan secara mandiri menggunakan program perhitungan RELAP5/SCDAP/Mod3.4. Dampak yang ingin dilihat adalah kondisi teras selama terjadinya small break LOCA yang terdiri dari pembentukan mixture level dan transien temperatur kelongsong bahan bakar. Hasil simulasi menunjukkan bahwa mixture level untuk semua kejadian small break LOCA berada di atas tinggi teras aktif yang menunjukkan tidak terjadinya core uncovery. Adanya mixture level berpengaruh pada transien temperatur kelongsong yang menurun dan menunjukkan pendinginan bahan bakar yang efektif. Hasil di atas juga identik dengan hasil perhitungan program lain yaitu NOTRUMP. Keefektifan pendinginan teras juga disebabkan oleh berfungsinya injeksi pendingin melalui fitur keselamatan pasif yang menjadi ciri reaktor daya AP1000. Secara keseluruhan, hasil analisis menunjukkan model AP1000 yang telah dikembangkan dengan RELAP5 dapat digunakan untuk keperluan analisis kecelakaan dasar desain pada reaktor daya maju AP1000. Kata kunci: analisis

  14. ANALISIS SKENARIO KEGAGALAN SISTEM UNTUK MENENTUKAN PROBABILITAS KECELAKAAN PARAH AP1000

    Directory of Open Access Journals (Sweden)

    D.T. Sony Tjahyani

    2014-03-01

    Full Text Available Kejadian Fukushima telah menunjukkan bahwa kecelakaan parah dapat terjadi, maka dari itu sangatlah penting untuk menganalisis tingkat keselamatan pada reaktor daya. Berdasarkan rekomendasi expert mission IAEA setelah kejadian Fukushima, perlu dilakukan upaya untuk meminimalisasi terjadinya kecelakaan parah yaitu dengan melakukan proses pendinginan yang maksimal. Dalam konsep keselamatan fasilitas nuklir, khususnya reaktor daya telah diterapkan konsep keselamatan berlapis (Defence in Depth, DiD. Konsep keselamatan tersebut terdiri atas 5 level pertahanan yang bertujuan mencegah dan mengurangi lepasan produk fisi ke masyarakat dan lingkungan pada saat reaktor daya mengalami kecelakaan. Dalam reaktor telah didesain sistem atau tindakan yang mempunyai fungsi untuk mengatasi setiap level tersebut. Tujuan dari analisis ini adalah menentukan probabilitas kecelakaan parah dengan melakukan skenario kegagalan sistem dalam proses pendinginan di reaktor. Sebagai obyek analisis adalah reaktor daya AP1000, karena jenis reaktor ini sedang banyak dibangun saat ini. Skenario dilakukan dengan mengasumsikan beberapa kombinasi kegagalan sistem yang termasuk dalam DiD level 2 dan 3. Kegagalan sistem kemudian dianalisis dengan menggunakan analisis pohon kegagalan berdasarkan perangkat lunak SAPHIRE ver. 6.76. Dari analisis didapatkan probabilitas gagal dari kelompok sistem DiD level 2 dan 3 pada AP1000 masih di bawah batas kriteria dari IAEA yaitu lebih kecil dari 10-2, serta probabilitas kecelakaan parah didapatkan sebesar 6,17 x 10-10. Berdasarkan analisis ini disimpulkan bahwa AP1000 mempunyai tingkat keselamatan yang cukup tinggi, karena melalui skenario kegagalan sistem didapatkan probabilitas kecelakaan parah yang sangat kecil.   ABSTRACT Fukushima accident has shown that severe accident could be occurred, therefore it is important to analyze safety level of nuclear power plants. Based on the recommendations of IAEA expert mission after the Fukushima accident

  15. Preliminary risk analysis of an Hydrogen production plant using the reformed process of methane with vapor coupled to a high temperature nuclear reactor; Analisis preliminar de riesgo de una planta de produccion de hidrogeno utilizando el proceso de reformado de metano con vapor acoplada a un reactor nuclear de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Flores y Flores, A. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: alain_fyf@yahoo.com; Nelson E, P.F.; Francois L, J.L. [Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2004-07-01

    It is necessary to identify the different types of dangers, as well as their causes, probabilities and consequences of the same ones, inside plants, industries and any process to classify the risks. This work is focused in particular to a study using the technical HAZOP (Hazard and Operability) for a plant of reformed of methane with vapor coupled to a nuclear reactor of the type HTTR (High Temperature Test Reactor), which is designed to be built in Japan. In particular in this study the interaction is analyzed between the nuclear reactor and the plant of reformed of methane with vapor. After knowing the possible causes of risk one it is built chart of results of HAZOP to have a better vision of the consequences of this faults toward the buildings and constructions, to people and the influence of the fault on each plant; for what there are proposed solutions to mitigate these consequences or to avoid them. The work is divided in three sections: a brief introduction about the technique of HAZOP; some important aspects of the plant of reformed of methane with vapor; and the construction of the chart of results of HAZOP. (Author)

  16. Neutron activation analysis and activity in the vessel steel of a BWR reactor for their study without radiological risks in microscopy and spectrometry; Analisis de activacion neutronica y actividad en el acero de la vasija de un reactor nuclear tipo BWR para su estudio sin riesgos radiologicos en microscopia y espectrometria

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel, M.; Garcia B, A. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Fisica, Unidad Profesional Adolfo Lopez Mateos, Zacatenco, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: mmoranchel@ipn.mx [IAEA, Department of Technical Cooperation, Division for Latin America, Room B1109 Wagramerstrasse 5, PO Box 100, A-1400, Vienna (Austria)

    2012-07-01

    The vessel material of nuclear reactors is subject to irradiation damage induced by the bombardment of neutrons coming from the reactor core. Neutrons are classified as fast and thermal, which produce different effects. Fast neutrons cause damage to the material by dislocation or displacement of atoms in the crystal structure, while the effect of thermal neutrons is a nuclear transmutation that can significantly change the properties of the material. The type and intensity of damage is based on the characteristics of the material, the flow of neutrons and the modes of neutrons interaction with the atomic structures of the material, among others. This work, alluding to nuclear transmutation, makes an analysis of neutron activation of all isotopes in a steel boiling water nuclear reactor (BWR) vessel. An analytical expression is obtained in order to model activity of steel, on the basis of the weight percentage of its atomic components. Its activity is theoretically estimated in a witness sample of the same material as that of the vessel, placed within the nuclear reactor since the beginning of its commercial operation in April 1995, up to August 2010. It was theoretically determined that the witness sample, with a 0.56 g mass (1 x 1 x 0.07 cm{sup 3} dimensions or equivalent) does not present a radiological risks during the stage of preparation, observation and analysis of it in electron microscopy and X-ray diffraction equipment s. The theoretical results were checked experimentally by measuring the activity of the sample by means of gamma spectrometry, measurement of the exposure levels around the sample, as well as the induced level to whole body and limbs, using thermo-luminescent dosimetry (TLD). As a result of the theoretical analysis, new chemical elements are predicted, as a result of the activation phenomena and radioactive decay, whose presence can be a fundamental factor of change in the properties of the vessel. This work is a preamble to the

  17. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  18. Analysis of the microstructural evolution of the damage by neutron irradiation in the pressure vessel of a nuclear power reactor BWR; Analisis de la evolucion microestructural del dano por irradiacion neutronica en la vasija de presion de un reactor nuclear de potencia BWR

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y R, M.

    2012-07-01

    Nuclear reactor pressure vessel type BWR, installed in Mexico and in many other countries, are made of an alloy of low carbon steel. The American Society for Testing and Materials (Astm) classifies this alloy as A533-B, class 1. Both the vessel and other internal structures are continuously exposed to the neutron flux from the reactions of fission in nuclear fuel. A large number of neutrons reach the vessel and penetrate certain depth depending on their energy. Its penetration in the neutron collides with the nuclei of the atoms out of their positions in the crystal lattice of steel, producing vacancies, interstitial, segregations, among other defects, capable of affecting its mechanical properties. Analyze the micro-structural damage to the vessel due to neutron irradiation, is essential for reasons of integrity of this enclosure and safety of any nuclear power plant. The objective of this thesis work is theoretical and experimentally determine the microstructural damage of a type nuclear reactor vessel steel BWR, due to neutron radiation from the reactor core, using microscopic and spectroscopic techniques as well as Monte Carlo simulation. Microscopy Optical, Scanning Electron Microscopy, Transmission Electron Microscopy, Energy Dispersion of X-rays Spectrometry and X-rays Diffractometry were the techniques used in this research. These techniques helped in the characterization of both the basis of design of pressure vessel steel and steel irradiated, after eight years of neutron irradiation on the vessel, allowing know the surface morphology and crystal structures of the previous steel and post-irradiation, analyze the change in the microstructure of the steel vessel, morphological damage to surface level in an irradiated sample, among which are cavities in the order of microns produced by Atomic displacements due to the impact of neutronic, above all in the first layers of thickness of the vessel, the effect of swelling, regions of greater damage and Atomic

  19. ANALISIS POSITIONINGLAYANAN BCA CABANG KUTA

    Directory of Open Access Journals (Sweden)

    Amen Wirajaya

    2013-10-01

    Full Text Available The aims of this study are investigating PT Bank Central Asia, Tbk. Kuta Branch positioning to its competitor in Bali;and superiority services of PT Bank Central Asia, Tbk. Kuta Branch based on customer perception and determining the best relevant marketing strategy for PT Bank Central Asia, Tbk. Kuta Branch to counter its  competitor.  The  data  will  be  analyzed  using  statistical  method  of  Multi  Dimensional  Scaling  and Correspondence analysis. The result of this study shows that BCA Kuta has similiarities with Mandiri, it means that Mandiri is the nearest competitor of BCA Kuta. BCA is superior in waiting time of teller services, ATM services, internet banking, and mobile banking.

  20. Study of instabilities in phase by using the tool {sup D}ynamics{sup :} analysis of the evolution space temporary of the waves of density in channels of reactors BWR; Estudio de las Inestabilidades en Fase Mediante la Herramienta Dinamics: analisis de la Evolucion Espacio Temporal de las Ondas de Densidad en Canales de Reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Munoz-Cobo, J. L.; Escriva, R.; Merino, R.; Melara, J.

    2013-07-01

    This paper presents the basics of Dynamics V2 to code It allows calculations of stability for oscillations in phase in BWR reactors in the time domain. The equations of the model are exposed and is the integration of the equations. The model can be used in a large number of nodes thrust for the calculations to an acceptable computational cost, it has simplified dynamics of recirculation loop and the code has been incorporated the Oscillation in phase boundary conditions. The code incorporates the equations of boiling sub-cooled which allows to make more realistic calculations as well as subroutines to calculate the subroutines-based properties of the MATPRO and ASME.

  1. ANALISIS PENGENDALIAN DAYA REAKTOR PCMSR DENGAN LAJU ALIR PENDINGIN

    Directory of Open Access Journals (Sweden)

    Iqbal Syafin Noha

    2015-03-01

    Full Text Available Passive Compact Molten Salt Reactor (PCMSR merupakan pengembangan dari Molten Salt Reactor (MSR yang memiliki karakter berbeda dengan lima reaktor generasi IV lainnya, yaitu menggunakan bahan bakar leburan garam. Pada reaktor MSR, garam lebur tidak digunakan sebagai pendingin tetapi digunakan sebagai medium pembawa bahan bakar. Dengan fase bahan bakar yang berupa garam lebur LiF-BeF2-ThF4-UF4, maka dapat dilakukan pengendalian daya dengan mengatur laju aliran bahan bakar dan pendingin. Tujuan penelitian ini adalah untuk mengetahui pengaruh perubahan laju alir pendingin terhadap daya reaktor PCMSR. Analisis dilakukan dengan empat jenis masukan untuk perubahan laju alir pendingin, yaitu masukan step, ramp, eksponensial, dan sinusoidal. Untuk masukan step, laju alir pendingin dibuat berubah secara mendadak. Selanjutnya untuk masukan ramp dan eksponensal, perubahan laju alir masing-masing dibuat perlahan secara linear dan mengikuti fungsi eksponensial. Kemudian untuk masukan sinusoidal, laju alir berubah naik turun secara periodik dengan memvariasikan frekuensi dari perubahan laju alir tersebut. Hasil penelitian menunjukkan bahwa penurunan laju alir pendingin sebesar 50% dari laju pendingin sebelumnya, menyebabkan daya pada reaktor PCMSR turun sebesar 63% dari daya sebelumnya. Jika terjadi fluktuasi laju aliran pendingin, maka semakin cepat perubahan tersebut, maka respon daya yang diberikan semakin kecil. Pada frekuensi yang sangat cepat, daya reaktor menjadi konstan dan cenderung tidak memiliki respon terhadap laju aliran. Hal ini merupakan salah satu aspek keselamatan reaktor, karena reaktor tidak merespon perubahan yang terlalu cepat. Kemampuan reaktor mengatur daya menyesuaikan laju aliran pendingin merupakan aspek keselamatan lainnya. Kata kunci : PCMSR, pengendalian daya, laju alir pendingin, uji respon   Passive Compact Molten Salt Reactor (PCMSR is the development of Molten Salt Reactor (MSR which has different character from other five

  2. Optimization of the pyrolysis process of empty fruit bunch (EFB) in a fixed-bed reactor through a central composite design (CCD)

    Science.gov (United States)

    Mohamed, Alina Rahayu; Hamzah, Zainab; Daud, Mohamed Zulkali Mohamed

    2014-07-01

    The production of crude palm oil from the processing of palm fresh fruit bunches in the palm oil mills in Malaysia hs resulted in a huge quantity of empty fruit bunch (EFB) accumulated. The EFB was used as a feedstock in the pyrolysis process using a fixed-bed reactor in the present study. The optimization of process parameters such as pyrolysis temperature (factor A), biomass particle size (factor B) and holding time (factor C) were investigated through Central Composite Design (CCD) using Stat-Ease Design Expert software version 7 with bio-oil yield considered as the response. Twenty experimental runs were conducted. The results were completely analyzed by Analysis of Variance (ANOVA). The model was statistically significant. All factors studied were significant with p-values oil from EFB pyrolysis process. A quadratic model equation was developed and employed to predict the highest theoretical bio-oil yield. The maximum bio-oil yield of 46.2 % was achieved at pyrolysis temperature of 442.15 °C using the EFB particle size of 866 μm which corresponded to the EFB particle size in the range of 710-1000 μm and holding time of 483 seconds.

  3. Optimization of the pyrolysis process of empty fruit bunch (EFB) in a fixed-bed reactor through a central composite design (CCD)

    International Nuclear Information System (INIS)

    Mohamed, Alina Rahayu; Hamzah, Zainab; Daud, Mohamed Zulkali Mohamed

    2014-01-01

    The production of crude palm oil from the processing of palm fresh fruit bunches in the palm oil mills in Malaysia hs resulted in a huge quantity of empty fruit bunch (EFB) accumulated. The EFB was used as a feedstock in the pyrolysis process using a fixed-bed reactor in the present study. The optimization of process parameters such as pyrolysis temperature (factor A), biomass particle size (factor B) and holding time (factor C) were investigated through Central Composite Design (CCD) using Stat-Ease Design Expert software version 7 with bio-oil yield considered as the response. Twenty experimental runs were conducted. The results were completely analyzed by Analysis of Variance (ANOVA). The model was statistically significant. All factors studied were significant with p-values 2 was 0.9564 which indicated that the selected factors and its levels showed high correlation to the production of bio-oil from EFB pyrolysis process. A quadratic model equation was developed and employed to predict the highest theoretical bio-oil yield. The maximum bio-oil yield of 46.2 % was achieved at pyrolysis temperature of 442.15 °C using the EFB particle size of 866 μm which corresponded to the EFB particle size in the range of 710–1000 μm and holding time of 483 seconds

  4. Statistical analysis in the design of nuclear fuel cells and training of a neural network to predict safety parameters for reactors BWR; Analisis estadistico en el diseno de celdas de combustible nuclear y entrenamiento de una red neuronal para predecir parametros de seguridad para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Jauregui Ch, V.

    2013-07-01

    In this work the obtained results for a statistical analysis are shown, with the purpose of studying the performance of the fuel lattice, taking into account the frequency of the pins that were used. For this objective, different statistical distributions were used; one approximately to normal, another type X{sup 2} but in an inverse form and a random distribution. Also, the prediction of some parameters of the nuclear reactor in a fuel reload was made through a neuronal network, which was trained. The statistical analysis was made using the parameters of the fuel lattice, which was generated through three heuristic techniques: Ant Colony Optimization System, Neuronal Networks and a hybrid among Scatter Search and Path Re linking. The behavior of the local power peak factor was revised in the fuel lattice with the use of different frequencies of enrichment uranium pines, using the three techniques mentioned before, in the same way the infinite multiplication factor of neutrons was analyzed (k..), to determine within what range this factor in the reactor is. Taking into account all the information, which was obtained through the statistical analysis, a neuronal network was trained; that will help to predict the behavior of some parameters of the nuclear reactor, considering a fixed fuel reload with their respective control rods pattern. In the same way, the quality of the training was evaluated using different fuel lattices. The neuronal network learned to predict the next parameters: Shutdown Margin (SDM), the pin burn peaks for two different fuel batches, Thermal Limits and the Effective Neutron Multiplication Factor (k{sup eff}). The results show that the fuel lattices in which the frequency, which the inverted form of the X{sup 2} distribution, was used revealed the best values of local power peak factor. Additionally it is shown that the performance of a fuel lattice could be enhanced controlling the frequency of the uranium enrichment rods and the variety of

  5. Detail analysis of tritium permeation in the metal liquid channels of the regenerating sheaths of a fusion reactor in presence of helium bubbles; Analisis de detalle de la permeacion de tritio en los caneles de metal liquido de las envolturas regeneradoras de un reactor de fusion en presencia de burbujas de helio

    Energy Technology Data Exchange (ETDEWEB)

    Banet, L.; Mas de les Valls, E.; Sedano, L. A.

    2012-07-01

    Inside the channels of liquid metal of the fusion reactor regenerative wrappers, the possible existence of nucleated helium bubbles is not remote. Helium is formed joined the tritium in the escaped neutrons of plasma with lithium. The accumulation of helium in the contact surfaces, between the structure and ML, lead a reduction of heat transfer, at the same time a reduction in the permeation of tritium. The coexistence of three phases in touch: metal liquid, helium and structural material, makes the transport of heat and tritium in a complex phenomenon. To enrich tritium transport studies conducted in the past, there is now a detail analysis of the helium bubble environment adhered to the channel ML wall of a regenerative wrap. For the study we used a CFD tool development on free code OpenFOAM.

  6. Evaluation and standardization of neutron activation analysis according to the K{sub 0} method in the RP-10 reactor; Evaluacion y estandarizacion del analisis por activacion neutronica segun el metodo del K{sub 0} en el reactor nuclear RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Montoya R, E

    1995-06-01

    It has been characterized and standardized an irradiation of the RP-10 Research Nuclear Reactor for use of the K{sub 0} method of neutron activation analysis using the Hoegdahl convention; also it has been evaluate the behaviour of such method in regard to the accuracy and precision of the results obtained in the quantitative multi elemental analysis of several certified materials of reference. In order to prove that the analytical method is totally under statistical control, it has been used the Heydorn method. It has been verified that the method is exact, precise and reliable to determine the aluminium, antimuonium, arsenic, bromine, calcium, chloride, copper, magnesium, manganese, sodium, titanium, vanadium, zinc and other elements. Also, they are discussed, in regard to the use of K{sub 0} constants, the different formalisms employed to calculate the integral of the reaction rate by nucleus in the activation. (author). 58 refs., 18 tabs., 6 figs.

  7. Major accident analyses for experimental zero-power fast reactor assemblies; Analyse des accidents graves pouvant survenir dans les reacteurs experimentaux a neutrons rapides de puissance zero; Analiz krupnoj avarii dlya ehksperimental'ny kh reaktornykh ustanovok nulevoj moshchnosti na bystrykh nejtronakh; Analisis de los accidentes graves que pueden producirse en los reactores experimentales rapidos de potencia cero

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, G.; Barts, E. W.; Kapil, S.; Tomabechi, K. [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    A study has been made of the possibility, mechanism, and consequence of melt-down and other major nuclear accidents for a ZPR-III type experimental zero-power fast reactor of the two-half type. This study has been supplemented by an evaluation of the importance of the Doppler effect for a wide range of nuclear reactor assemblies for such a reactor. A melt-down event is highly improbable because of the restricted sequence of events which must be postulated. A discussion of the mechanism of the collapse is followed by the results of coupled neutronics-hydrodynamic s calculations for two zero-power assemblies. A 1200-l core has been examined because it represents a relatively large reactor of common core composition. A smaller core with a high-void fraction has been examined as a potentially more dangerous system. Very different time-wise behaviour has been found for the two systems. For sharp accidents in zero-power assemblies, the U{sup 235}-atoms, separated as plates of enriched uranium, will heat very rapidly while the remainder of the core remains essentially cold, so that a gas of U{sup 235}-vapour will provide the disassembly pressure. The adaption of the neutronics-hydrodynamic s code AX-I to the use of a Van der Waals gas is described. Another important change in the equation of state used in the code is to employ a Mie-Griineisen type equation derivable from solid state theory. This change provides a more satisfactory way to evaluate the pressure term for cores of variable composition. Because the highly enriched U{sup 235} plates of a zero-power assembly will heat much more rapidly than the depleted uranium plates, the possibility of a net positive Doppler effect is much larger for an experimental assembly than for the equivalent power breeder reactor. This hazard has been examined for a range of possible assemblies. These calculations indicate that the Doppler coefficient for a zero-power assembly does not become important as a hazard until one approaches

  8. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    Edwards, R.M.; Power, M.A.; Bryan, M.

    1992-01-01

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  9. Nuclear reactors

    International Nuclear Information System (INIS)

    Yoshioka, Michiko.

    1985-01-01

    Purpose: To obtain an optimum structural arrangement of IRM having a satisfactory responsibility to the inoperable state of a nuclear reactor and capable of detecting the reactor power in an averaged manner. Constitution: As the structural arrangement of IRM, from 6 to 16 even number of IRM are bisected into equial number so as to belong two trip systems respectively, in which all of the detectors are arranged at an equal pitch along a circumference of a circle with a radius rl having the center at the position of the central control rod in one trip system, while one detector is disposed near the central control rod and other detectors are arranged substantially at an equal pitch along the circumference of a circle with a radius r2 having the center at the position for the central control rod in another trip system. Furthermore, the radius r1 and r2 are set such that r1 = 0.3 R, r2 = 0.5 R in the case where there are 6 IRM and r1 = 0.4 R and R2 = 0.8 R where there are eight IRM where R represents the radius of the reactor core. (Kawakami, Y.)

  10. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  11. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  12. Optimization of the pyrolysis process of empty fruit bunch (EFB) in a fixed-bed reactor through a central composite design (CCD)

    Energy Technology Data Exchange (ETDEWEB)

    Mohamed, Alina Rahayu; Hamzah, Zainab; Daud, Mohamed Zulkali Mohamed [School of Bioprocess Engineering, Jejawi Complex of Academics (3), UniMAP, 02600 Arau Perlis (Malaysia)

    2014-07-10

    The production of crude palm oil from the processing of palm fresh fruit bunches in the palm oil mills in Malaysia hs resulted in a huge quantity of empty fruit bunch (EFB) accumulated. The EFB was used as a feedstock in the pyrolysis process using a fixed-bed reactor in the present study. The optimization of process parameters such as pyrolysis temperature (factor A), biomass particle size (factor B) and holding time (factor C) were investigated through Central Composite Design (CCD) using Stat-Ease Design Expert software version 7 with bio-oil yield considered as the response. Twenty experimental runs were conducted. The results were completely analyzed by Analysis of Variance (ANOVA). The model was statistically significant. All factors studied were significant with p-values < 0.05. The pyrolysis temperature (factor A) was considered as the most significant parameter because its F-value of 116.29 was the highest. The value of R{sup 2} was 0.9564 which indicated that the selected factors and its levels showed high correlation to the production of bio-oil from EFB pyrolysis process. A quadratic model equation was developed and employed to predict the highest theoretical bio-oil yield. The maximum bio-oil yield of 46.2 % was achieved at pyrolysis temperature of 442.15 °C using the EFB particle size of 866 μm which corresponded to the EFB particle size in the range of 710–1000 μm and holding time of 483 seconds.

  13. ANALISIS PERIKANAN HUHATE DI PERAIRAN LARANTUKA, FLORES

    Directory of Open Access Journals (Sweden)

    Mohamad Adha Akbar

    2016-11-01

    Full Text Available Informasi mengenai beberapa aspek perikanan huhate sangat diperlukan sebagai bahan untuk perencanaan pengelolaan perikanan yang berkelanjutan. Penelitian ini dilakukan di Larantuka, Flores Timur pada tahun 2014 dengan tujuan untuk menganalisis perikanan huhate sebagai salah satu tulang punggung perikanan TCT. Kegiatan penelitian diprioritaskan pada analisis unit alat tangkap, daerah penangkapan, komposisi hasil tangkapan dan estimasi Total Faktor Produktivitas (TFP perikanan huhate. Basis data pengukuran adalah himpunan  data pendaratan dan observasi lapang. Hasil penelitian menunjukan bahwa karakteristik armada terdiri dari kapal yang terbuat dari fibreglass dengan kisaran bobot kapal 6 - 30 GT. Daerah penangkapan di sekitar perairan Laut Sawu dan Laut Flores. Hasil tangkapan utama didominansi oleh cakalang (Katsuwonus pelamis sebanyak 82%, juwana tuna (Thunnus spp. 17% dan tongkol (Auxis spp. 1% serta hasil tangkapan ikutan lemadang (Coryphaena hippurus dan marlin (Makaira spp. < 1%. Hasil analisis tangkapan per unit upaya (CPUE memberikan nilai rata-rata sebesar 1,1 ton/trip (0,4-1,7 ton/trip dengan nilai tertinggi terjadi pada Februari, sedangkan terendah terjadi pada Januari. Hasil penelitian menunjukkan terdapat hubungan yang signifikan antara tren bulanan CPUE dan nilai TFP.

  14. ANALISIS PENGELOLAAN LINGKUNGAN PERMUKIMAN DI KABUPATEN SOPPENG

    Directory of Open Access Journals (Sweden)

    Bakhrani Rauf

    2016-08-01

    Full Text Available Penelitian ini  bertujuan untuk mendeskripsikan pengelolaan lingkungan permukiman di Kabupaten Soppeng pada aspek: (1 penyediaan dan penanganan lahan terbuka hijau (open space; (2 penyediaan dan penanganan drainase; (3  penanganan sampah; (4 penyediaan dan penanganan pembuangan veses (septic tank. Jenis penelitian ini adalah penelitian kuantitatif dengan pendekatan survei.  Sampel wailayah penelitian ini adalah satu RW di ibu kota kabupaten dan satu RW di desa yang dipilih dengan metode purpossive sampling,  yaitu RW yang sudah maju di ibu kota kabupaten dan RW yang tertinggal di desa. Responden sebanyak 50 kepala keluarga yakni masing-masing 25 kepala keuarga di setiap RW, dipilih dengan  systematic random sampling.  Teknik pengumpulan data yang dilakukan adalah melakukan observasi langsung dan dilengkapi dengan wawancara terhadap responden. Analisis yang digunakan adalah analisis deskriptif. Hasil penelitian menunjukkan bahwa pengelolaan lingkungan permukiman di Kabupaten Soppeng pada aspek: (1 ketersediaan dan penanganan lahan terbuka hijau (open space ditemukan belum memadai; (2 ketersediaan drainase (air kotor dan air hujan ditemukan belum memadai; (3 Penanganan sampahbelum memadai; dan (4 penanganan veses dan penyediaan septic tankbelum memadai.

  15. Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca; Radovi za potrebe eksploatacije reaktora RA - I-IV, II Deo, Predprojekat VI-SA 1, Petlja za ispitivanje gorivnih elemenata reaktora EL-4 u centralnom vertikalnom eksperimentalnom kanalu reaktora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO{sub 2} with beryllium cladding, cooled by CO{sub 2} under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO{sub 2}. This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment.

  16. IDENTIFIKASI MISKONSEPSI SISWA SMP PADA KONSEP FOTOSINTESIS MELALUI ANALISIS GAMBAR

    Directory of Open Access Journals (Sweden)

    Devi Ariandini

    2014-01-01

    Full Text Available Tujuan dari penelitian ini adalah untuk mengidentifikasi miskonsepsi siswa dengan analisis menggambar. Tiga puluh empat siswa di kelas 8 di sekolah menengah pertama digunakan sebagai subyek dalam penelitian ini. Teknik sampel menggunakan teknik purposive sampling. Data yang diperlukan untuk penelitian ini dikumpulkan melalui kuesioner, menggambar analisis rubrik, dan wawancara. Identifikasi Kesalahpahaman ditentukan dengan menggambar siswa berdasarkan menggambar kriteria klasifikasi oleh Kose (2008. Siswa diperintahkan untuk menarik tentang konsep fotosintesis setelah proses pembelajaran. Gambar siswa dianalisis dengan rubrik dan setelah itu mereka diwawancarai. Hasil penelitian menunjukkan tidak semua tingkat kriteria menggambar dari tingkat 1 sampai 5 diidentifikasi. Dari hasil analisa, gambar paling banyak ditemukan adalah pada tingkat 4. Gambar pada tingkat 4 dikategorikan sebagai gambar lengkap konsep fotosintesis dan tidak ada kesalahpahaman ditemukan. Berdasarkan gambar mereka, ada siswa 2,9% diidentifikasi yang diselenggarakan kesalahpahaman. Ada perbedaan jumlah siswa yang diadakan kesalahpahaman antara gambar hasil analisis dan hasil wawancara. Dari hasil wawancara, ada siswa 35,2% dimiliki kesalahpahaman, lebih dari menggambar hasil analisis. Ini berarti bahwa identifikasi kesalahpahaman melalui analisis gambar tidak efektif. Kesalahpahaman siswa yang paling sering terjadi pada konsep fotosintesis adalah tempat berlangsungnya fotosintesis. Faktor yang membuat kesalahpahaman siswa yaitu karena siswa itu sendiri dan lingkungannya. Kata Kunci: fotosintesis, kesalahpahaman, konsep, menggambar analisis

  17. The fast breeder reactor

    International Nuclear Information System (INIS)

    Davis, D.A.; Baker, M.A.W.; Hall, R.S.

    1990-01-01

    Following submission of written evidence, the Energy Committee members asked questions of three witnesses from the Central Electricity Generating Board and Nuclear Electric (which will be the government owned company running nuclear power stations after privatisation). Both questions and answers are reported verbatim. The points raised include where the responsibility for the future fast reactor programme should lie, with government only or with private enterprise or both and the viability of fast breeder reactors in the future. The case for the fast reactor was stated as essentially strategic not economic. This raised the issue of nuclear cost which has both a construction and a decommissioning element. There was considerable discussion as to the cost of building a European Fast reactor and the cost of the electricity it would generate compared with PWR type reactors. The likely demand for fast reactors will not arrive for 20-30 years and the need to build a fast reactor now is questioned. (UK)

  18. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

    The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

  19. ANALISIS EFISIENSI LEMBAGA KEUANGAN MIKRO

    Directory of Open Access Journals (Sweden)

    Ihwan Susila

    2007-12-01

    Full Text Available This article discuss about microfinance organizations. The research based on analysis of efficiency of Badan Kredit Desa (BKD in Sukoharjo district in Central of Java Province. In the earlier, paper discuss about microfinance and its role in the economics development. Analysis data use Data Envelopment Analysis with three inputs and two outputs to analysis of financial performance and eight inputs and four outputs to analysis of general efficiency. This research found that from 169 BKD used as setting in this research, only 21 BKD have efficiency in finance performance and 73 BKD in general performance. In the future, microfinance organizations (BKD need innovation especially in the system which originated in developing countries where it has successfully enabled extremely impoverished people to engage in self-employment projects that allow them to generate an income and, in many cases, begin to build wealth and exit poverty. Due to the success of microcredit, many in the traditional banking industry have begun to realize that these microcredit borrowers should more correctly be categorized as pre-bankable; thus, microcredit is increasingly gaining credibility in the mainstream finance industry and many traditional large finance organizations are contemplating microcredit projects as a source of future growth.

  20. Analisis Tingkat Kepentingan Dan Kinerja Layanan Automated Teller Machine (Atm) Bank Mandiri

    OpenAIRE

    Setiawati, Lenny; Sugiharto, Toto

    2008-01-01

    Penelitian ini ditujukan untuk menganalisis tingkat kepentingan dan kinerja layananATM Bank Mandiri. Analisis Servqual yang terdiri atas dimensi tangible, realibility,responsiveness, assurance,dan empathy digunakan untuk menganalisis kinerjalayanan ATM. Sementara itu, Customer Satisfaction Index dan ImportancePerformance Analysis yang terdiri atas analisis kuadran dan analisis kesenjangandigunakan untuk menginvestigasi kepuasan pelanggan dan untuk mengidentifikasikandimensi layanan yang kiner...

  1. ANALISIS VARIABEL KEUANGAN YANG MEMPENGARUHI KEBIJAKAN DEVIDEN

    Directory of Open Access Journals (Sweden)

    Sumiadji -

    2012-03-01

    Full Text Available Penelitian ini dilakukan untuk menguji pengaruh variabel keuangan yang terdiri dari: rasio pro-fitabilitas (return on assets, likuiditas (cash ratio, rasio hutang (debt to equity ratio, market value (earnings per share, dan perputaran total aset (total assets turnover terhadap kebijakan dividen yang diproksikan dengan dividend payout ratio (DPR pada perusahaan manufaktur yang terdaftar di Bursa Efek Indonesia tahun 2004-2008. Prosedur pemilihan sampel penelitian menggunakan purposive sampling sehingga menghasilkan 8 perusahaan yang memenuhi kriteria sampel. Data sekunder dikumpulkan dengan teknik dokumentasi bersumber dari Indonesian Capital Market Directory (ICMD, laporan keuangan, dan hasil Rapat Umum Pemegang Saham (RUPS. Teknik analisis yang digunakan dalam penelitian ini adalah analisis regresi linear berganda. Hasil penelitian ini adalah secara simultan variabel ROA, CR, DER, EPS dan TATO berpengaruh terhadap DPR. Secara parsial variabel yang mempengaruhi DPR adalah CR, EPS dan TATO. Varabel lainnya, yaitu ROA dan DER ditemukan tidak berpengaruh terhadap DPR. This research was conducted to examine the influence of the financial variables which consists of: return on assets (ROA, cash ratio (CR, debt to equity ratio (DER, earnings per share (EPS, and total asset turnover (TATO to the dividend policy that indicated by the dividend payout ratio (DPR of listed manufacturing company in Indonesia Stock Exchange  2004 to 2008. The sample selection procedure used was a purposive sampling so that it produced eight companies that met the sample criteria. Se-condary data was collected by the documentation technique were obtained from the Indonesian Capital Market Directory (ICMD, financial statements, and the results of the Annual General Meeting of Shareholders. The analysis technique used was multiple linear regression analysis. The research found that five variables of kind of ROA, CR, DER, EPS dan TATO simultaneously influence to dividend

  2. ANALISIS PEMANFAATAN JEJARING SOSIAL UNTUK PENENTUAN KONSENTRASI MAHASISWA DENGAN METODE SOCIAL NETWORK ANALYSIS (Studi Kasus: Universitas Nusantara PGRI Kediri

    Directory of Open Access Journals (Sweden)

    Risky Aswi R

    2015-08-01

    Full Text Available Analisis pemanfaatan  jejaring  sosial untuk penentuan konsentrasi mahasiswa dengan metode sosial network analysis. Tujuan dibangun sistem ini untuk menentukan konsentrasi mahasiswa dengan pendekatan Sosial Network Analisis Studi Kasus Jejaring Sosial Facebook dan mampu memanfaatkan facebook sebagai alat untuk menentukan konsentrasi mahasiswa jurusan teknik informatika menjadi tiga bagian yaitu pemrograman, jaringan, dan multimedia. Batasan yang digunakan dalam penelitian ini adalah penelitian ini hanya berlaku pada mahasiswa yang memiliki akun facebook. Penelitian ini menggunakan Social Network Analysis untuk mencari between centrality.Pada tahap pertama setiap akun akan dilihat relasinya setelah itu hubungan antar akun akan dimasukan ke node XL dan akan menghasilkan between centrality. Mahasiswa yang melanjutkan proses selanjutnya adalah mahasiswa yang nilai betweent centralitynya 85% teratas. Setelah itu akan ditambahkan variabel group yang digunakan untuk mengkelompokan peminatan, dan ditambahkan variabel nilai akademis untuk menguatkan pendapat yang diperoleh sebelumnya.Dengan cara melihat between centrality dan menambahkan variabel group untuk membagi siswa sesuai konsentrasi, dan memabahkan variabel nilai akademik untuk memperkuat pendapat. Sosial network analysis terbukti dapat menentukan konsentrasi mahaiswa. Facebook dapat digunakan sebagai alat untuk menentukan konsentrasi mahasiswa, konsentrasi mahasiswa dibagi menjadi pemrograman, jaringan, dan multimedia. Kata Kunci : Jejaring Sosial, Social Network Analysis, between centrality

  3. FBR type reactor

    International Nuclear Information System (INIS)

    Hayase, Tamotsu.

    1991-01-01

    The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

  4. ANALISIS PENGARUH KONSUMSI ROKOK DENGAN KEMISKINAN DI PROVINSI JAWA TENGAH

    Directory of Open Access Journals (Sweden)

    Agnes Marisca Dian Sari

    2017-06-01

    Full Text Available Tujuan penelitian ini adalah untuk mengetahui pengaruh kemiskinan dengan konsumsi rokok di Jawa Tengah tahun 2013 dan mengetahui pengaruh pajak rokok dengan konsumsi rokok di Jawa Tengah tahun 2013. Jenis data yang digunakan adalah data sekunder. Metode analisis yang digunakan ialah regresi Ordinary Least Square (OLS dengan data cross section tahun 2013 di Provinsi Jawa Tengah dengan 35 Kabupaten/Kota. Hasil penelitian ini adalah ketika Garis kemiskinan naik maka akan menaikan konsumsi rokok. Variabel Garis kemiskinan signifikan dan positif terhadap konsumsi rokok di Jawa Tengah tahun 2013.Variabel pajak rokok bernilai positif namun tidak signifikan. Variabel Kemiskinan dan pajak rokok mampu menjelaskan tingkat konsumsi rokok sebesar 0.1263% dan sisanya dijelaskan oleh variabel lain. F-statistik sebesar 2,31. F-tabel sebesar 1,37, dan t-tabel sebesar 2,034.Hasil penelitian dapat disimpulkan adanya pengaruh antara konsumsi rokok dengan kemiskinan di Jawa Tengah tahun 2013. Ketika konsumsi rokok di Jawa Tengah naik maka meningkatkan kemiskinan di Jawa Tengah pada Tahun 2013 dan pengaruh antara konsumsi rokok dan pajak rokok di Jawa Tengah pada tahun 2013 tidak signifikan tapi bernilai positif. Artinya kebijakan pajak di Jawa Tengah belum mampu untuk mengurangi konsumsi rokok di Jawa Tengah pada tahun 2013. Meskipun sudah ada pajak rokok namun konsumsi rokok tetap terus meningkat. The aims of this research were to find out the effects of poverty on cigarette consumption in Central Java in 2013 and to recognize the effects of tax cigarette on cigarette consumption in Central Java in 2013. The type of the data used was secondary data. The analysis method used was the regression of Ordinary Least Square (OLS with the cross section data of 2013 in 35 Districts of Central Java Province.The research results show that when the Poverty Line increases, it increases cigarette consumption. The variable on Poverty Line has effect on cigarette consumption in

  5. ANALISIS VARIABILITAS CURAH HUJAN DAN SUHU DI BALI

    Directory of Open Access Journals (Sweden)

    Ogi Setiawan

    2017-01-01

    Full Text Available Indonesia sebagai negara kepulauan yang terdiri dari pulau-pulau besar dan kecil menjadi sangat rentan terhadap dampak perubahan iklim. Salah satu pulau yang juga rentan terhadap perubahan iklim adalah pulau Bali. Dampak potensial adanya perubahan iklim adalah perubahan pola hujan, peningkatan suhuudaradankenaikanpermukaanlaut. Sektoryangakanmenerimadampakperubahaniklimdengan serius adalah sektor kehutanan dan pertanian. Untuk mendukung upaya mitigasi dan adaptasi maka diperlukan informasi perubahan iklim yang terjadi. Penelitian ini bertujuan untuk mengetahui variabilitas iklim di Bali. Metode yang digunakan adalah analisis kecenderungan curah hujan, analisis perubahan suhu udara, analisis perubahan tipe iklim dan analisis pergeseran bulan basah, lembab dan kering. Data hujan yang digunakan adalah data hujan dari GPCC (1961-1998 dan BMKG Bali (19992008, sedangkan data suhu berasal dari BMKG Bali (2004-2008. Hasil analisis menunjukkan bahwa di pulau Bali secara umum sudah mengalami perubahan iklim. Tipe iklim berdasarkan Schmidt-Ferguson mengalami perubahan dari relatif basah menjadi agak kering. Suhu udara rata-rata bulanan serta curah hujan bulanan dan tahunan memiliki kecenderungan yang semakin meningkat. Bulan basah dan bulan kering telah mengalami pergeseran dan perubahan jumlahnya. Dampak perubahan iklim terhadap ekosistem hutan di Bali belum diketahui dengan pasti, namun terdapat beberapa implikasi perubahan iklim terhadap sektor kehutanan diantaranya kebakaran hutan dan perubahan jadwal penanaman.

  6. Utilization of noise analysis technique for mechanical vibrations estimation in the ATUCHA{sub 1} and Embalse Argentine NPP; Uso de la tecnica de analisis de ruido para la estimacion de vibraciones mecanicas en las centrales nucleares argentinas Atucha I y Embalse

    Energy Technology Data Exchange (ETDEWEB)

    Lescano, V.H.; Wentzeis, L.M. [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Centro Atomico Constituyentes; Guevara, M.; Moreno, C. [Nucleoelectrica Argentina S.A., Cordoba (Argentina). Central Nuclear Embalse; Pineyro, J. [Nucleoelectrica Argentina S.A., Buenos Aires (Argentina). Central Nuclear Atucha I

    1996-07-01

    In Argentine, comprehensive noise measurements have been performed with the reactor instrumentation of the PHWR power plant Atucha I and Embalse. The Embalse reactor is a CANDU-600 (600 Mwe) type pressurized heavy water reactor. It's a heavy water moderator and heavy water cooled natural uranium fueled pressure tube system. Signal of vanadium and platinum type in core-self power neutron detectors of ex-core ion chambers and of a moderator pressure sensor have been recorded and analysed. The vibration of reactor internals as vertical and horizontal in-core neutron flux detectors units and the coolant channels systems, consisting of calandria and pressure tubes with fuel bundles, have been identified and monitored during normal reactor operation. Atucha I, is a PHWR reactor natural uranium fueled, and heavy water moderated and cooled. Neutron noise techniques using of ex-core ionization chambers and in-core Vanadium SPND's were implemented, among others, in order to produce early detection of anomalous vibrations in the reactor internals. Noise analysis was successfully performed to identify normal and peculiar vibrations in particular reactor internals. (author)

  7. Modern concepts of thermodynamic optimization in Mexican thermoelectric stations; Conceptos modernos de optimacion termodinamica en centrales termoelectricas mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Cervantes-de Gortari, J; Vidal-Santo, A.; Mendez-Lavielle, F.; Bautista-Godinez, O. [Departamento de Termoenergia, from Facultad de Ingenieria UNAM (Mexico)

    2002-03-01

    In this paper, a summary review of the current thermodynamic concepts related to the maximum power generation and minimum entropy production are presented. The results of the analysis are considered in Mexican power stations using conventional cycles and are compared with other power stations around the world. [Spanish] En este trabajo se revisa el analisis de maxima generacion de potencia que implica la minimizacion de la produccion de entropia en centrales generadoras de potencia. De acuerdo con los lineamientos mas recientes publicados en la literatura. Los conceptos y resultados del analisis se aplican a varias centrales mexicanas y se comparan con otras centrales en el mundo.

  8. Modern concepts of thermodynamic optimization in Mexican thermoelectric power stations; Conceptos modernos de optimacion termodinamica en centrales termoelectricas mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Cervantes de Gortari, J.; Vidal Santo, A.; Mendez Lavielle, F.; Bautista Godinez, O. [Facultad de Ingenieria, UNAM, Mexico, D.F. (Mexico)

    2002-03-01

    In this paper, a summary review of the current thermodynamic concepts to the maximum power generation and minimum entropy production are presented. The results of the analysis are considered in Mexican power stations using conventional cycles and are compared with other power stations around the world. [Spanish] En este trabajo se revisa el analisis de maxima generacion de potencia que implica la minimizacion de la produccion de entropia en centrales generadoras de potencia, de acuerdo con los lineamientos mas recientes publicados en la literatura. Los conceptos y resultados del analisis se aplican a varias centrales mexicanas y se comparan con otras centrales en el mundo.

  9. Site of the First Spanish Nuclear Power Stations; Los Emplazamientos de las Primeras Centrales Nucleares Espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Pascual, F.; Alonso, A.; Norena, S.; Sevilla, A. [Junta de Energia Nuclear, Madrid (Spain)

    1967-09-15

    (e), con reactor de agua en ebullicion y contencion por condensacion de vapor, y la central de Vandellos, de 480 MW(e), con reactor grafito-gas y diseno integrado del tipo EDF-4. Los dos primeros estan situados en el interior del pais, el tercero en la costa mediterranea. Se discuten los criterios convencionales y los relacionados con la seguridad, que se han utilizado en la seleccion. Se pone de relieve la influencia de la orografia espanola en el transporte del equipo pesado y su repercusion en la seleccion de emplazamientos para centrales nucleares. Se hace referencia a la experiencia obtenida en el transporte del equipo de la central de Zorita. Se analizan las dificultades practicas encontradas al aplicar unas determinadas normas de seguridad a emplazamientos de centrales de tipo y caracteristicas de diseno diferentes. Ya que el tipo de reactor y su sistema de contencion influyen en el valor practico de la aplicacion de unas determinadas normas que, ademas, han de adaptarse a las caracteristicas peculiares de cada nacion, se indica la conveniencia de utilizar de forma adecuada y flexible las normas de seguridad para el analisis de los emplazamientos de centrales nucleares. Se describen las caracteristicas geologicas y meteorologicas de los tres emplazamientos y se resumen los trabajos e investigaciones realizados en estos campos. En especial, se destacan los estudios de hidrologia realizados en el caso de Zorita y Santa Maria de Garofia, y se describen las estaciones meteorologicas montadas en ambos emplazamientos, los experimentos de difusion con globos equilibrados realizados en el caso de Santa Maria de Garofia y los resultados de estas investigaciones. (author)

  10. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  11. Nuclear reactor construction with bottom supported reactor vessel

    International Nuclear Information System (INIS)

    Sharbaugh, J.E.

    1987-01-01

    This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

  12. ANALISIS SEBARAN RADIONUKLIDA PADA KONDISI NORMAL UNTUK REAKTOR AEC 1000 MW

    Directory of Open Access Journals (Sweden)

    Sri Kuntjoro

    2015-03-01

    Full Text Available Telah dilakukan analisis sebaran radionuklida pada reaktor daya Atomic Energy Agency (AEC 3568 MWTh, setara dengan 1000 Mwe untuk kondisi operasi normal. Analisis dilakukan untuk dua reaktor yang terpisah sejauh 500 m dan sudut 90o satu dengan yang lain. Langkah awal dalam melakukan analisis adalah menentukan suku sumber reaktor menggunakan program komputer ORIGEN2 dan EMERALD NORMAL. ORIGEN2 digunakan untuk menentukan inventori radionuklida yang terdapat di reaktor. Selanjutnya dengan dengan menggunakan program EMERALD NORMAL dihitung suku sumber yang sampai ke cerobong reaktor. Untuk menganalisis dosis yang diterima penduduk dilakukan dengan menggunakan program PC-CREAM. Perhitungan dilakukan untuk satu dan dua PLTN di calon tapak PLTN. Hasil yang diperoleh adalah sebaran radionuklida terbesar untuk satu PLTN pada jarak 1 km dan kearah zona 9 (191,25o dan untuk dua PLTN pada jarak 1 km dan kearah zona 10 (213,75o. Radionuklida yang sampai ke penduduk melalui dua alur yaitu alur makanan dan hirupan. Untuk alur makanan berasal dari radionuklida I-131, dan terbesar melalui alur produk susu sebesar 53,40 % untuk satu maupun dua PLTN . Untuk alur hirupan ranionuklida pemberi kontribusi paparan terbesar berasal dari Kr-85m sebesar 53,80 %. Dosis total terbesar yang diterima penduduk terdapat pada jarak 1 Km untuk bayi yaitu sebesar 4,10 μSi dan 11,26 μSi untuk satu dan dua PLTN. Hasil ini sangat kecil dibandingkan dengan batas dosis yang diijinkan oleh badan pengawas (BAPETEN untuk penduduk yaitu sebesar 1 mSi. Kata Kunci : Reaktor daya, komputer code, radionuklida, alur makanan, hirupan   Analysis for radionuclide dispersion for the Atomic Energy Agency (AEC 3568 MWth Power Reactor, equal to the 1000 MWe at normal condition has been done. Analysis was done for two piles that is separated by 500 m distance and angle of 90o one to other. Initial pace in doing the analysis is to determine reactors source term using ORIGEN2 and EMERALD NORMAL

  13. ANALISIS SPASIAL KEJADIAN DEMAM BERDARAH DENGUE BERDASARKAN KEPADATAN PENDUDUK

    Directory of Open Access Journals (Sweden)

    Agcrista Permata Kusuma

    2016-01-01

    Full Text Available Abstrak Puskesmas Kedungmundu merupakan wilayah endemis DBD dengan kasus yang tinggi. Diperlukan upaya dalam menentukan kebijakan strategi pengendalian vektor secara efektif dan efisien. Analisis spasial dalam SIG dapat digunakan untuk mengetahui pola penyebaran dan daerah potensi penularan DBD. Jenis penelitian ini adalah penelitian deskriptif analitik menggunakan pendekatan cross sectional. Teknik pengambilan sampel menggunakan sampel wilayah memperhatikan proporsi sampel dengan jumlah sampel 146 responden. Pengambilan titik koordinat menggunakan GPS. Analisis data menggunakan analisis univariat dan analisis spasial. Hasil perhitungan statistik spasial ANN diperoleh nilai Z-score = -11,054 terdapat pola spasial kasus DBD di wilayah kerja Puskesmas Kedungmundu. Nilai ANN = 0,52 < 1, artinya pola penyebaran kejadian DBD yang terjadi adalah berkerumun. Kesimpulan dalam penelitian ini sebaran kasus DBD memiliki keterkaitan secara spasial dengan kepadatan penduduk. Abstract Kedungmundu PHC is an endemich region with a high case. Be required to determine policy of vector control strategies effectively and efficiently. Spatial analsys in GIS can be used to determine the pattern of distribution and areas of DHF potential transmission. The type this research was analysis descriptive with cross sectional approach. The sampling technique used a sample area of attention to the proportion of the sample with 146 respondents of total sample. Capturing the coordinates used GPS. Data analisys used univariat and spatial analisys. Result of ANN obtained a Z-score= -11,054, there was a spatial pattern of dengue cases in Kedungmundu PHC. ANN value = 0,52 < 1, it meant that the pattern of DHF distribution was clustered. The conclution of this research was DHF distribution cases has spatial correlation with density population.

  14. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1983-01-01

    Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

  15. ANALISIS GEN HAEMAGGLUTININ PADA VIRUS CAMPAK LIAR

    Directory of Open Access Journals (Sweden)

    Subangkit Subangkit

    2015-05-01

    Full Text Available AbstrakPenyakit Campak disebabkan oleh virus campak yang termasuk genus Morbilivirus dan Family Paramyxoviridae. Penyakit campak masih menjadi masalah kesehatan karena masih ditemukan Kejadian Luar Biasa (KLB di Indonesia. Salah satu penyebab terjadinya KLB tersebut diduga sebagaiakibat perbedaan antigenesitas antara strain vaksin yang digunakan dengan strain virus campak liar yang beredar di Indonesia. Penelitian ini bertujuan mendapatkan gambaran tentang karakteristik genetik gen Haemagglutinin virus campak liar yang ada di Indonesia. Spesimen yang digunakan sebanyak 27 isolat virus penyebab KLB dari 17 propinsi selama periode tahun 2003-2010. Isolat virus dilakukan pemeriksaan secara RT-PCR dan sekuensing dengan metode Sanger. Hasil sekuensing dianalisis dengan menggunakan perangkat lunak Bioedit 7.0 dan MEGA 4.0. Hasil penelitian didapatkan perbedaan 10 asam amino antara virus campak strain vaksin CAM-70 dan virus campak liar pada posisi D416N; K424T; V451M; N455T; V466I; I473T; F476L; Y481S atau Y481N; H495N; G505D. Kesimpulan penelitian ini adalah terdapat perbedaan karakteristik genetik antara virus campak liar di Indonesia berbeda dengan strain virus vaksin CAM-70.Kata kunci : Campak, Analisis Molekuler, Hemagglutinin, CD46AbstractMeasles is caused by virus belonging to the genus Morbilivirus and Family Paramyxoviridae. Measles is still a public health problem because outbreak of measles still found in Indonesia. Outbreak is suspected as a result of differences in antigenicity between vaccine strains used with wild-type measles virus strains circulating in Indonesia. This study aims to get genetic characteristics of wild-type measles virus haemagglutinin gene in Indonesia. The specimens were used 27 viral isolates from 17 provinces period 2003-2010. Viral isolates examined by RT-PCR and sequencing with Sanger method. Sequencing analysis were conducted using Bioedit 7.0 and MEGA 4.0 software. The results showed 10 amino acid differences

  16. Analisis Kelayakan Finansial Usaha Budidaya Bambu

    Directory of Open Access Journals (Sweden)

    Husnul Khotimah

    2015-12-01

    Full Text Available Budidaya bambu diperlukan untuk menambah populasi bambu yang cenderung berkurang yang disebabkan oleh beralihnya fungsi lahan yang digunakan untuk pemukiman atau diganti dengan komoditi tanaman lain yang dianggap lebih menguntungkan. Sementara itu kebutuhan bahan baku bambu terus meningkat sejalan dengan pertumbuhan penduduk dan perkembangan kemajuan ilmu pengetahuan. Budidaya bambu bermanfaat selain untuk menjaga ketersediaan suplai juga untuk meningkatkan kualitas bambu untuk memenuhi permintaan pasar. Tulisan ini mengkaji analisis finansial dari penanaman bambu. Kajian finansial dibutuhkan untuk menunjukkan bahwa upaya penanaman atau budidaya bambu ini layak atau tidak secara finansial untuk dilakukan. Data yang digunakan adalah data hasil penelitian di perusahaan perkebunan bambu PT XYZ di Lampung. Hasil penelitian menunjukkan bahwa nilai NPV (Rp 36.644.364,08 lebih besar dari nol, Net B/C (2,56 lebih besar dari satu, IRR (11 % lebih besar dari suku bunga 6 %, serta payback period pada tahun ke-9 umur proyek 15 tahun. Berdasarkan kriteria indikator kelayakan finansial dapat disimpulkan bahwa usaha budidaya bambu layak secara finansial untuk diusahakan. Katakunci: Hasil Hutan Bukan Kayu (HHBK, budidaya bambu, studi kelayakan, analisis finansial   Financial analysis and feasibity study of bamboo cultivation  Abstract Bamboo cultivation is necessary to increase the population of bamboo clumps. The bamboo clumps tend to decrease due to the shift of used lands for residential or replaced by other crop comodities, which are considered more profitable. On the other hand, the need of bamboo for raw materials remain increase in line with population growth and the development of science. The important of the bamboo cultivation are to maintain the availability of its supply and to improve the quality of bamboo, which meet the market demands. This paper examined financial analysis of bamboo cultivation. Financial study was necessary to show whether

  17. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  18. Analisis Korelasi Kanonik Hubungan Perilaku Pemimpin dan Motivasi Kerja Karyawan

    Directory of Open Access Journals (Sweden)

    I Gusti Ayu Made Srinadi

    2014-06-01

    Full Text Available Kualitas pemimpin merupakan penentu keberhasilan organisasi yang dipimpin. Hubungan antara pemimpin dengan karyawannya merupakan hubungan saling ketergantungan yang umumnya tidak seimbang. Dalam proses interaksi yang terjadi antara pemimpin dan karyawan, berlangsung proses saling memengaruhi. Penelitian ini bertujuan untuk mencari hubungan perilaku pemimpin terhadap motivasi kerja karyawan dengan menggunakan analisis korelasi kanonik. Pengujian dengan menggunakan analisis korelasi kanonik menunjukkan bahwa perilaku pemimpin dengan motivasi karyawan memiliki keeratan hubungan dengan nilai korelasi kanonik sebesar 0,9058533. Faktor perilaku pemimpin yang paling tinggi berkorelasi dengan motivasi kerja karyawan di McDonald’s Kuta Beach adalah faktor kemampuan mengarahkan dan menghadapi karyawan dengan nilai korelasi yaitu sebesar 0,7619707.

  19. Analisis Korelasi Kanonik Hubungan Perilaku Pemimpin dan Motivasi Kerja Karyawan

    Directory of Open Access Journals (Sweden)

    I Gusti Ayu Made Srinadi

    2015-04-01

    Full Text Available Kualitas pemimpin merupakan penentu keberhasilan organisasi yang dipimpin. Hubungan antara pemimpin dengan karyawannya merupakan hubungan saling ketergantungan yang umumnya tidak seimbang. Dalam proses interaksi yang terjadi antara pemimpin dan karyawan, berlangsung proses saling memengaruhi. Penelitian ini bertujuan untuk mencari hubungan perilaku pemimpin terhadap motivasi kerja karyawan dengan menggunakan analisis korelasi kanonik. Pengujian dengan menggunakan analisis korelasi kanonik menunjukkan bahwa perilaku pemimpin dengan motivasi karyawan memiliki keeratan hubungan dengan nilai korelasi kanonik sebesar 0,9058533. Faktor perilaku pemimpin yang paling tinggi berkorelasi dengan motivasi kerja karyawan di McDonald’s Kuta Beach adalah faktor kemampuan mengarahkan dan menghadapi karyawan dengan nilai korelasi yaitu sebesar 0,7619707.

  20. Analisis Aliran Daya Berbasis Injeksi Arus dalam Bentuk Vektor

    Directory of Open Access Journals (Sweden)

    Ahmad Wira Satriawan

    2017-11-01

    Full Text Available Tulisan ini memaparkan hasil penelitian yang telah dilakukan untuk membandingkan metode analisis aliran daya berbasis injeksi arus dalam bentuk vektor dengan format polar dan rektangular. Penelitian ini dilakukan untuk memperoleh metode analisa aliran daya dengan perhitungan yang lebih cepat dan akurat, serta iterasi yang lebih sedikit. Metode iterasi Newton Raphson diadopsi dalam penelitian ini dan bahasa pemrograman Python serta library komputasinya digunakan. Analisis terhadap karakteristik konvergensi dari kedua format dilakukan pada IEEE 14-bus Test System. Dari penelitian ini diperoleh hasil bahwa format rektangular lebih unggul dibandingkan format polar untuk kasus yang diteliti.

  1. Analisis Spasial Kejadian Filariasi di Kabupaten Demak Jawa Tengah

    Directory of Open Access Journals (Sweden)

    Nurjazuli Nurjazuli

    2018-04-01

    Full Text Available Latar Belakang: Filariasis merupakan salah satu penyakit tular vektor yang kurang mendapatkan perhatian, termasuk kelompok Neglected Tropical Diseases (NTDs. Kabupaten Demak merupakan salah satu wilayah di Propinsi Jawa Tengah  yang merupakan daerah endemis filarisis (mf rate>1%. Kejadian filarisis di daerah ini diduga berkaitan dengan kondisi lingkungan fisik dan biologis (nyamuk yang mempunyai peran penting dalam penyebaran penyakit filarisis. Penelitian ini bertujuan untuk menemukan adanya penderita baru,  mengidentifikasi kondisi lingkungan fisik dan biologi yang berkaitan dengan sebaran filarisis di Kabupaten Demak. Matede: Penelitian ini merupakan penelitian observasional dengan rancangan cross-sectional. Sebanyak 30 kasus filariasis dijadikan indek kasus yang selanjutnya dipilih secara purposif sebanyak 140 yang tinggal di sekitar 30 kasus tersebut untuk dilakukan pengamblan darah jari. Observasi lingkungan dilakukan untuk mengidentifikasi kondisi lingkungan (breeding places dan resting places dari yang diduga sebagai nyamuk vektor filariasis. Penangkapan nyamuk dilakukan di sekitar rumah penderita filariasis. Pengukuran koordinat kasus filariais dilakukan dengan pesawat Geographic Positioning System (GPS. Pemeriksaan darah jadi jari dilakukan di Laboratorium Kesehatan Daerah (LABKESDA Propinsi Jawa Tengah. Sedang bedah nyamuk dilakukan di Balai Penelitian Vektor Penyakit Banjarnegara. Analisis data dlakukan secara deskriptif, analisis spasial dilakukan dengan software ArcGis 9.3. Hasil: Penelitian ini tidak menemukan penderita baru filarisis (mf rate=0%. Sebanyak 129 ekor nyamuk telah dilakukan pembedahan dengan hasil semuanya negatip cacing filaria. Hasil identifikasi nyamuk menemukan spesies nyamuk Culex quinquefasciatus merupakan nyamuk yang dominan (72,86% di lokasi penelitian.Terdapat breeding places (40% berupa genangan air terbuka (SPAL dan resting places (83,3% berupa semak-semak di sekitar rumah penderita. Analisis spasial

  2. Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde; Cuestionamientos al aumento de potencia de los reactores de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Salas M, B., E-mail: salasmarb@yahoo.com.mx [UNAM, Facultad de Ciencias, Departamento de Fisica, Circuito exterior s/n, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2014-08-15

    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)

  3. Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide (Spanish Edition); Diseno del sistema de refrigeracion del reactor y los sistemas asociados en las centrales nucleares. Guia de seguridad

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-15

    This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1982), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1987), which are superseded by this new Safety Guide. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1982 and 1987, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2004, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included.

  4. ANALISIS FAKTOR KEHADIRAN DOSEN DI UNIVERSITAS X

    Directory of Open Access Journals (Sweden)

    Annisa Mulia Rani

    2016-10-01

    Full Text Available Aspek kualitas pekerjaan berkaitan langsung dengan waktu yang khusus digunakan dosen untuk mengembangkan kemampuan. Maka untuk merealisasikan kualitas dosen yang terbaik , pihak manajemen khusunya dekan membuat peraturan untuk kehadiran dosen adalah minimal 25 jam/minggu. Dengan peraturan ini diharapkan dosen dapat melaksanakan beban kerja dosen sebaik-baiknya. Peraturan ini tertulis dan tertuang pada SK Dekan No 20/2006 pada kampus X. Dengan Menggunakan Analisis faktor mencoba menemukan hubungan atar sejumlah variable-variabel yang awalnya saling independen satu dengan yang lain dimana variable penyebab kekurangan jam dosen datang/minggu adalah keluaraga, manajemen, hubungan social, fasilitas pengajaran, jarak/lokasi, kompensasi transport. Berdasarkan uji Bartley test dan Measure sample of adequate yang pertama maka dengan nilai sig 0.04 dan msa 0.540 . Dengan menggunakan metode principal component analysis maka pembentukan factor hanya ada 1 componen karena nilai eigen value yang mempunyai nilai diatas 1. Faktor pembentuk baru yaitu manajemen, kompensasi dan jarak menjadi satu component.

  5. Analisis Gameplay Game Genre Virtual Pet

    Directory of Open Access Journals (Sweden)

    Abi Senoprabowo

    2015-02-01

    Full Text Available Game adalah struktur interaktif yang membuat pemain berjuang menuju sebuah tujuan. Game dapat memberikan emosi dan mood, menghubungkan dengan orang latihan, sarana latihan, serta dapat memberikan edukasi. Salah satu game yang berkembang saat ini adalah game bergenre Virtual pet. Game virtual pet merupakan game simulasi memelihara sesuatu. Virtual pet memiliki gameplay yang menarik dan menyenangkan yang membuat pemain seolah-olah benar-benar memiliki binatang peliharaan mereka sendiri. Virtual pet dianggap oleh sebagian besar penggunanya dapat memberikan kegembiraan serta rasa kasih sayang karena tingkat interaksinya yang baik. Banyak pengembang game pemula yang mengembangkan genre ini sebagai game yang mereka buat karena kemudahaan dan tingkat penggunanya yang banyak. Akan tetapi banyak dari pengembang game pemula tidak memperhatikan tingkat keberlanjutan game virtual pet yang mereka buat sehingga membuat pemain cepat bosan. Pada penelitian ini, analisis game bergenre virtual pet yang sudah sukses dibuat seperti Zombigotchi, Tamagotchi Unicorn, dan Bird Land, diharapkan dapat membantu para pengembang game pemula agar mengetahui cara merancang dan mengembangkan game virtual pet dengan baik. Kata Kunci: game, gameplay, virtual pet

  6. ANALISIS MODEL KEPUASAN TERHADAP PEMBELIAN ULANG

    Directory of Open Access Journals (Sweden)

    Naili Farida

    2014-09-01

    Full Text Available Tujuan penelitian ini yaitu untuk menguji pengaruh brand equity, nilai pelanggan dan lifestyle yang dimediasi kepuasan konsumen terhadap pembelian ulang produk gadget di Kota Semarang. Responden dalam penelitian ini adalah seluruh konsumen yang telah melakukan pembelian produk gadget merek Samsung, sebanyak 120 orang. Teknik sampling yang digunakan yaitu purposive sampling. Teknik analisis yang digunakan yaitu Partial Least Square (PLS. Hasil penelitian menunjukkan bahwa terdapat pengaruh brand equity terhadap kepuasan, namun dalam konteks lifestyle dan nilai pelanggan tidak ada pengaruh terhadap kepuasan. Sedangkan kepuasan menunjukkan adanya pengaruh terhadap pembelian ulang. Diharapkan dari hasil penelitian ini mampu meningkatkan pembelian ulang melalui brand equity, lifestyle dan nilai pelanggan dalam konteks kepuasan. The objective of the research was to test the influence of brand equity, customer value and lifestyle which were mediated by consumer satisfaction toward re-purchasing of gadget products in Semarang. The respondents of the study were all consumers who have purchased Samsung gadget products. It was a purposive sampling study with 120 respondents. The data were analyzed by Partial Least Square (PLS. The result of the study showed that there was an influence of brand equity toward satisfaction, but in the lifestyle context and customer value did not give any influence toward satisfaction. Whereas; the satisfaction gave influence toward re-purchase. It is expected that this study can increase the repurchasethrough brand equity, lifestyle and customer values in the satisfaction context.

  7. ANALISIS POLA MANAJEMEN BAHAN BAKAR DESAIN TERAS REAKTOR RISET TIPE MTR

    Directory of Open Access Journals (Sweden)

    Lily Suparlina

    2015-03-01

    Full Text Available Parameter neutronik dibutuhkan dalam mendesain teras reaktor riset. Reaktor riset jenis MTR (Material Testing Reactor sangat diminati karena dapat digunakan baik untuk riset dan juga produksi radio isotop. Reaktor riset yang ada saat ini sudah tua sehingga dibutuhkan desain reaktor yang mempunyai teras kompak. Desain teras reaktor riset yang sudah ada saat ini belum cukup memadai untuk memenuhi persyaratan di dalam UCD yang telah ditetapkan yaitu fluks neutron termal di teras 1x1015 n/cm2s, oleh karena itu perlu dibuat desain teras reaktor baru sebagai alternatif yang kompak dan dapat menghasilkan fluks neutron tinggi. Telah dilakukan perhitungan dan analisis terhadap manajemen bahan bakar desain teras kompak dengan konfigurasi teras 5x5, berbahan bakar U9Mo-Al dan tinggi teras aktif 70 cm. Tujuan dari riset ini untuk memperoleh fluks neutron di teras memenuhi kebutuhan seperti yang telah ditetapkan di UCD dengan panjang siklus operasi minimum 20 hari pada daya 50 MW. Perhitungan dilakukan dengan menggunakan paket program komputer WIMSD-5B untuk menggenerasi tampang lintang makroskopik bahan bakar dan Batan-FUEL untuk memperoleh nilai parameter neutronik serta Batan-3DIFF untuk perhitungan nilai reaktivitas batang kendali. Perhitungan parameter neutronik teras reaktor riset ini dilakukan untuk bahan bakar U-9Mo-Al dengan tingkat muat bervariasi dan 2 macam pola pergantian bahan bakar yaitu teras segar dan teras setimbang. Hasil analisis menunjukkan bahwa pada teras segar, tingkat muat 235U sebesar 360 gram, 390 gram dan 450 gram memenuhi kriteria keselamatan dan kriteria penerimaan di UCD dengan nilai fluks neutron termal di teras lebih dari 1x1015 n/cm2s dan panjang siklus >20 hari, sedangkan pada teras setimbang panjang siklus dapat terpenuhi hanya untuk tingkat muat 450 gram. Kata kunci: desain teras reaktor, bahan bakar UMo, pola bahan bakar, WIMS, BATAN-FUEL   Research reactor core design needs neutronics parameter calculation use computer

  8. Life time of nuclear power plants and new types of reactors; La duree de vie des centrales nucleaires et les nouveaux types de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-05-01

    This report, realized by the Evaluation Parliamentary Office of scientific and technological choices, aims to answer simple but fundamental questions for the french electric power production. What are the phenomena which may limit the exploitation time of nuclear power plants? How can we fight against the aging, at which cost and with which safety? The first chapter presents the management of the nuclear power plants life time, an essential element of the park optimization but not a sufficient element. The second chapter details the EPR and the other reactors for 2015 as a bond between the today and tomorrow parks. The last chapter deals with the necessity of efforts in the research and development to succeed in 2035 and presents other reactors in project. (A.L.B.)

  9. Thermal response of core and central-cavity components of a high-temperature gas-cooled reactor in the absence of forced convection coolant flow

    International Nuclear Information System (INIS)

    Whaley, R.L.; Sanders, J.P.

    1976-09-01

    A means of determining the thermal responses of the core and the components of a high-temperature gas-cooled reactor after loss of forced coolant flow is discussed. A computer program, using a finite-difference technique, is presented together with a solution of the confined natural convection. The results obtained are reasonable and demonstrate that the computer program adequately represents the confined natural convection

  10. The safety of light water reactors

    International Nuclear Information System (INIS)

    Pershagen, B.

    1986-04-01

    The book describes the principles and practices of reactor safety as applied to the design, regulation and operation of both pressurized water reactors and boiling water reactors. The central part of the book is devoted to methods and results of safety analysis. Some significant events are described, notably the Three Mile Island accident. The book concludes with a chapter on the PIUS principle of inherent reactor safety as applied to the SECURE type of reactor developed in Sweden. (G.B.)

  11. ANALISIS KONTRIBUSI PAJAK HOTEL TERHADAP PENDAPATAN ASLI DAERAH KABUPATEN NUNUKAN

    OpenAIRE

    -, MULIATI

    2014-01-01

    2014 Analisis Kontribusi Pajak Hotel terhadap Pendapatan Asli Daerah Kabupaten Nunukan Analysis of The Contributions Tax on Hotel Againts Regional Renenue Nunukan District Muliati Haerial M. Christian Mangiwa Penelitian ini bertujuan untuk mengetahui seberapa besar kontribusi pajak hotel terhadap pendapatan asli daerah, mengetahui sistem pengawasan, dan potensi yang ada untuk meningkatkan pajak hotel, mengetahui sistem dan prosedur...

  12. Analisis Sektor/Sub Sektor Unggulan di Kabupaten Bungo

    Directory of Open Access Journals (Sweden)

    Gafur Gafur

    2016-03-01

    Full Text Available Abstract. This study aimed to analyze the leading sectors in Bungo. The method used is Location Quotient (LQ, Dynamic Location Quotient (DLQ, specialization index, Growth Ratio Model (MRP. Based on analysis of LQ and DLQ, there are only two basis sectors at present and in the future, namely the construction sector and trade, hotels and restaurants. Based on the analysis of Specialization Index, in Bungo Regency has a concentration of the economy in the agricultural sector and the manufacturing sector. Based on MRP analysis also showed that prominent sector growth at the level of Bungo and Jambi Province, namely electricity, gas and water supply; the building sector; and trade, hotels and restaurants. Keywords : Location Quotient (LQ, Dinamic Location Quotient (DLQ, Specialization Index, Growth Ratio Model   Abstrak. Penelitian ini bertujuan untuk menganalisis sektor unggulan di Kabupaten Bungo. Metode yang digunakan adalah analisis Location Quotient (LQ, Dinamic Location Quotient (DLQ, indeks spesialisasi, Model Rasio Pertumbuhan (MRP. Berdasarkan analisis LQ dan DLQ,  hanya ada 2 sektor yang menjadi sektor basis pada saat ini dan pada masa yang akan datang yaitu sektor bangunan dan sektor perdagangan, hotel dan restoran. Berdasarkan analisis Indeks Spesialisasi, di Kabupaten Bungo telah terjadi konsentrasi ekonomi pada sektor pertanian dan sektor industri pengolahan. Berdasarkan analisis MRP juga dapat diketahui bahwa sektor yang menonjol pertumbuhannya pada tingkat Kabupaten Bungo dan Provinsi Jambi yaitu sektor listrik, gas dan air bersih; sektor bangunan; serta sektor perdagangan, hotel dan restoran. Kata Kunci : Location Quotient (LQ, Dinamic Location Quotient (DLQ, indeks spesialisasi, Model Rasio Pertumbuhan

  13. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  14. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

    The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

  15. ANALISIS HUBUNGAN KEMANDIRIAN KEUANGAN DAERAH DAN KETERGANTUNGAN DAERAH TERHADAP PENGANGGURAN DAN KEMISKINAN

    Directory of Open Access Journals (Sweden)

    Rosyafah Febiandani

    2017-06-01

    Full Text Available Adanya desentralisasi fiskal diharapkan dapat menciptakan kemandirian daerah dan dapat mengurangi ketergantungan pemerintah daerah terhadap pemerintah pusat. Kemandirian keuangan daerah dicerminkan dengan perbandingan besarnya PAD terhadap total pendapatan daerah. Sejak 10 tahun dilaksanakannya otonomi daerah sesuai UU No 32 Tahun 2004, kemandirian keuangan daerah di Provinsi Jawa Tengah masih berada di level yang kurang baik dibandingkan dengan provinsi lainnya di Pulau Jawa. Jumlah pengangguran dan jumlah penduduk miskin di Provinsi Jawa Tengah juga masih terhitung tinggi. Penelitian ini bertujuan untuk mengetahui hubungan dari tingkat kemandirian keuangan daerah dan tingkat ketergantungan daerah terhadap tingkat pengangguran dan tingkat kemiskinan di kabupaten/kota Provinsi Jawa Tengah Tahun 2013. Data yang digunakan dalam penelitian ini adalah data sekunder. Metode analisis yang digunakan adalah Analisis Korelasi Kanonikal menggunakan bantuan program SPSS. Hasil penelitian menunjukkan kemandirian keuangan daerah mempunyi hubungan yang signifikan, kuat, dan tidak searah dengan pengangguran dan kemiskinan. Sedangkan hubungan antara ketergantungan daerah terhadap kemiskinan dan pengangguran mempunyai hubungan yang signifikan, tidak kuat, dan tidak searah. Peningkatan kemandirian keuangan daerah guna mengurangi tingkat ketergantungan terhadap pemerintah pusat dapat dilakukan dengan cara menggali dan mengelola sumber daya atau potensi daerah yang dimilikinya secara efektif dan efisien sebagai sumber utama pendapatan keuangan daerahnya. Fiscal decentralization is expected to create independency regional financial and to reduce the dependence of local governments to the central government. Independency regional financial can be result by the ratio of PAD to total local revenue. Since 10 years the implementation of regional autonomy based on UU No. 32 of 2004, independency regional financial in Central Java is still unwell compared to the other

  16. ANALISIS KINERJA DENGAN MENGGUNAKAN PENDEKATAN RASIO CAMEL

    Directory of Open Access Journals (Sweden)

    Sri Murdiati

    2015-06-01

    Full Text Available Tujuan penelitian ini adalah untuk menganalisis tingkat kesehatan bank dilihat dari kategori CAMEL. Metode penelitian yang digunakan adalah studi kasus di PD BPR BKK Banjarharjo.Dalam menguji hipotesis digunakan alat analisis CAMEL. Hasil penelitian ini yaitu modal pada 2008 sampai 2010 termasuk dalam kriteria sehat. ROA meningkat 2008 sampai 2010 dengan kriteria sehat bagi biaya operasional yang dikeluarkan oleh pendapatan operasional yang seimbang. Rasio Kas tahun 2008 sampai 2010 termasuk dalam kriteria sehat berarti bank memiliki kemampuan untuk mengelola asset yang digunakan untuk membayar kewajiban. LDR mengalami tren yang signifikan selama tahun 2008 sampai 2010 sehingga dana yang diterima bank untuk meningkatkan baik tabungan, deposito berjangka, modal inti, yang berarti kemampuan bank untuk meningkatkan penyaluran kredit, IRR menunjukan nilai positif dalam menghadapi resiko pasar.Pengembangan tingkat kesehatan pada tahun 2008 sampai 2010 untuk komponen Capital, Assets, Laba dan Likuiditas meningkat. The goal of this research is to analyze the healtiness of banks seen from CAMEL category. The research applied a case study in PD BPR BKK Banjarharjo. The hypotheses tested using CAMEL analysis tools. The result of the study is that the modal used 2008 until 2010 is consideredin a healthy criteria. The increasing ROA in 2008 until 2010 is considered healthy criteria for operational expenses incurred by the operating income. Such condition meant that the banks are able to manage the assets which are used to pay the obligations. The significant increasing of LDR over the years 2008 until 2010 makes the received funds by the bank to increase the savings deposits, time deposits and the core capital. As the recunts, the banks are able to increase credit disstribution. More over, the IRR showed a positive values in the face of market risks and the development of healthy levels in 2008 until 2010 for the components of Capital, Assets, Earnings and

  17. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    In the system described the fuel elements are arranged vertically in groups and are supported in such a manner as to tend to tilt them towards the center of the respective group, the fuel elements being urged laterally into abutment with one another. The elements have interlocking bearing pads, whereby lateral movement of adjacent elements is resisted; this improves the stability of the reactor core during refuelling operations. Fuel elements may comprise clusters of parallel fuel pins enclosed in a wrapper of hexagonal cross section, with bearing pads in the form of spline-like ribs located on each side of the wrapper and extending parallel to the longitudinal axis of the fuel element, being interlockable with ribs on pads of adjacent fuel elements. The arrangement is applicable to a reactor core in which fuel elements and control rod guide tubes are arranged in modules each of which comprises a cluster of at least three fuel elements, one of which is rigidly supported whilst the others are resiliently tilted towards the center of the cluster so as to lean on the rigidly supported element. It is also applicable to modules comprising a cluster of six fuel elements, each resiliently tilted towards a central void to form a circular arch. The modules may include additional fuel elements located outside the clusters and also resiliently tilted towards the central voids, the latter being used to accommodate control rod guide tubes. The need for separate structural members to act as leaning posts is thus avoided. Such structural members are liable to irradiation embrittlement, that could lead to core failure. (U.K.)

  18. On fusion and fission breeder reactors

    International Nuclear Information System (INIS)

    Brandt, B.; Schuurman, W.; Klippel, H.Th.

    1981-02-01

    Fast breeder reactors and fusion reactors are suitable candidates for centralized, long-term energy production, their fuel reserves being practically unlimited. The technology of a durable and economical fusion reactor is still to be developed. Such a development parallel with the fast breeder is valuable by reasons of safety, proliferation, new fuel reserves, and by the very broad potential of the development of the fusion reactor. In order to facilitate a discussion of these aspects, the fusion reactor and the fast breeder reactor were compared in the IIASA-report. Aspects of both reactor systems are compared

  19. ANALISIS PARITAS DAYA BELI KURS RUPIAH TERHADAP DOLLAR AMERIKA SERIKAT

    Directory of Open Access Journals (Sweden)

    Elysa Pernika Simanjuntak

    2017-06-01

    Full Text Available Penelitian ini bertujuan untuk menganalisis bagaimana penerapan teori paritas daya beli kurs Rupiah terhadap Dollar AS dalam jangka panjang maupun jangka pendek dan pengaruh tingkat inflasi, produk domestik bruto, jumlah uang beredar, dan cadangan devisa terhadap kurs Rp/USD dengan menggunakan alat analisis Error Correction Model Engle-Granger. Variabel dependen dalam penelitian ini adalah kurs, sedangkan variabel independennya adalah inflasi, produk domesti bruto, jumlah uang beredar, dan cadangan devisa. Hasil penelitian ini menunjukkan bahwa dalam jangka panjang maupun jangka pendek, teori paritas daya beli berlaku pada kurs Rupiah terhadap Dollar Amerika Serikat. Variabel independen secara bersama-sama berpengaruh terhadap kurs Rupiah dalam jangka pendek maupun jangka panjang kecuali variabel jumlah uang beredar tidak berpengaruh dalam jangka panjang dan cadangan devisa tidak berpengaruh terhadap kurs dalam jangka pendek. Rekomendasi dari penelitian ini adalah Bank Indonesia selaku bank sentral Republik Indonesia diharapkan lebih berhati- hati dalam mengambil kebijakan yang tepat demi menjaga kestabilan nilai tukar Rupiah. Salah satunya tetap mengawasi kebijakan yang ditetapkan pemerintah mengenai pemakaian Rupiah untuk seluruh transaksi dalam negeri.  This research aims to analyze how the application of the theory of purchasing power parity exchange rate of the Rupiah against the US Dollar in the long term and short term and influence the rate of inflation, GDP, money supply, and the foreign exchange reserves of the exchange rate of Rp/USD by using analytical tools Error Correction Model Engle-Granger. Dependent variable in this study is the exchange rate, while the independent variables are inflation, gross domestic product, money supply, and the foreign exchange reserves. The results of this study indicated that in the long term and short term, the theory of purchasing power parity exchange rate prevailing at the Rupiah against the US

  20. ANALISIS DESAIN PROSES SISTEM PENDINGIN PADA REAKTOR RISET INOVATIF 50 MW

    Directory of Open Access Journals (Sweden)

    Sukmanto Dibyo

    2015-03-01

    Full Text Available Reaktor Riset Inovatif (RRI merupakan jenis MTR (Material Testing Reactor yang dipersiapkan ke depan sebagai desain reaktor baru. Daya RRI telah ditetapkan dari perhitungan neutronik dan termohidrolika teras yaitu 50 MW termal. Reaktor bertekanan 8 kgf/cm2 dan laju aliran massa pendingin primer 900 kg/s. Tantangan yang penting dalam menindak lanjuti desain reaktor ini adalah analisis desain pada sistem pendingin. Makalah ini bertujuan untuk menganalisis desain proses sistem pendingin utama reaktor RRI daya 50 MW (RRI-50 dengan menggunakan program Chemcad 6.1.4. Dalam analisis ini dilakukan perhitungan neraca massa dan energi (mass/energy balances pada sistem pendingin primer dan sekunder sebagai pendingin utama. Masing-masing sistem pendingin tersebut terdiri dari 2 jalur beroperasi secara paralel dan 1 jalur redundansi. Disamping itu untuk desain termal unit komponen telah dianalisis dengan program RELAP5, frenchcreek dan Metoda Analitik. Hasil analisis yang diperoleh adalah desain diagram sistem pendingin yang mencakup data parameter entalpi, temperatur, tekanan dan laju aliran massa pendingin untuk masing-masing jalur. Adapun hasil desain unit komponen utama pada RRI-50 adalah tangki tunda dengan volume 51,5 m3, 2 unit pompa sentrifugal dan 1 unit pompa cadangan pada pendingin primer daya 141 kW/pompa dan pendingin sekunder daya 206 kW/pompa, 2 unit penukar panas tipe shell-tube dengan koefisien termal overall 1377 W/m2.oC dan 4 unit menara pendingin yang mampu melepaskan panas ke udara dengan desain temperatur approach 5,0 oC dan temperatur range 9,0 oC. Desain sistem pendingin reaktor RRI-50 ini telah menetapkan parameter operasi sistem pendingin yaitu temperatur, tekanan dan laju aliran massa pendingin dengan mempertimbangkan tuntutan aspek keselamatan teras reaktor sehingga desain temperatur maksimum pendingin masuk ke teras 44,5 oC. Kata kunci : RRI 50 MW, desain sistem pendingin, program Chemcad 6.1.4   Innovative Research Reactor RRI

  1. A contribution to the analysis of the thermal behaviour of Fast Breeder fuel rods with UO{sub 2}-PuO{sub 2} fuel; Contribucion al analisis del comportamiento termico de las barras combustibles de UO{sub 2}-PuO{sub 2} de los reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Jimenez, J; Elbel, H

    1977-07-01

    The fuel of Fast Breeder Reactors which consists of Uranium and Plutonium dioxide is mainly characterized by the amount and distribution of void volume and Plutonium and the amount of oxygen. Irradiation experiments carried out with this fuel have shown that initial structure of the fuel pellet is subjected to large changes during operation. These are consequences of the radial and axial temperature gradients within the fuel rods. (Author) 54 refs.

  2. Advanced reactor development

    International Nuclear Information System (INIS)

    Till, C.E.

    1989-01-01

    Consideration is given to what the aims of advanced reactor development have to be, if a new generation of nuclear power is really to play an important role in man's energy generation activities in a fragile environment. The background given briefly covers present atmospheric evidence, the current situation in nuclear power, how reactors work and what can go wrong with them, and the present magnitudes of world energy generation. The central part of the paper describes what is currently being done in advanced reactor development and what can be expected from various systems and various elements of it. A vigorous case is made that three elements must be present in any advanced reactor development: (1) breeding; (2) passive safety; and (3) shorter-live nuclear waste. All three are possible. In the right advanced reactor systems the ways of achieving them are known. But R and D is necessary. That is the central argument made in the paper. Not advanced reactor prototype construction at this point, but R and D itself. (author)

  3. Analisis Pembiayaan Kesehatan Keluarga Penderita Talasemia

    Directory of Open Access Journals (Sweden)

    Arif Kurniawan

    2013-04-01

    Full Text Available Pembiayaan kesehatan sekitar 146 (60% penderita talasemia di Banyumas, tahun 2011 ditanggung rumah tangga dalam bentuk pembayaran langsung (out of pocket payment. Penelitian ini bertujuan untuk menganalisis ability to pay, willingness to pay, dan need assessment pembiayaan kesehatan penderita talasemia di Kabupaten Banyumas. Jenis penelitian ini adalah observasional analitik dengan rancangan studi kasus. Penelitian ini menggunakan desain studi cross sectional dengan teknik pengambilan sampel simple random sampling. Jumlah sampel penelitian 30 responden yang mempunyai anggota keluarga penderita talasemia di Kabupaten Banyumas. Hasil penelitian menunjukkan keluarga penderita talasemia mempunyai ability to pay rata-rata adalah Rp34.448,8/bulan dan rata-rata willingness to pay pengobatan talasemia adalah Rp133.833,3/ bulan. Pola pembiayaan kesehatan talasemia di Kabupaten Banyumas menggunakan 93,3% Jaminan Kesehatan Masyarakat (Jamkesmas, 3,3% biaya sendiri, dan 3,3% asuransi kesehatan. Sebelum mendapatkan Jamkesmas, 90,0% responden membayar dengan out of pocket, berhutang, berhemat pada kebutuhan nonkesehatan, dan menjual perhiasan/sawah. Kebutuhan pelayanan kesehatan yang diharapkan keluarga penderita talasemia adalah konsultasi talasemia dan desain khusus ruang perawatan anak. Kebutuhan pembiayaan kesehatan keluarga penderita talasemia adalah uang transportasi ke rumah sakit sebagai bentuk biaya tidak langsung. Health financing of majority thalassemia patients, around 146 people (60% in Banyumas year 2011 is assured by Households in direct payments to health care providers (out-of-pocket payment. This study aimed to analyze the ability to pay, willingness to pay, and need assessment of health financing thalassemia in Banyumas. This research an analytic observation- Analisis Pembiayaan Kesehatan Keluarga Penderita Talasemia Health Financing Analysis of Thalassemia Patient Family Arif Kurniawan, Arih Diyaning Intiasari al with case study design

  4. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    matieres nucleaires ne se limite pas S de simples travaux d'inventaire mais sert de base a beaucoup d'autres activites qui font partie integrante du programme d'operations de tout reacteur, par exemple les expeditions de combustible irradie, le traitement chimique du combustible epuise et la comptabilite du combustible recupere et des matieres produites au cours du fonctionnement du reacteur, et l'institution et l'application d'un regime d'assurance satisfaisant. (author) [Spanish] Combustible relativamente nuevo y sumamente valioso para la produccion de energia electrica, el uranio requiere un control muy minucioso desde el momento en que la direccion de una central asume la responsabilidad financiera inherente a su posesion hasta que como combustible parcialmente agotado se transfiere a otra instalacion en la que se recupera la parte que no se ha consumido. Antes de que se descubriera la posibilidad de emplear la energia nuclear para producir electricidad, la mayor parte de las empresas que actualmente explotan centrales nucleares explotaban centrales alimentadas con combustibles fosiles y hablan establecido sistemas de control relativamente completos y adecuados para los combustibles de ese tipo. Los responsables de las centrales nucleoelectricas deben disponer de sistemas no menos adecuados para controlar los materiales nucleares especiales que utilizan. La explotacion de los reactores de potencia no es una ciencia antigua, pero durante el tiempo relativamente corto que ha transcurrido desde que se inicio su empleo los ingenieros y hombres de ciencia han mejorado continuamente el diseflo del equipo y los metodos de trabajo con objeto de disminuir los costos de produccion y de lograr que las centrales nucleares puedan competir en el plano economico con las centrales clasicas. La administracion de los materiales nucleares debe efectuarse con metodos modernos y eficientes a fin de que los adelantos tecnologicos que han permitido reducir los costos no resulten inutiles

  5. Nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    Sakurai, Shungo; Ogiya, Shunsuke.

    1990-01-01

    In a fuel assembly, if the entire fuels comprise mixed oxide fuels, reactivity change in cold temperature-power operation is increased to worsen the reactor shutdown margin. The reactor shutdown margin has been improved by increasing the burnable poison concentration thereby reducing the reactivity of the fuel assembly. However, since unburnt poisons are present at the completion of the reactor operation, the reactivity can not be utilized effectively to bring about economical disadvantage. In view of the above, the reactivity change between lower temperature-power operations is reduced by providing a non-boiling range with more than 9.1% of cross sectional area at the inside of a channel at the central portion of the fuel assembly. As a result, the amount of the unburnt burnable poisons is decreased, the economy of fuel assembly is improved and the reactor shutdown margin can be increase. (N.H.)

  6. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  7. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  8. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  9. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  10. Improved nuclear reactor construction with bottom supported reactor vessel

    International Nuclear Information System (INIS)

    Sharbaugh, J.E.

    1987-01-01

    An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

  11. Analisis Komoditi Unggulan Subsektor Tanaman Pangan di Sumatera Utara Tahun 2010 – 2014

    OpenAIRE

    Sinaga, Terry Praganda

    2016-01-01

    Tujuan penelitian ini adalah untuk mengetahui perkembangan produksi komoditi tanaman pangan selama periode tersebut sehingga dapat menganalisis komoditi subsektor tanaman pangan yang menjadi unggulan di Sumatera Utara. Komoditi unggulan tersebut juga dijabarkan untuk setiap kabupatem/kota yang ada di Sumatera Utara. Metode yang digunakan yaitu secara Convenience Sampling, dan metode analisis data dengan menggunakan analisis Location Quotient. Hasil penelitian menyimpulkan ba...

  12. ANALISIS KINERJA KEUANGAN PERUSAHAAN PT. ASURANSI JIWASRAYA (PERSERO) CABANG SULAWESI SELATAN

    OpenAIRE

    ARIANTY, ASTRI

    2012-01-01

    ANALISIS KINERJA KEUANGAN PERUSAHAAN PT. ASURANSI JIWASRAYA (PERSERO) CABANG SULAWESI SELATAN COMPANY FINANCIAL PERFORMANCE ANALYSIS PT. INSURANCE JIWASRAYA (LIMITED) SOUTH BRANCH SULAWESI Astri Arianty Prof. Dr. H. Muhammad Ali, SE., M.S Drs. Armayah Sida, M.Si Analisis terhadap kinerja keuangan perusahaan sangat penting dilakukan untuk mengetahui sejauh mana tingkat pencapaian yang telah diperoleh perusahaan sebagaimana tujuan perusahaan dalam menjalankan proses produk...

  13. Identifiksi Sebaran Litologi berdasarkan Analisis Data Resistivitas di Gunung Wungkal

    OpenAIRE

    Nurul Dzakiya; MGS. Dwiki Nugraha; Nenden L. Sidik; Trias Galena

    2017-01-01

    Analisis data untuk mengidentifikasi sebaran litologi yang memiliki potensi bahan galian industri di Daerah Gunung Wungkal Yogyakarta dengan menggunakan metode resistivitas dan survei geologi permukaan telah dilakukan. Hasil korelasi kedua data tersebut menunjukkan sebaran litologi merupakan pelapukan intrusi batuan beku yang kemudian menghasilkan material lempung (6,0-10 m), lempung pasiran (11-30 m) dan lapukan batuan diorit (30-55 m) yang berada di kedalaman berbeda. Ketebalan batuan di pe...

  14. Analisis Sikap Konsumen terhadap Produk Fashion Lokal dan Impor

    OpenAIRE

    Setiawan, Evelyn

    2014-01-01

    Abstrak: Analisis Sikap Konsumen Terhadap Produk Fashion Lokal dan Impor. Penelitian ini bertujuan untuk menganalisis sikap konsumen terhadap produk fashion lokal dan impor yang akan berpengaruh terhadap keputusan konsumsi. Sampel yang akan digunakan dalam penelitian ini adalah 1.000 mahasiswa dari 10 perguruan tinggi swasta terbesar di Surabaya. Pengambilan data dilakukan dengan metode kuesioner. Hasil pengujian statistik menunjukkan bahwa sebagian besar mahasiswa di Surabaya merasa bangga d...

  15. Uso de Analisis de Covarianza (ANCOVA en investigacion cientifica.

    Directory of Open Access Journals (Sweden)

    Badii, M.H.

    2008-01-01

    Full Text Available The basics of the ANalisis of COVAriance (ANCOVA are given. The objectives and the application of ANCOVA are laid out. Techniques for the estimation of contrasts and for the control and reduction of the degree of error are discussed. The application of a simple ANCOVA using real data is highlighted. The application of this technique in fixing the auxiliary variable in experimentation is emphasized.

  16. Analisis Pemasaran Ayam Ras Pedaging di Pasar Tradisional Kota Medan

    OpenAIRE

    Fachri, Yusrizal

    2017-01-01

    130306044 YUSRIZAL FACHRI, 2017. “Analisis Pemasaran Ayam Ras Pedaging di Pasar Tradisional Kota Medan”. Dibimbing oleh ARMYN HAKIM DAULAY dan NEVY DIANA HANAFI. Penelitian ini bertujuan untuk mengidentifikasi karakteristik lembaga pemasaran, bentuk saluran, fungsi pemasaran, dan menganalisis nilai tambah di lembaga-lembaga pemasaran ayam ras pedaging di pasar tradisional Kota Medan pada April sampai Mei 2017. Penelitian ini menggunakan data primer yang didapatkan dari observasi dan waw...

  17. Metode Pengumpulan dan Analisis Data : Lang Kah Vital Proses Penelitian

    OpenAIRE

    Suprapto, Agus .

    2005-01-01

    The process of data collection and. analysis is one of chains in scientific method that should be done in a research. This part later on will determine the right method in searching and analyzing a way in solving a problem. The data collected should be the ones which are relevant which the essence of research problems, so that the next interpreted data will eventually be concluded as valid. keywords: Pengumpulan data, analisis data,dan metode ilmiah

  18. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  19. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  20. ANALISIS PENGARUH KINERJA LINGKUNGAN TERHADAP KINERJA INDUSTRI KECIL

    Directory of Open Access Journals (Sweden)

    Sukirman -

    2012-03-01

    Full Text Available Tujuan penelitian adalah mengidentifikasi, menganalisis praktik pengelolaan lingkungan pada sentra industri kecil dibandingkan best practices dalam upaya meningkatkan kinerja lingkungan di Kabupaten Pati. Kajian difokuskan pada pengelolaan lingkungan secara efektif dengan melibatkan variabel inisiatif lingkungan, keterlibatan karyawan, dan integrasi dengan supplier. Populasinya adalah seluruh perusahaan Industri Kecil di Kabupaten Pati. Sampel berjumlah 97 perusahaan. Teknik sampling menggunakan kluster sampling, dengan sampel pada sentra industri kecil di Kabupaten Pati.  Analisis menggunakan analisis deskriptif dan analisis komparatif. Hasil penelitian menunjukkan praktik pengelolaan lingkungan pada sentra industri kecil di Kabupaten Pati belum dilaksanakan secara optimal. Sementara itu, variabel integrasi supplier berpengaruh langsung terhadap kinerja perusahaan.The purpose of this study is to identify and to analyze an environmental management practice which is compared to the best practices in order to improve environmental performance in the industrial centers in Pati District. This study focuses on managing the environment effectively by involving environmental initiative variables, employee involvement, and integration of suppliers. Population in this study was all small industrial enterprises in Pati regency which has 97 companies as data samples. Data were collected by using cluster sampling techniques, and samples were taken from small industrial centers in the District of Pati. Data were analyzed by using descriptive and comparative methods. Results of this study showed that environmental management practices in small industrial centers had not been implemented optimally. Meanwhile, supplier integration variables influenced directly toward corporate performance.

  1. Microfinanza: analisi d’impatto di un programma in India

    Directory of Open Access Journals (Sweden)

    Tommaso Rondinella

    2005-03-01

    Full Text Available L’analisi d’impatto dei programmi di microfinanza è uno strumento utile sia per migliorare i servizi offerti sia per garantire ai donatori che il denaro concesso sia utilizzato per programmi efficaci nell’alleviare la povertà. Il presente lavoro è costituito da due parti: la prima è dedicata all’analisi d’impatto, la seconda all’analisi empirica sul campo. L’indagine è stata condotta attraverso l’utilizzo di uno strumento in grado di dare una indicazione chiara dei cambiamenti avvenuti nelle condizioni di vita dei beneficiari e con il pregio di essere applicabile a costi molto ridotti. I risultati ottenuti mostrano in che misura l’accesso al credito cambi le condizioni di vita dei più poveri inducendo consistenti aumenti del reddito familiare, dei risparmi, della diversificazione delle attività produttive e del consumo di cibo. Inoltre si osserva, all’interno dei nuclei familiari, un miglioramento della condizione femminile chiaramente dipendente dalla partecipazione al programma di microcredito

  2. ANALISIS CLUSTER K-MEANS DALAM PENGELOMPOKAN KEMAMPUAN MAHASISWA

    Directory of Open Access Journals (Sweden)

    B. Poerwanto

    2016-12-01

    Full Text Available Abstract. Cluster Analysis, K-Means Algorithm, Student Classification. This study aims to classify students based on learning outcomes for subject the basic of statistics (DDS, which is measured based on attendance, task, midterm (UTS, and final exams (UAS to further used to evaluate learning for subjects that require analysis of quantitative . This study uses k-means cluster analysis to classify the students into three groups based on learning outcomes. After grouped, there are 3 people in the low category, 27 in the medium category and over 70% in the high category.Abstrak. Analisis Cluster K-Means dalam Pengelompokan Kemampuan Mahasiswa. Pene-litian ini bertujuan untuk mengelompokkan mahasiswa berdasarkan hasil belajar mata kuliah dasar-dasar statistika (DDS yang diukur berdasarkan variabel nilai kehadiran, tugas, ujian tengah semester (UTS, dan ujian akhir semester (UAS untuk selanjutnya digunakan untuk mengevaluasi pembelajaran untuk mata kuliah yang membutuhkan kemampuan analisis kuantititatif yang baik. Penelitian ini menggunakan analisis cluster k-means dalam mengelompokkan mahasiswa ke dalam tiga kelompok berdasarkan hasil belajarnya. Seteleh dikelompokkan, terdapat 3 orang yang masuk pada kategori rendah, 27 orang pada kategori sedang dan lebih dari 70% pada kategori tinggi.Kata Kunci: Cluster Analysis, K-Means Algoritma, Klasifikasi Mahasiswa, Universitas Cokroaminoto Palopo

  3. Estetika Tari Minang dalam Kesenian Randai Analisis Tekstual-Kontekstual

    Directory of Open Access Journals (Sweden)

    Sri Rustiyanti

    2013-03-01

    Full Text Available ABSTRACT   This paper reveals textual and contextual Randai, among other things, an analysis of Gerak Ga­ lombang Randai, an analysis of the character of Anak Randai, and at the end of the study series, to reveal the values contained in Randai as a cultural reality, which in principle is an inseparable part of the existence of Minangkabau community as the cultural support. The variety of motion used in Gerak Galombang Randai is not only a decoration of the motion beauty (tangible, but it also can be translated, as well as a symbol or emblem that has educational meanings (intangible, and can be an example of the daily life of the indigenous Minangkabau society.   Keywords: Minang Dance aesthetic, Randai, textual­contextual analysis     ABSTRAK   Tulisan ini mengungkap teksual dan kontekstual Randai, di antaranya, analisis terhadap gerak galombang Randai, analisis karakter tokoh anak Randai, dan sebagai akhir dari rang- kaian penelitian ini, mengungkapkan nilai-nilai yang terdapat pada Randai sebagai realitas budaya, yang pada prinsipnya merupakan bagian yang tak dapat dipisahkan dari eksistensi masyarakat Minangkabau sebagai penyangga kebudayaan. Ragam gerak yang digunakan dalam gerak galombang Randai itu kiranya tidak hanya sekedar hiasan keindahan gerak be- laka (tangibel, namun ia dapat diterjemahkan, sekaligus merupakan simbol atau lambang yang bermakna  mendidik (intangibel, dan dapat   menjadi teladan dalam kehidupan se- hari-hari dalam masyarakat adat di Minangkabau.   Kata Kunci: estetika Tari Minang, Randai, analisis tekstual-kontekstual

  4. Analisis Termal High Pressure Feedwater Heater di PLTU PT. XYZ

    Directory of Open Access Journals (Sweden)

    Maria Ulfa Damayanti

    2017-01-01

    Full Text Available Abstrak- PT. XYZ mengoperasikan tiga unit Pembangkit Listrik Tenaga Uap (PLTU unit 3, 7 dan 8 berkapasitas 2.030 MegaWatt. Pada PLTU Paiton unit 7 dan 8 terdapat delapan buah feedwater heater yaitu empat buah Low Pressure Water Heater (LPWH, tiga buah High Pressure Water Heater (HPWH, dan sebuah dearator. Pada PLTU Paiton unit 7 dan 8 terdapat kerusakan pada HPWH 6 yang menyebabkan penurunan efisiensi dari siklus secara keseluruhan. Penurunan efisiensi dapat terjadi karena temperatur feedwater sebelum masuk ke boiler terlalu rendah, sehingga kalor yang dibutuhkan oleh boiler untuk memanaskan feedwater meningkat. Oleh karena itu konsumsi batubara akan meningkat dan menyebabkan terjadi kenaikan biaya operasional harian dalam sistem pembangkit. Dari data Divisi Produksi PT. XYZ Unit 7 dan 8 diperoleh spesifikasi HPWH 6, 7, dan 8 dan propertis fluida dalam HPWH 6, 7, dan 8. Data tersebut digunakan sebagai dasar analisis termal yang meliputi performa masing-masing HPH. Tahap selanjutnya dalam analisis termal adalah memvariasikan beban 25%, 50%, 75%, 100%, dan 105%. Tahap terakhir analisis adalah menghitung performa dengan variasi sumbatan (plug 5%, 10%, 15%, dan 20% sesuai dengan variasi beban. Hasil yang didapatkan dari penelitian tugas akhir ini adalah nilai effectiveness tertinggi tercapai pada pembebanan 100% serta menghasilkan pressure drop tertinggi pada pembebanan 105%, nilai effectiveness terbesar serta nilai pressure drop terkecil terjadi pada zona Condensing, serta sumbatan (plugging pada HPH akan menyebabkan penurunan nilai effectiveness dan kenaikan pressure drop sisi tube.

  5. ANALISIS DAYA SAING EKSPOR SEKTOR UNGGULAN DI JAWA TENGAH

    Directory of Open Access Journals (Sweden)

    Wiwit Santi Wahyuningsih

    2017-06-01

    Full Text Available Penelitian ini bertujuan untuk mengidentifikasi industri unggulan yang ada di Jawa Tengah, dan kemudian industri unggulan tersebut diidentifikasi mana saja yang mempunyai daya saing ekspor. Penelitian ini menggunakan data PDRB Jawa Tengah dan PDB Tahun 2010-2015, Tabel Input Output Jawa Tengah Tahun 2013, serta data Ekspor-Impor Jawa Tengah Tahun 1997-2015. Data tersebut diperoleh dari data sekunder, yaitu dengan memanfaatkan data yang telah tersedia pada instansi terkait. Penelitian ini mengunakan alat analisis Indeks Daya Penyebaran (IDP, Indeks Derajat Kepekaan (IDK dan Revealed Comparative Advantage (RCA. Dari hasil IDP dan IDK terdapat 9 industri unggulan di Jawa Tengah yaitu industri pengolahan dan pengawetan ikan, industri minyak dan lemak, industri penggilingan padi, industri tepung terigu dan tepung lainnya, industri makanan ternak, industri pemintalan, industri tekstil, industri kayu dan bahan bangunan dari kayu, serta industri karet dan barang dari karet. Tetapi dari 9 industri unggulan tersebut yang memiliki daya saing ekspor tinggi hanya ada 3 industri yaitu industri dengan IDP>1, IDK>1 dan RCA>1 yang meliputi industri pemintalan, industri tekstil, dan industri kayu dan bahan bangunan dari kayu. Dari penelitian ini dapat disimpulkan bahwa sektor industri yang dapat diandalkan untuk meningkatkan pertumbuhan ekonomi melalui ekspor dan memiliki daya saing ekspor yang sangat bagus serta memilki harga jual tinggi yaitu hanya industri pemintalan, industri tekstil, dan industri kayu dan bahan bangunan dari kayu. Maka dari itu sebaiknya kebijakan pemerintah lebih ditekankan pada sektor hulu dan sektor hilir dari industri-industri tersebut. This research’s aim is to identify the leading manufactures in central Java then identify which of those industries have the export competitiveness. This study used data of Central Java’s Gross Domestic Regional Product (GDRP and Gross National Product (GNP on 2010-2015, Input Output Table on 2013, as

  6. Computerized reactor power regulation with logarithmic controller

    International Nuclear Information System (INIS)

    Gossanyi, A.; Vegh, E.

    1982-11-01

    A computerized reactor control system has been operating at a 5 MW WWR-SM research reactor in the Central Research Institute for Physics, Budapest, for some years. This paper describes the power controller used in the SPC operating mode of the system, which operates in a 5-decade wide power range with +-0.5% accuracy. The structure of the controller easily limits the minimal reactor period and produces a reactor transient with constant period if the power demand changes. (author)

  7. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  8. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

    A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

  9. Nuclear Energy in Central Europe 98, Proceedings

    International Nuclear Information System (INIS)

    Ravnik, M.; Jencic, I.; Zagar, T.

    1998-01-01

    Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 63 articles from Slovenia, sorounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Nuclear Methods, Reactor Physics, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation and Nuclear Waste disposal

  10. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

  11. Multiregion reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

  12. 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).

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

    Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

  14. ANALISIS KESENJANGAN PEMBANGUNAN EKONOMI ANTAR KABUPATEN/KOTA DI PROVINSI JAWA TENGAH

    Directory of Open Access Journals (Sweden)

    Panji Irawan Yogyadipratama

    2017-06-01

    Full Text Available Tujuan dari penelitian ini adalah (1 mengetahui bagaimana perkembangan tingkat ketimpangan pembangunan ekonomi Provinsi Jawa Tengah menurut Indeks Williamson; (2 mengetahui sejauh mana pengaruh angkatan kerja terhadap tingkat pembangunan ekonomi Provinsi Jawa Tengah; dan (3 mengetahui bagaimana pengaruh alokasi dana bantuan pembangunan kabupaten/kota terhadap pembangunan ekonomi Provinsi Jawa Tengah. Penelitian ini merupakan penelitian kuantitatif dengan digunakan data panel, data time series (tahun 2002-2011 dan cross section (35 kabupaten/kota di Provinsi Jawa Tengah. Jenis data yang digunakan dalam penelitian ini adalah data sekunder yang diperoleh dari Badan Pusat Statistik (BPS. Metode analisis yang digunakan adalah metode analisis regresi linier berganda data panel dengan metode FEM digunakan alat bantu software Eviews 7. Hasil penelitian adalah menunjukan(1 ketimpangan pembangunan ekonomi antar daerah di Provinsi Jawa Tengah yang dihitung dengan menggunakan indeks Williamson selama periode 2008-2011 menunjukkan ketimpangan semakin melebar; (2 alokasi dana bantuan pembangunan dari pemerintah pusat yang tidak merata dan daerah yang mendapat bantuan terlalu besar dapat meningkatkan tingkat ketimpangan antar daerah. Hal ini akibat pembangunan yang terkonsentrasi dengan daerah-daerah yang sudah maju dibandingkan daerah yang masih tertinggal, karena daerah yang maju memiliki fasilitas lebih baik dari daerah yang belum maju; dan (3 nilai R2 sebesar 0,9949 artinya variasi variabel ketimpangan pembangunan ekonomi di Provinsi Jawa Tengah dapat dijelaskan oleh variabel-variabel angkatan kerja dan alokasi dana pembangunan daerah sebesar 95,5% sedangkan sisanya sebesar 0,05% dijelaskan faktor-faktor lainnya di luar model. The purpose of this study were (1 to know how the development level of inequality of economic development in Central Java Province according to Williamson Index; (2 determine the extent of the influence of the labor force to the

  15. Blowing loop in the EL-4 reactor: CO{sub 2} flow control analogue study; Boucle de soufflage de la centrale EL-4 - regulation du debit CO{sub 2} - etude analogique

    Energy Technology Data Exchange (ETDEWEB)

    Chazal, G; Merle, J P; Guillemard, B [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Leroy, C; Robin, L; Jacquin, J C; Cornudet, A [Societe INDATOM, France (France)

    1966-07-01

    This report describes one study which contributed to the construction of the Monts d'Arree nuclear power station: EL-4. The reactor is cooled by a CO{sub 2} current provided by 3 turbo-blower groups. The priming vapour for the turbines is taken at the exit of the main CO{sub 2} - H{sub 2}O exchangers. The operation of EL 4 is based on a high degree of centralization of the controls which attributes an important role to the general regulation circuits. This general regulation includes in particular an internal blowing loop which controls the CO{sub 2} flow. The study of the control of this CO{sub 2} flow is made up of 3 parts: - analogue representation of the reactors cooling circuit and of the turbo blower unit. - first test campaign using the analogue computer describing the natural behaviour of the system in the absence of control. theoretical determination of the regulation factors; definition of the regulation using an analogue computer and second test campaign for recording the performances of the blowing loop. The 4. part of the report deals with the analogue study: analogue equations - development. (authors) [French] Ce rapport prend place parmi les etudes de realisation de la Centrale des Monts d'Arree EL-4. Le reacteur est refroidi par une circulation de CO{sub 2} assuree par 3 groupes turbosoufflantes. La vapeur d'entrainement des turbines est prelevee a la sortie des echangeurs principaux CO{sub 2} - H{sub 2}O. L'exploitation de EL-4 repose sur une centralisation poussee des moyens de controle-commande qui attribue un role essentiel aux circuits de regulation generale. Cette regulation generale comporte en particulier une boucle interne de soufflage qui realise un asservissement du debit de CO{sub 2}. L'etude de cette regulation du debit CO{sub 2} comprend 3 parties: - representation analogique du circuit de refroidissement du reacteur et de l'ensemble turbine-soufflante. - premiere campagne d'essais sur calculateur analogique decrivant le comportement

  16. Tingkat Keamanan Konsumsi Residu Karbamat dalam Buah dan Sayur Menurut Analisis Pascakolom Kromatografi Cair Kinerja Tinggi

    Directory of Open Access Journals (Sweden)

    Bambang Wispriyono

    2013-02-01

    Full Text Available Karbamat merupakan salah satu jenis pestisida yang banyak digunakan untuk membasmi hama buah dan sayur. Untuk menentukan bahwa residu karbamat dalam sayuran masih aman dikonsumsi manusia, telah dilakukan analisis beberapa residu karbamat seperti metomil, karbaril, karbofuran, dan propoksur. Sampel-sampel tomat, apel, selada air, kubis, dan sawi hijau dikumpulkan dari tiga supermarket dan satu pasar tradisional di Depok, Jawa Barat. Analisis dilakukan serempak untuk ke empat residu karbamat menggunakan kromatografi cair kinerja tinggi denganpereaksi o-ftalaldehida dan 2-merkaptoetanol dalam reaktor pascakolom dengan detektor fluoresensi. Dari sampel-sampel buah dan sayur yang dianalisis, hanya sawi hijau asal pasar tradisional yang positif mengandung propoksur dengan kadar 1,2 mg/25 gram berat basah (0,048 mg/g berat basah. Dengan Acceptable Daily Intake(ADI propoksur 0,005 mg/kg berat badan/hari, konsumsi sawi hijau harian seberat 20 g/hari masih cukup aman dari gangguan kesehatan akibat pajanan kronik propoksur dengan margin of safety 298,7 (> 100 sebagai batas aman. Carbamat is a group of pesticides which is commonly used to control fruits and vegetables pests. To determine that carbamat residues in fruits and vegetables are safe for human consumption, carbamate residues such as methomyl, carbaryl, carbofuran, and propoxur in vegetables and fruits have been analyzed. Samples of tomato, apple, water lettuces, cabbage, and mustard greens were collected from three supermarkets and one traditional market in Depok, West Java. The analysis was carried out simultaneously for all four carbamate residues by high performance liquid chromatography using o-phtaladehyde and 2 mercaptoethanol reagents in post-column reactor with a fluorescence detector. Of fruits and vegetable samples analyzed, only mustard greens from traditional market positively containe propoxur at 1.2 mg/ 25 gram wet weight (0,048 mg/gram wet weight. With Acceptable Daily Intake (ADI

  17. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  18. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  19. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  20. Fast reactor parameter optimization taking into account changes in fuel charge type during reactor operation time

    International Nuclear Information System (INIS)

    Afrin, B.A.; Rechnov, A.V.; Usynin, G.B.

    1987-01-01

    The formulation and solution of optimization problem for parameters determining the layout of the central part of sodium cooled power reactor taking into account possible changes in fuel charge type during reactor operation time are performed. The losses under change of fuel composition type for two reactor modifications providing for minimum doubling time for oxide and carbide fuels respectively, are estimated

  1. ANALYSIS OF GAMMA HEATING AT TRIGA MARK REACTOR CORE BANDUNG USING PLATE TYPE FUEL

    Directory of Open Access Journals (Sweden)

    Setiyanto Setiyanto

    2016-10-01

    Full Text Available ABSTRACT In accordance with the discontinuation of TRIGA fuel element production by its producer, the operation of all TRIGA type reactor of at all over the word will be disturbed, as well as TRIGA reactor in Bandung. In order to support the continuous operation of Bandung TRIGA reactor, a study on utilization of fuel plate mode, as used at RSG-GAS reactor, to replace the cylindrical model has been done. Various assessments have been done, including core design calculation and its safety aspects. Based on the neutronic calculation, utilization of fuel plate shows that Bandung TRIGA reactor can be operated by 20 fuel elements only. Compared with the original core, the new reactor core configuration is smaller and it results in some empty space that can be used for in-core irradiation facilities. Due to the existing of in-core irradiation facilities, the gamma heating value became a new factor that should be evaluated for safety analysis. For this reason, the gamma heating for TRIGA Bandung reactor using fuel plate was calculated by Gamset computer code. The calculations based on linear attenuation equations, line sources and gamma propagation on space. Calculations were also done for reflector positions (Lazy Susan irradiation facilities and central irradiation position (CIP, especially for any material samples. The calculation results show that gamma heating for CIP is significantly important (0,87 W/g, but very low value for Lazy Susan position (lest then 0,11 W/g. Based on this results, it can be concluded that the utilization of CIP as irradiation facilities need to consider of gamma heating as data for safety analysis report. Keywords: gamma heating, nuclear reactor, research reactor, reactor safety.   ABSTRAK Dengan dihentikannya produksi elemen bakar reaktor jenis Triga oleh produsen, maka semua reaktor TRIGA di dunia terganggu operasinya, termasuk juga reaktor TRIGA 2000 di Bandung. Untuk mendukung pengoperasian reaktor TRIGA Bandung

  2. ANALISIS DAN MODEL STRATEGI PENINGKATAN DAYA SAING PRODUK EDAMAME BEKU

    Directory of Open Access Journals (Sweden)

    Sandryas Alief Kurniasanti

    2015-03-01

    Full Text Available Jember regency is a agricultural and plantation central area. The soybean plant is principal commodity that competes fiercely with production of corn. PT Mitratani Dua Tujuh (PT MT 27 try to find new technology by processing edamame to frozen edamame that focus in the export market. The primary market of frozen edamame besides domestic market is Japan. The aim of this research is to analyze competitiveness and formulated the priority of competitiveness alternative strategy on frozen edamame product in PT MT 27. The research method used is the analysis of competitiveness by using revealed comparative advantage to know the export performance of the product on the world market then analyze a factor of competition by using Diamond Porter's Theory. Alternative strategies are resulted from the SWOT analysis and priorities are determined by using analytical hierarchy process from the expert source. The research results about alternative strategy priority to increase the competitiveness of frozen edamame products in PT MT 27 are: (1 market diversification, (2 product diversification, (3 improve cooperation overseas, (4 develop a research and development division, (5 develop corporate social responsibility, (6 proper financial management, and (7 to develop an agricultural area greenhouse-based to avoid bad weather as tropical country. Managerial implications of this research are expanding existing markets, and develop type of product produced to satisfy the export market and also savings cost production. Keywords: competitiveness, frozen edamame, Mitratani Dua Tujuh, competitiveness strategiesABSTRAKKabupaten Jember merupakan sentra  daerah pertanian dan perkebunan. Tanaman kedelai merupakan komoditas utama yang bersaing ketat dengan produksi jagung. PT Mitratani Dua Tujuh (PT MT 27 mencoba untuk mencari terobosan baru yaitu dengan mengolah edamame menjadi edamame beku siap makan. Pasar utama edamame beku ini selain pasar domestik adalah Jepang. Tujuan

  3. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  4. CFD analysis for the hydrogen transport in the primary contention of a BWR using the codes OpenFOAM and Gas-Flow; Analisis CFD para el transporte de hidrogeno en la contencion primaria de un reactor BWR usando los codigos OpenFOAM y GasFlow

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez P, D. A.

    2014-07-01

    using a limited number of semi-empirical data, and instead, mathematical relationships are used taking into account the various physical phenomena as well the interactions that occur among them, such as heat transfer between the fluid and the solid walls condensation of water vapor on the walls, the turbulent effects in areas of restricted passage, etc. Taking into account these advantages, this study presents a qualitative and quantitative comparison between the CFD codes OpenFOAM and Gas-Flow related to the transport phenomena of Hydrogen and other gases in the primary containment of a BWR reactor. Gas-Flow is a code of commercial license that is well validated, developed in Germany to analyze the transport of gases in nuclear reactor containments. On the other hand, OpenFOAM is an open source CFD code offering several solvers for different phenomena assessments, in this work, the reacting Foam solver is used because it has a strong similarity to the intended application of Hydrogen transport. In this thesis the results obtained using the reacting Foam solver of OpenFOAM for the calculation of transport of Hydrogen are compared with the results of the Gas-Flow code in order to assess if it is feasible to use the open source code OpenFOAM in the case of Hydrogen transport in primary containment of a BWR reactor. Some differences in the qualitative and quantitative results from both codes were found, the differences (with a maximum error rate of 4%) in the quantitative results were found are small and are considered more than acceptable for this type of analysis, moreover, these differences are mainly attributed to the transport models used, mainly because OpenFOAM uses a homogeneous mixture model and Gas-Flow a heterogeneous one. Implementing appropriate solvers in codes like OpenFOAM has the goal to develop own tools that are applicable to the transport of Hydrogen in the primary containment of a BWR reactor and thus, to gain some independence while not relying on

  5. ANALISIS PENERAPAN 8 STANDAR NASIONAL PENDIDIKAN PADA SMP NEGERI 2 DOLOPO KABUPATEN MADIUN

    Directory of Open Access Journals (Sweden)

    Luki Eko Cahyono

    2015-10-01

    Penelitian ini menggunakan desain penelitian Deskriptif Kualitatif. Jenis penelitian adalah studi kasus. Data yang digunakan adalah data Primer. Teknik pengumpulan data yang digunakan adalah wawancara dan dokumentasi. Teknik keabsahan data adalah Triangulasi Sumber dan teknik analisis data yang digunakan adalah pendekatan Strengths, Weakness, Opportunities, dan Threats (Analisis SWOT. Kesimpulan penelitian ini adalah (1 Hasil analisis Strenght (Kekuatan adalah sekolah sudah merencanakan, melaksanakan dan mengevaluasi sebagian besar indikator dalam pemenuhan Standar Nasional Pendidikan sehingga meningkatkan mutu pendidikan sekolah. (2 Hasil analisis Weakness (kelemahan adalah keterbatasan anggaran dana dan sumber daya manusia baik peserta didik, pendidik, maupun tenaga kependidikan dalam pemenuhan seluruh unsur Standar Nasional Pendidikan. (3 Hasil analisis Opportunities (peluang adalah Pemberian workshop dan pelatihan kepada pendidik dan tenaga kependidikan meningkatkan kualitas pendidikan sekolah, dan perencanaan, pelaksanaan pembiayaan serta evaluasi penganggaran yang baik memberikan dampak positif terhadap semua unsur operasional sekolah maupun sarana prasarana sekolah. (4 Hasil analisis Threats (Tantangan adalah perencanaan, sosialisasi, pelaksanaan dan evaluasi serta tindak lanjut yang tidak dijalankan dengan manajemen yang baik dalam upaya pemenuhan Standar Nasional Pendidikan akan menghambat peningkatan kualitas pendidikan sekolah. (5 Hasil penerapan Standar Nasional Pendidikan pada SMP Negeri 2 Dolopo menggunakan analisis SWOT menunjukkan bahwa Kekuatan lebih besar daripada Kelemahan dan Peluang lebih besar dari Ancaman, yang berarti Standar Nasional Pendidikan telah terpenuhi dan menghasilkan Akreditasi Sekolah nilai A.

  6. Methods of Containment Adopted for the EL4 Reactor and Projected Heavy-Water, Gas-Cooled Plants; Mode de Confinement Adopte pour le Reacteur EL4 et les Projets de Centrales Eau Lourde-Gaz

    Energy Technology Data Exchange (ETDEWEB)

    Schulhof, P.; Justin, F. [Commissariat a l' Energie Atomique, Paris (France)

    1967-09-15

    After a brief description of the plant, the paper explains the principles adopted for preventing the release of waste gas, from the EL4 reactor and refers to some of the difficulties associated with this type of containment. From the economic standpoint, the authors present the results of a comparative civil engineering study of pre-stressed concrete and steel shells for a projected 60 MW(e) power station, giving various values for accidental pressures. They demonstrate the influence of the stress values adopted. (author) [French] Les auteurs rappellent les principes adoptes dans le reacteur EL4 pour le confinement des rejets gazeux, apres une description sommaire des installations. Suivent quelques aspects des difficultes introduites par ce type de confinement. Dans le domaine economique, ils presentent le resultat d'une etude comparative de genie civil d'enceintes en beton precontraint et en acier pour un projet de centrale de 600 MW(e), avec diverses valeurs de pression accidentelle. Dans cette etude, ils font ressortir l'influence des valeurs admises pour le taux de travail des materiaux. (author)

  7. ANALISIS SENSITIVITAS TURBULENSI ALIRAN PADA KANAL BAHAN BAKAR PWR BERBASIS CFD

    Directory of Open Access Journals (Sweden)

    Endiah Puji Hastuti

    2015-04-01

    Full Text Available Turbulensi aliran pendingin pada proses perpindahan panas berfungsi untuk meningkatkan nilai koefisien perpindahan panas, tidak terkecuali aliran dalam kanal bahan bakar. Program CFD (CFD=computational fluid dynamics, FLUENT adalah program komputasi berbasis elemen hingga (finite element yang mampu memprediksi dan menganalisis fenomena dinamika aliran fluida secara teliti. Program perhitungan CFD dipilih dalam penelitian ini karena selain akurat juga dapat memberikan visualisasi dengan baik. Penelitian ini bertujuan untuk memahami karakteristika perpindahan panas, massa dan momentum dari dinding rod bahan bakar ke pendingin secara visual, pada medan temperatur, medan tekanan, dan medan energi kinetika pendingin, sebagai fungsi dinamika aliran di dalam kanal, pada kondisi tunak dan transien. Analisis dinamika aliran pada kanal bahan bakar PWR berbasis CFD dilakukan dengan menggunakan sampel data reaktor PWR dengan daya 1000 MWe dengan susunan bahan bakar 17x17. Untuk menguji sensitivitas persamaan aliran yang sesuai dengan model aliran turbulen pada kanal bahan bakar dilakukan pemodelan dengan menggunakan persamaan k-omega (Ƙ-ω, k-epsilon (Ƙ-ε, dan Reynold stress model (RSM. Pada analisis sensitivitas aliran turbulen di dalam kanal digunakan model mesh hexahedral dengan memilih tiga geometri sel yang masing masing berukuran 0,5 mm; 0,2 mm dan 0,15 mm. Hasil analisis menunjukkan bahwa pada analisis kondisi tunak (steady state, terdapat hasil yang mirip pada model turbulen Ƙ-ε standard dan Ƙ-ω standard. Pengujian terhadap kriteria Dittus Boelter untuk bilangan Nusselt menunjukkan bahwa model Reynold stress model (RSM direkomendasikan. Analisis sensitivitas terhadap geometri mesh antara sel yang berukuran 0,5 mm, 0,2 mm dan 0,15 mm, menunjukkan bahwa geometri sel sebesar 0,5 mm telah mencukupi. Aliran turbulen berkembang penuh telah tercapai pada model LES dan DES, meskipun hanya dalam waktu singkat (3 s, model LES memerlukan waktu komputasi

  8. FBR type reactor

    International Nuclear Information System (INIS)

    Inoue, Kotaro; Kawashima, Katsuyuki; Zuketen, Atsushi.

    1982-01-01

    Purpose: To flatten the power distribution of a reactor core and shorten the breeding time. Constitution: The reactor core comprises a core region having fission products, an outer blanket region surrounding the outer side of the core region and having fertile material and an inner blanket region disposed within the core region and having fertile material. The axial thickness of the inner blanket region is made greater at the central portion and smaller at the peripheral portion of the inner blanket region, and the outermost peripheral end at the peripheral portion of the inner blanket region is opposed by way of the core region to the outer blanket region. In such an arrangement, the power decrease in the peripheral portion of the core region can be suppressed to thereby flatten the power distribution in the reactor core and shorten the breeding time. (Moriyama, K.)

  9. Reactor utilization; Eksploatacija reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel.

  10. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

    The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

  11. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

    A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

  13. Analisis Penerimaan PAD Pada Dinas Perikanan dan Peternakan Kabupaten Tebo

    Directory of Open Access Journals (Sweden)

    Eko Purnarianto

    2016-06-01

    Full Text Available Abstract. This study aims to analyze potential, efficiency, effectivity and contribution of PAD admission at Department of Fishery and Animal Husbandry in Tebo Regencyincluding the strategy establishment to increase its revenue.The analysis used is a potential formula, efficiency ratio, effectivity ratio, contributions ratio and SWOT analysis.The results shows that the potential revenue of retribution slaughterhouse (RPH, the potential sales of livestock, and potential sales fishery product are beyond the current target. The efficiency level of retribution slaughterhouse (RPH and sales of fishery product is poor, but the sales of livestock is very efficient. Effectivity level of livestock and fishery product sales are low, whileretribution slaughterhouses(RPH is not effective regarded to its potential  but in the contrary for its target. Contribution of PAD admission of Fishery and Animal Husbandry Department is very low regarded Tebo Regency PAD. The result of SWOT analysis of retribution slaughter house (RPH admission using WO (Weakness-Opportunity strategy, livestock sales using SO (Strength-Oppurtunity strategy, and fishery product sales using ST (strength-threat strategy. Keywords: Retribution SlaughterHouse (RPH, Sales of Fishery, Livestock Sales, SWOT Analysis   Abstrak. Penelitian ini bertujuan untuk menganalisis potensi, efisiensi, efektivitas dan kontribusi penerimaan PAD pada Dinas Perikanan dan Peternakan Kabupaten Teboserta menetapkan strategi untuk peningkatan penerimaan PAD. Analisis yang digunakan adalah rumus potensi, rasio efisiensi, rasio efektivitas, rasio kontribusi dan analisis SWOT.Hasil penelitian menunjukkan bahwa potensi penerimaan retribusi rumah potong hewan (RPH, potensi penjualan hasil peternakan, potensi  penjualan hasil perikanan lebih besar dari target yang telah ditetapkan. Tingkat efisiensi retribusi RPH dan penjualan hasil perikanan tidak efisien, penjualan hasil peternakan sangat efisien. Tingkat

  14. Identifiksi Sebaran Litologi berdasarkan Analisis Data Resistivitas di Gunung Wungkal

    Directory of Open Access Journals (Sweden)

    Nurul Dzakiya

    2017-05-01

    Full Text Available Analisis data untuk mengidentifikasi sebaran litologi yang memiliki potensi bahan galian industri di Daerah Gunung Wungkal Yogyakarta dengan menggunakan metode resistivitas dan survei geologi permukaan telah dilakukan. Hasil korelasi kedua data tersebut menunjukkan sebaran litologi merupakan pelapukan intrusi batuan beku yang kemudian menghasilkan material lempung (6,0-10 m, lempung pasiran (11-30 m dan lapukan batuan diorit (30-55 m yang berada di kedalaman berbeda. Ketebalan batuan di permukaan sekitar 225-231 meter berdasarkan penampang peta geologi dengan arah sebaran dari Barat Laut hingga Tenggara. Proses pelapukan dan alterasi di daerah ini intensif (alterasi argilik dengan jenis morfologi perbukitan intrusi terdenudasi dan dataran Alluvial.

  15. ANALISIS KEAMANAN DATA PADA BLOCK CIPHER ALGORITMA KRIPTOGRAFI RSA

    Directory of Open Access Journals (Sweden)

    Fadhillah Azmi

    2017-01-01

    Full Text Available Komunikasi adalah proses dasar dari pertukaran informasi. Efektifitas komunikasikomputer secara umum adalah melalui internet atau beberapa saluran komunikasi lainnya.Tujuan utama tulisan ini adalah berdasarkan pada analisis hasil yang diberikan Weinermengatakan bahwa jika private key d digunakan dalam algoritma kriptografi RSA kurang darin292, maka sistem tersebut kurang aman. Di sini penulis menganalisa pada hasil yang diberikanoleh Weiner dan mencoba untuk meningkatkan range dari private key d sampai n0.5. Karena nadalah perkalian p dan q, yang mana bilangan relative prima. Sehingga mempengaruhi kinerjaenkripsi algoritma yang lebih aman.

  16. Analisis Derau dalam Perancangan Rangkaian Terintegrasi Op-Amp

    Directory of Open Access Journals (Sweden)

    Siti Sendari

    2009-02-01

    Full Text Available Perancangan IC Op-Amp, memerlukan spesifikasi-spesifikasi yang meliputi parameter proses dan parameter perancangan. Dalam menentukan parameter perancangan, derau merupakan suatu hal yang tidak bisa ditinggalkan, karena derau dapat menentukan keandalan perancangan. Untuk menganalisis derau pada IC Op-Amp langkah pertama yang harus diketahui adalah sumber-sumber derau, setelah itu dilakukan analisis derau baik secara teoritis maupun secara simulasi untuk mengetahui derau yang mungkin terjadi dalam perancangan IC, apakah sudah sesuai dengan spesifikasi yang ditentukan atau tidak. Untuk simulasi derau dapat dilakukan dengan program Spice.

  17. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Sekimizu, Koichi

    1980-01-01

    Purpose: To improve the performance and secure the safety of a nuclear reactor by rapidly computing and display the power density in the nuclear reactor by using a plurality of processors. Constitution: Plant data for a nuclear reactor containing the measured values from a local power monitor LPRM are sent and recorded in a magnetic disc. They are also sent to a core performance computer in which burn-up degree distribution and the like are computed, and the results are sent and recorded in the magnetic disc. A central processors loads programs to each of the processors and applies data recorded in the magnetic disc to each of the processors. Each of the processors computes the corresponding power distribution in four fuel assemblies surrounding the LPRM string by the above information. The central processor compiles the computation results and displays them on a display. In this way, power distribution in the fuel assemblies can rapidly be computed to thereby secure the improvement of the performance and safety of the reactor. (Seki, T.)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Batheja, P.; Huber, R.; Rau, P.

    1985-01-01

    Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

  19. In situ reactor

    Science.gov (United States)

    Radtke, Corey William; Blackwelder, David Bradley

    2004-01-27

    An in situ reactor for use in a geological strata, is described and which includes a liner defining a centrally disposed passageway and which is placed in a borehole formed in the geological strata; and a sampling conduit is received within the passageway defined by the liner and which receives a geological specimen which is derived from the geological strata, and wherein the sampling conduit is in fluid communication with the passageway defined by the liner.

  20. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  1. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    1982-09-01

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.) [de

  2. MARS: Mirror Advanced Reactor Study

    International Nuclear Information System (INIS)

    Logan, B.G.

    1984-01-01

    A recently completed two-year study of a commercial tandem mirror reactor design [Mirror Advanced Reactor Study (MARS)] is briefly reviewed. The end plugs are designed for trapped particle stability, MHD ballooning, balanced geodesic curvature, and small radial electric fields in the central cell. New technologies such as lithium-lead blankets, 24T hybrid coils, gridless direct converters and plasma halo vacuum pumps are highlighted

  3. ANALISIS NERACA PERDAGANGAN MIGAS DAN NON MIGAS INDONESIA TERHADAP VOLATILITAS CADANGAN DEVISA 2003-2013

    Directory of Open Access Journals (Sweden)

    Haniyah Safitri

    2014-10-01

    Full Text Available Abstrak ___________________________________________________________________ Cadangan devisa adalah asset ataupun aktiva dari bank sentral. Cadangan devisa tersimpan dalam mata uang asing seperti dolar, euro, yen dan digunakan untuk perdagangan internasional dan membiayai perekonomian sebuah negara. Cadangan ini tersimpan dalam neraca pembayaran. Krisis Asia 1997 dulu, membuat Indonesia mengalami krisis moneter yang berkepanjangan. Hal ini berdampak terhadap perdagangan internasional (Ekspor Impor dan mengalami krisi nilai tukar. Mempengaruhi perekonomian kita dan mengakibatkan kita kehilangan kepercayaan negara lain terkhususnya Negara Dunia Pertama. Judul jurnal ini adalah “ Analisis Neraca Perdagangan Migas dan Nonmigas Indonesia Terhadap Volatilitas Cadangan Devisa “. Neraca perdagangan migas dan nonmigas Indonesia mengakibatkan volatilitas yang berdampak tergerusnya cadangan devisa dan melemahnya nilai tukar rupiah. Abstract ___________________________________________________________________ Foreign exchange reserves is an asset of central Bank. It has saved by reserve currency like dolar, euro, yen and uses for beganing international trade and covered the economic of the country. It saved in a Balance Payment (BOP Prior to the 1997 Asia economic crisis, make Indonesia got a long time crisis monetary. It effected to the international trade (Export and Import and got the exchange rate crisis. The influence our economy and we lost trust from another country especially’ The First Country’ and causes decrease our Balance Of Payment. The title of this journal is "Analysis of Oil and Non-oil Trade Balance Indonesia Against Volatility Reserves". Oil and non-oil trade balance volatility impacting Indonesia resulted in erosion of foreign reserves and a weakening of the exchange rate. © 2014 Universitas Negeri Semarang

  4. The advanced MAPLE reactor concept

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Lee, A.G.; Gillespie, G.E.; Smith, H.J.

    1989-01-01

    High-flux neutron sources are continuing to be of interest both in Canada and internationally to support materials testing for advanced power reactors, new developments in extracted-neutron-beam applications, and commercial production of selected radioisotopes. The advanced MAPLE reactor concept has been developed to meet these needs. The advanced MAPLE reactor is a new tank-type D 2 O reactor that uses rodded low-enrichment uranium fuel in a compact annular core to generate peak thermal-neutron fluxes of 1 x 10 19 n·s -1 in a central irradiation rig with a thermal power output of 50 MW. Capital and incremental development costs are minimized by using MAPLE reactor technology to the greatest extent practicable

  5. Safety equipment in a reactor

    International Nuclear Information System (INIS)

    Shiratori, Hirozo; Ishiyama, Satoshi; Ugawa, Yukio.

    1976-01-01

    Object: To safely retain, even if fuel should be molten and flown through the bottom of a container in a reactor, the molten fuel to remove heat generation of the fuel to prevent occurrence of a critical trouble. Structure: A reactor container housing a core and coolant has thereunder a separation dome in a central portion thereof and a partitioning plate coaxially and circularly disposed in the periphery of the separation dome, with a tray formed of magnesium oxide being disposed. Further, a cooling path system is provided so as to surround the tray. The cooling path system and the reactor container are surrounded and protected by a reactor wall provided with heat insulating refractory bricks, a coolant pouring system extends through the reactor wall, and the coolant is supplied to the tray. (Furukawa, Y.)

  6. FRACTURE MECHANICS UNCERTAINTY ANALYSIS IN THE RELIABILITY ASSESSMENT OF THE REACTOR PRESSURE VESSEL: (2D SUBJECTED TO INTERNAL PRESSURE

    Directory of Open Access Journals (Sweden)

    Entin Hartini

    2016-06-01

    Full Text Available ABSTRACT FRACTURE MECHANICS UNCERTAINTY ANALYSIS IN THE RELIABILITY ASSESSMENT OF THE REACTOR PRESSURE VESSEL: (2D SUBJECTED TO INTERNAL PRESSURE. The reactor pressure vessel (RPV is a pressure boundary in the PWR type reactor which serves to confine radioactive material during chain reaction process. The integrity of the RPV must be guaranteed either  in a normal operation or accident conditions. In analyzing the integrity of RPV, especially related to the crack behavior which can introduce break to the reactor pressure vessel, a fracture mechanic approach should be taken for this assessment. The uncertainty of input used in the assessment, such as mechanical properties and physical environment, becomes a reason that the assessment is not sufficient if it is perfomed only by deterministic approach. Therefore, the uncertainty approach should be applied. The aim of this study is to analize the uncertainty of fracture mechanics calculations in evaluating the reliability of PWR`s reactor pressure vessel. Random character of input quantity was generated using probabilistic principles and theories. Fracture mechanics analysis is solved by Finite Element Method (FEM with  MSC MARC software, while uncertainty input analysis is done based on probability density function with Latin Hypercube Sampling (LHS using python script. The output of MSC MARC is a J-integral value, which is converted into stress intensity factor for evaluating the reliability of RPV’s 2D. From the result of the calculation, it can be concluded that the SIF from  probabilistic method, reached the limit value of  fracture toughness earlier than SIF from  deterministic method.  The SIF generated by the probabilistic method is 105.240 MPa m0.5. Meanwhile, the SIF generated by deterministic method is 100.876 MPa m0.5. Keywords: Uncertainty analysis, fracture mechanics, LHS, FEM, reactor pressure vessels   ABSTRAK ANALISIS KETIDAKPASTIAN FRACTURE MECHANIC PADA EVALUASI KEANDALAN

  7. Study and Construction of the Metal Vessels for the Reactors of the EDF1 and EDF2 Sectors at Chinon; Etude et construction des caissons metalliques des reacteurs des tranches EDF1 et EDF2 de la centrale de Chinon; Izuchenie i konstruktsiya metallicheskikh korpusov reaktorov pervoj i vtoroj chasti programm ehlektrostantsij; Estudio y construccion de los recipientes metalicos de los reactores EDF1 y EDF2 de la central de Chinon

    Energy Technology Data Exchange (ETDEWEB)

    Lamiral, G.; Millot, R.; Passerieux, P. [Electricite de France, Clamart, Seine (France)

    1963-10-15

    The first two natural uranium-graphite-C0{sub 2} reactors at the Chinon station have metal vessels of thick manganese-molybdenum steel plate. The studies carried out on these vessels raised certain problems, particularly in connection with the design and dimensions of the port reinforcements. The reinforcements for the control-rod channels and fuel ports were studied on mock-ups and the results obtained were checked on the completed reactors during hydraulic tests. The type of construction initially used for the EDF1 vessel was relatively simple. The plates to be welded were locally preheated, and the vessel was not supposed to undergo more than one stress-relief heat treatment after completion of all the welding. Serious cracks developed, however, and it became necessary to alter the whole method of construction. In particular, the welding was now done after overall preheating and the vessel was subjected to multiple stress-relief treatments. This made it possible to fabricate the vessels for EDF1 and EDF2, but at the same time imposed certain limitations which considerably complicated work on the site. (author) [French] Les reacteurs a uranium naturel, graphite et gaz carbonique des deux premieres tranches de la Centrale de Chinon comportent des caissons metalliques realises a partir de toles de fortes epaisseurs, en acier au manganese-molybdene. Les etudes de ces paissons ont pose certains problemes, notamment en ce qui concerne les renforts d'ouvertures. Les renforts des passages des barres de controle et des orifices de chargement ont ete etudies sur maquette et les resultats obtenus ont ete controles sur les ouvrages termines lors des epreuves hydrauliques. Le mode de construction initialement utilise pour le caisson de la tranche EDF1 etait relativement simple; les toles a souder etaient prechauffees localement et le caisson ne devait subir qu'un seul traitement thermique de detente, apres execution de toutes les soudures. Une fissuration importante en cours

  8. Klasifikasi Kecamatan Berdasarkan Nilai Akhir SMA/MA di Kabupaten Aceh Selatan Menggunakan Analisis Diskriminan

    Directory of Open Access Journals (Sweden)

    Fitriana A.R.

    2015-11-01

    Full Text Available Analisis diskriminan merupakan bagian dari analisis peubah ganda. Analisis diskriminan digunakan untuk memodelkan variabel tak bebas yang bersifat kualitatif dengan variabel bebas yang bersifat kuantitatif. Pada penelitian ini, analisis diskriminan lebih dari dua kelompok diterapkan pada data nilai akhir SMA/MA di Kabupaten Aceh Selatan yang bertujuan untuk mendapatkan model untuk pengklasifikasian kecamatan. Pengklasifikasian ini bertujuan untuk melihat perbedaan kualitas siswa SMA/MA yang berada di masing-masing kecamatan Kabupaten Aceh Selatan berdasarkan data nilai akhir. Variabel tak bebas yang digunakan berupa klasifikasi kecamatan berdasarkan rata-rata jumlah nilai akhir SMA/MA yang berada di masing-masing kecamatan yang dibentuk dengan K-Means Cluster. Sedangkan variabel bebas yang digunakan adalah data rata-rata nilai akhir SMA/MA untuk setiap mata pelajaran yang diujiankan pada masing-masing jurusan setiap kecamatan. Model yang didapatkan adalah dua model diskriminan untuk jurusan IPA dan IPS.

  9. La financial education nella regione Puglia: analisi e prospettive di intervento

    OpenAIRE

    A. Garzoni; V. Nastasi

    2010-01-01

    Analisi del contesto e delle principali tematiche di financial education affrontate a livello internazionale e nazionale, valutazione delle opportunità e degli aspetti critici, il progetto pilota nella regione Puglia e le nuove idee di progetto da realizzare

  10. ANALISIS FINANSIAL DAN KELEMBAGAAN RANTAI NILAI MEBEL MAHONI JEPARA

    Directory of Open Access Journals (Sweden)

    Nunung Parlinah

    2011-12-01

    Full Text Available Industri mebel umumnya termasuk dalam industri kecil dan menengah. Selain berperan dalam penerimaan devisa, bisnis di bidang mebel ini juga menciptakan lapangan kerja bagi masyarakat terutama di Kabupaten Jepara. Adanya hubungan (pemberi kepercayaan - (penerima kepercayaan yang terjadi antar aktor atau pelaku di dalam rantai berpengaruh terhadap besarnya distribusi nilai tambah yang diperoleh oleh masingmasing pelaku di sepanjang rantai nilai Tujuan dari penelitian ini adalah mengidentifikasi kelembagaan (aturan yang terjadi antar pelaku di sepanjang rantai nilai mebel mahoni Jepara dan menentukan skenario kebijakan yang dapat mendukung bagi kelestarian industri mebel Jepara. Data yang digunakan meliputi data primer dan data sekunder. Analisis data meliputi identifikasi aktor dan kelembagaan (aturan yang terjadi antar pelaku serta analisis manfaat biaya yang terdiri dari NVP, BCR dan IRR. Hasil penelitian menunjukkan bahwa (1 para pengrajin ( memproduksi mebelnya lebih didasarkan pada pesanan pembeli ( . agent principal Asymetic information yang terjadi antara pedagang kayu dan petani juga telah mengakibatkan posisi petani sebagai (2 Nilai NPV, BCRdan IRR untuk tiap pelaku berbeda-beda tetapi nilai-nilai tersebut mengindikasikan bahwa pola kemitraan yang terjadi antar pelaku dalam rantai nilai mebel mahoni saat ini sudah efektif. Skenario kebijakan yang dapat diterapkan adalah kebijakan yang bersifat insentif bagi petani hutan rakyat, peningkatan kemampuan pengrajin di bidang pemasaran; dan membangun aksi kolektif diantara pengrajin. price taker;

  11. Analisis Rugi Daya Pada Penyulang Bangli Dengan Beroperasinya PLTS Kayubihi

    Directory of Open Access Journals (Sweden)

    I GN Dion Adiputra

    2015-06-01

    Full Text Available Analisis rugi daya pada Penyulang Bangli dilakukan untuk mengetahui perbanding an rugi daya pada jaringan distribusi setelah penempatan pembangkit tersebar jenis PLTS berkapasitas 1 MWp. Lokasi penempatan PLTS ditentukan berdasarkan analisis sensitivitas bus. Nilai sensitivitas bus(?didapat dengan cara membandingkan nilai rugi daya pada sistem dengan total beban yang terhubung pada bus. Penelitian ini menggunakan simulasi aliran daya dengan metode aliran daya Newton-Raphson. Hasil penelitian menunjukkan bus TK 0041 memiliki sensitivitas terbesar dengan nilai ?= 0,178. Dari hasil simulasi aliran daya, penempatan PLTS 1MWp pada lokasi alternatif 1 menghasilkan rugi daya minimum pada Penyulang Bangli yaitu 103,1 kW atau 3,3% dari total suplai daya 3071 kW. Pemasangan PLTS dapat menurunkan rugi daya pada Penyulang Bangli sebesar 57 kW dari total rugi daya pada kondisi tanpa PLTS yaitu 160,1 kW. Bila dibandingkan dengan kondisi eksisting, penem patan PLTS pada lokasi alternatif 1 memiliki selisih rugi daya 7,3 kW lebih kecil dari total rugi daya yang dihasilkan kondisi eksisting sebesar 110,4kW.

  12. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

    1979-08-01

    Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

  13. Reactor safety

    International Nuclear Information System (INIS)

    Butz, H.P.; Heuser, F.W.; May, H.

    1985-01-01

    The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  15. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

    Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

  16. RA Reactor

    International Nuclear Information System (INIS)

    1989-01-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels [sr

  17. Reactor physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1998-01-01

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  18. Pembuatan Dan Analisis Exciter Generator Rf Untuk Siklotron Proton Decy-13

    OpenAIRE

    Prajitno, Prajitno

    2011-01-01

    PEMBUATAN DAN ANALISIS EXCITER GENERATOR RF UNTUK SIKLOTRON PROTON DECY-13.Telah dilakukan analisis dan pembuatan exciter generator RF untuk siklotron proton 13MeV. Generator RFakan digunakan sebagai sumber tegangan pemercepat bolak-Balik siklotron DECY-13 rancangan PTAPBBATAN.Berdasarkan dokumen rancangan dasar yang telah dibuat siklotron Decy-13 akan menggunakanmedan magnet 1,275 Tesla, sehingga frekuensi generator RF bila menggunakan harmonik keempat adalah77,667 MHz. Salah satu teknik pem...

  19. ANALISIS HARGA POKOK PRODUKSI DAN PENERAPAN TARGET COSTING PADA UD WAJUKU MAKASSAR

    OpenAIRE

    -, CHAIDIR HAFID

    2017-01-01

    ABSTRAK Analisis Harga Pokok Produksi dan Penerapan Target Costing pada UD Wajuku Makassar The Analysis of The Cost of Goods Manufactured and Implementation of Target Costing in UD Wajuku Makassar Chaidir Hafid Asri Usman Syahrir Penelitian ini bertujuan untuk mengetahui perhitungan harga pokok produksi baju kaos polos sebelum dan setelah penerapan metode target costing pada UD Wajuku Makassar. Metode pengumpulan data yang digunakan adalah dokumentasi. Metode analisis dat...

  20. PENGUKURAN KINERJA PERUSAHAAN PT. HADJI KALLA DENGAN MENGGUNAKAN ANALISIS ECONOMIC VALUE ADDED

    OpenAIRE

    2013-01-01

    Tujuan dari penelitian ini adalah mengetahui kinerja Economic Value Added (EVA) yang dicapai oleh perusahaan PT. Hadji Kalla, sedangkan metode analisis yang digunakan dalam penelitian ini adalah analisis perkembangan Economic Value Added (EVA), Net Operating Profit After Tax (NOPAT) dan The purpose of this study was to determine the performance of the Economic Value Added (EVA), which is achieved by the company PT. Hadji Kalla...

  1. Reactor core

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

  2. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

    A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

  3. Reactor container

    International Nuclear Information System (INIS)

    Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

    1997-01-01

    In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  5. ANALISIS MODEL PREDIKSI AWAL MUSIM HUJAN DI SULAWESI SELATAN

    Directory of Open Access Journals (Sweden)

    Alimatul Rahim

    2016-03-01

    Full Text Available Model prediksi awal musim hujan merupakan salah satu kunci yang dapat digunakan untuk mengurangi resiko kegagalan panen padi yang disebabkan oleh faktor iklim di provinsi Sulawesi Selatan. Model prediksi awal musim hujan dibangun  dengan menggunakan data curah hujan observasi Sulawesi Selatan dan anomali suhu muka laut di kawasan Pasifik dan perairan Sulawesi. Pada studi ini dilakukan analisis pemilihan stasiun hujan observasi, penentuan awal musim hujan, analisis komponen utama dan pengelompokan, analisis korelasi awal musim hujan terhadap anomali suhu muka laut, pembangunan model untuk prediksi awal musimhujan dan verifikasi model.Hasil analisis awal musim hujan menunjukkan setiap stasiun hujan mempunyai perbedaan awal musim hujan dengan rata-rata jatuh pada Julian Date (JD ke-348 (14 Desember. Berdasarkan hasil analisis PCA dan cluster, diperoleh bahwa di Sulawesi Selatan terbagi menjadi 3 cluster wilayah. Cluster 1 mempunyai pola hujan lokal, sedangkan cluster 2 dan 3 mempunyai pola hujan monsun. Pada peta korelasi antara awal musim hujan di Sulawesi Selatan dan anomali suhu muka laut menunjukkan bahwa terdapat korelasi nyata(r≥0.5 antara kawasan Pasifik dan Laut Sulawesi pada cluster 1 dan 2 pada bulan Juni Juli Agustus September(JJAS. Sedangkan pada cluster 3, korelasi nyata hanya pada bulan Juni di perairan Sulawesi. Model prediksi AMH terbaik, pada cluster 2 terdapat di domain prediktor kawasan pasifik dengan nilai r=0.82, sedangkan pada cluster 1 dan 3, terdapat di domain perairan Sulawesi dengan nilai r=0.78 dan r-0.48. Verifikasi model terpilih pada cluster 3 mempunyai RMSE = 3, sedangkan cluster 1 dan 2, nilai RMSE berturut-turut sebesar 16 dan 29.   Model prediction of rainy season onset is one of the keys to reduce the risk of paddy haverst failure because of climate factor in South Sulawesi province. The model prediction for rainy season onset was build using rainfall data in South Sulawesi and SST anomaly in Pacific Ocean and

  6. Membandingkan Tingkat Kemiripan Rekaman Voice Changer Menggunakan Analisis Pitch, Formant dan Spectogram

    Directory of Open Access Journals (Sweden)

    Ahmad Subki

    2018-02-01

    Full Text Available Audio forensik merupakan salah satu ilmu yang mnyandingkan antara ilmu pengetahuan dan metode ilmiah dalam proses analisis rekaman suara untuk membantu dan mendukung pengungkapan suatu tindak kejahatan yang diperlukan dalam proses persidangan. Undang-undang ITE No.19 Tahun 2016 menyebutkan bahwa rekaman suara merupakan salah satu alat bukti digital yang sah dan dapat digunakan sebagai penguat dakwaan. Rekaman suara yang merupakan barang bukti digital sangatlah mudah dan rentan dimanipulasi, baik secara sengaja maupun tidak disengaja. Pada penelitian ini dilakukan analisis terkait tingkat kemiripan antara rekaman suara voice changer dengan rekaman suara asli menggunakan analisis pitch, formant dan spectogram, rekaman suara yang dianalisis ada dua jenis rekaman suara yaitu suara laki-laki dan suara perempuan. Rekaman suara voice changer  dan rekaman suara asli, diekstrak menggunakan tools praat kemudian informasi yang diperoleh dianalisis dengan analisis statistik pitch, formant dan spectrogrammenggunakan tools gnumeric. Penelitian ini menghasilkan bahwa analisis rekaman suara voice changer dengan rekaman suara asli dapat menggunakan analisis statistik pitch, formant dan spectrogram, rekaman suara voice changer A memiliki tingkat kemiripan yang paling tinggi dengan rekaman suara asli pada posisi low pitch, sedangkan voice changer yang lain lebih sulit untuk diidentifikasi.

  7. What have fusion reactor studies done for you today?

    International Nuclear Information System (INIS)

    Kulchinski, G.L.

    1985-01-01

    The University of Wisconsin examines the fusion program and puts into perspective what return is being made on investments in fusion reactor studies. Illustations show financial support for fusion research from the four major programs, FY'82 expenditures on fusion research, and the total expenditures on fusion research since 1951. Topics discussed include the estimated number of scientists conducting fusion research, the conceptual design study of a fusion reactor, scoping study of a reactor, the chronology of fusion reactor design studies, published fusion reactor studies 1967-1983, conceptual fusion reactor design studies, STARFIRE reference design, MARS central cell, HYLIFE reaction chamber, and selected contributions of reactor design studies to base programs

  8. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

    In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

  9. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

    Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

  10. ANALISIS DISKRIMINAN UNTUK MENENTUKAN INDIKATOR GARIS KEMISKINAN

    Directory of Open Access Journals (Sweden)

    Dadang Sukandar

    2012-03-01

    Full Text Available 800x600 Normal 0 false false false IN X-NONE X-NONE MicrosoftInternetExplorer4 The objectives of this study are to: 1 determine poverty line gold standard of farmers, 2 compare the gold standard with existing poverty line i.e. Sajogyo, Central Bureau of Statistics, BKKBN, World Bank US $ 1 and World Bank US $ 2, and 3 derive poverty indicators. This research was conducted in Subang, West Java. As many as 522 farmer households were collected as sample through stratified random sampling with proportional allocation. Data collected include socio-economic, income, expenditure, food consumption, health, anthropometry, agriculture aspects and living cost component and their prices. The Gold Standard was obtained through distribution standard normal while poverty indicator was derived through discriminant analysis. The results show that the poverty line gold standard of farmer is Rp. 457,558/capita/month which is equivalent to 2.29 gram of gold/capita/month. Discriminant analysis give five indicators of poverty namely, number of households member, husband education level, nutritional status of children, frequency of egg consumption, and land size manage by farmers. Keywords: farmer, poverty, gold standard, discriminant analysis, indicator

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  12. DESAIN TERAS PLTN JENIS PEBBLE BED MODULAR REACTOR (PBMR MENGGUNAKAN PAKET PROGRAM MCNP-5 PADA KONDISI BEGINNING OF LIFE

    Directory of Open Access Journals (Sweden)

    Ralind Re Marla

    2015-03-01

    Full Text Available Telah dilakukan desain teras Pembangkit Listrik Tenaga Nuklir (PLTN untuk jenis Pebble Bed Modular Reactor (PBMR dengan daya 70 MWe untuk keperluan proses smelter pada keadaan beginning of life (BOL. Analisis ini bertujuan untuk mengetahui persen pengkayaan, distribusi suhu dan nilai keselamatan dengan koefisien reaktivitas teras yang negatif pada reaktor jenis PBMR apabila daya reaktor 70 MWe. Analisis menggunakan program Monte Carlo N-Particle-5 (MCNP5 dan dari hasil analisis ini diharapkan dapat memenuhi syarat dalam mendukung program percepatan pembangunan kelistrikan batubara 10.000 MWe khususnya untuk proses smelter, yang tersebar merata di wilayah Indonesia. Hasil penelitian menunjukkan bahwa, faktor perlipatan efektif (k-eff Reaktor jenis PBMR daya 70 MWe mengalami kondisi kritis pada pengkayaan 5,626 % dengan nilai faktor perlipatan efektif 1,00031±0,00087 dan nilai koefisien reaktivitas suhu pada -10,0006 pcm/K. Dari hasil analisis daat disimpulkan bahwa reaktor jenis PBMR daya 70 MWe adalah aman.   ABSTRACT The core design of Nuclear Power Plant for Pebble Bed Modular Reactor (PBMR type with 70 MWe capacity power in Beginning of Life (BOL has been performed. The aim of this analysis, to know percent enrichment, temperature distribution and safety value by negative temperature coefficient at type PBMR if reactor power become lower equal to 70 MWe. This analysis was expected become one part of overview project development the power plant with 10.000 MWe of total capacity, spread evenly in territory of Indonesia especially to support of smelter industries. The results showed that, effective multiplication factor (keff with power 70 MWe critical condition at enrichment 5,626 %is 1,00031±0,00087, based on enrichment result, a value of the temperature coefficient reactivity is - 10,0006 pcm/K. Based on the results of these studies, it can beconcluded that the PBMR 70 MWe design is theoritically safe.

  13. ANALISIS KELAYAKAN FINANSIAL WISATA AIR WADUK JATIGEDE KABUPATEN SUMEDANG

    Directory of Open Access Journals (Sweden)

    Bambang Susanto

    2016-04-01

    pendahuluan agar manfaatnya jauh lebih besar dari biaya yang dikeluarkan. Oleh sebab itu untuk kepentingan ilmiah perlu dilakukan kajian akademisnya berupa Analisis kelayakan Finansial. Berdasarkan analisis kelayakan keuangan   ,dapat  disimpulkan bahwa wisata air di Waduk jatigede Kabupaten Sumedang  memberikan manfaat yang lebih dibandingkan dengan biaya yang dikeluarkan . ini dapat dilihat dari hasil analisis net present value yang positif, internal rate of return yang lebih besar dari tingkat bunga bank serta benefit cost yang lebih besar dari satu. Kata Kunci: Kelayakan Finansial; Wisata Air.

  14. ANALISIS RELEVANSI LULUSAN PERGURUAN TINGGI DENGAN DUNIA KERJA

    Directory of Open Access Journals (Sweden)

    Ali Muhson

    2012-04-01

    Full Text Available Abstract: A Relevance Analysis of University Graduates with World of Work. Education should be oriented to the competencies required by the workforce as a percentage of unemployment among the educated increase continuously. This study aims to examine the relevance of YSU Economic Education graduates. The study only focuses on the type of work and subjects taught. The subject of this study is the alumni of Economic Education Study Program. Sampling technique used is snowball sampling. Data collection technique using questionnaires and documentation while the technique of data analysis using descriptive analysis. The result suggests that the majority of the graduates find their first job as private a teacher, a private employee and a tutor, while current job of the most graduates are private teacher, private employee, and civil servant (teacher. The data shows that more than 50 percent of the graduates work in the education area. This implies that the relevance level based on the type of work is categorized as sufficient. Majority of the graduates teaches social science, economic, and entrepreneurship, hence it can be concluded that the relevance level based on the subjects taught is highly relevant.   Keyword: relevance of graduates, type of work, unemployment, employment     Abstrak: Analisis Relevansi Lulusan Perguruan Tinggi dengan Dunia Kerja. Pendidikan harus berorientasi pada kompetensi yang dibutuhkan oleh dunia kerja karena persentase penganggur di kalangan terdidik terus meningkat. Penelitian ini bertujuan untuk mengkaji tingkat relevansi (kesesuaian lulusan Pendidikan Ekonomi UNY. Kajian hanya diarahkan pada jenis pekerjaan dan mata pelajaran yang diampu. Penelitian ini mengambil subjek alumni Prodi Pendidikan Ekonomi dari berbagai angkatan. Teknik sampling yang digunakan adalah snowball sampling. Teknik pengumpulan data menggunakan angket dan dokumentasi sedangkan teknik analisis data menggunakan analisis deskriptif. Penelitian ini

  15. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

    Purpose: To facilitate and accelerate a leakage test of valves of a main steam pipe by adding a leakage test partition valve thereto. Constitution: A leakage testing partition valve is provided between a pressure vessel for a nuclear reactor and the most upstream side valve of a plurality of valves to be tested for leakage, a testing branch pipe is communicated with the downstream side of the partition valve, and the testing water for preventing leakage is introduced thereto through the branch pipe. Since main steam pipe can be simply isolated by closing the partition valve in the leakage test, the leakage test can be conducted without raising or lowering the water level in the pressure vessel, and since interference with other work in the reactor can be eliminated, the leakage test can be readily conducted parallel with other work in the reactor in a short time. Clean water can be used without using reactor water as the test water. (Yoshihara, H.)

  17. Reactor container

    International Nuclear Information System (INIS)

    Abe, Yoshihito; Sano, Tamotsu; Ueda, Sabuo; Tanaka, Kazuhisa.

    1987-01-01

    Purpose: To improve the liquid surface disturbance in LMFBR type reactors. Constitution: A horizontal flow suppressing mechanism mainly comprising vertical members is suspended near the free liquid surface of coolants in the upper plenum. The horizontal flow of coolants near the free liquid surface is reduced by the suppressing mechanism to effectively reduce the surface disturbance. The reduction in the liquid surface disturbance further prevails to the entire surface region with no particular vertical variations to the free liquid surface to remarkably improve the preventive performance for the liquid surface disturbance. Accordingly, it is also possible to attain the advantageous effects such as prevention for the thermal fatigue in reactor vessel walls, reactor upper mechanisms, etc. and prevention of burning damage to the reactor core due to the reduction of envolved Ar gas. (Kamimura, M.)

  18. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  19. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  20. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components [fr

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  2. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  3. WATER BOILER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1960-11-22

    As its name implies, this reactor utilizes an aqueous solution of a fissionable element salt, and is also conventional in that it contains a heat exchanger cooling coil immersed in the fuel. Its novelty lies in the utilization of a cylindrical reactor vessel to provide a critical region having a large and constant interface with a supernatant vapor region, and the use of a hollow sleeve coolant member suspended from the cover assembly in coaxial relation with the reactor vessel. Cool water is circulated inside this hollow coolant member, and a gap between its outer wall and the reactor vessel is used to carry off radiolytic gases for recombination in an external catalyst chamber. The central passage of the coolant member defines a reflux condenser passage into which the externally recombined gases are returned and condensed. The large and constant interface between fuel solution and vapor region prevents the formation of large bubbles and minimizes the amount of fuel salt carried off by water vapor, thus making possible higher flux densities, specific powers and power densities.

  4. Studies on reactor physics

    International Nuclear Information System (INIS)

    1960-01-01

    Most of the peaceful applications of atomic energy are inherently dependent on advances in the science and technology of nuclear reactors, and aspects of this development are part of a major programme of the International Atomic Energy Agency. The most useful role that the Agency can play is as a co-ordinating body or central forum where the trends can be reviewed and the results assessed. Some of the basic studies are carried out by members of the Agency's own scientific staff. The Agency also convenes groups of experts from different countries to examine a particular problem in detail and make any necessary recommendations. Some of the important subjects are discussed at international scientific meetings held by the Agency. One of the subjects covered by such studies is the physics of nuclear reactors and a specific topic recently discussed was Codes for Reactor Computations, on which a seminar was held in Vienna in April this year. Another The members of the Panel described the development of heavy water reactors, the equipment and methods of research currently used, and plans for further development in their respective countries meeting of Panel of Experts on Heavy Water Lattices was held in Vienna in August 1959

  5. Nuclear Reactor Sharing Program

    International Nuclear Information System (INIS)

    1994-01-01

    The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor parameter measurements. For neutron activation analysis and analyses of natural environmental radioactivity, the NRL maintains the gamma ray spectroscopy system (GRSS). It is comprised of two PC-based 8192-channel multichannel analyzers (MCAs) with all the required software for quantitative analysis. A 3 double-prime x 3 double-prime NaI(Tl), a 14 percent Ge(Li), and a High Purity Germanium detector are currently available for use with the spectroscopy system

  6. ANALISIS KEBERADAAN BIDAN DESA DAN DUKUN BAYI DI JAWA TIMUR

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    Mochamad Setyo Pramono

    2013-03-01

    Full Text Available ABSTRACT Background: The aim of the MDGs improving maternal health, one indicator is the proportion of aid delivery by trained health personnel. Related to this field which is spearheading the village midwife. The presence of the midwife profession not within the vacant land, because the tradition of the existence of traditional birth attendants have been there first. In the geographical and social conditions of a diverse society, where they can be a wealth of cultural treasures. Becomes interesting when the two interests are aligned but different backgrounds met in the field. How their existence in society, especially in rural areas whose traditions are still strong. Methods: This study was conducted in 2011 in four districts in East Java is Sampang, Probolinggo, Jombang and Madison. Refers to the characteristics of the election districts in East Java community is Madura, pandalungan, arek and Mataraman. This study combines quantitative and qualitative research. The data was collected by observation and in-depth interviews, informants were village midwives and traditional birth attendants in each region was selected health centers. Results: There is a dichotomy of senior midwives and midwives young. Senior midwife came mostly from outside the region. While a limited number of wide area coverage, it is not un comm on to make them choose to live in the central districts. As aresuIt, service delivery is limited. Relations senior midwife with pregnant women is quite high. Meanwhile, a young midwife from the local community though, is not necessarily acceptable in the neighborhood. Midwives are considered inexperienced young because young age, unmarried status or newly married. Meanwhile, the role of traditional birth attendants in rural areas is still quite significant, especially in Sampang and Probolinggo, there are still bold to help direct labor. In addition to knowledge of hereditary shamans, also based on modern medical knowledge gained

  7. Reactor containment

    International Nuclear Information System (INIS)

    Kawabe, Ryuhei; Yamaki, Rika.

    1990-01-01

    A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

  8. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

    Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

  9. ANALISIS LEMBAR KERJA SISWA DALAM MENINGKATKAN KOMUNIKASI MATEMATIS TULIS SISWA

    Directory of Open Access Journals (Sweden)

    Fimmatur Rizka Ardina

    2016-02-01

    Komunikasi merupakan suatu kemampuan yang penting untuk dimiliki setiap manusia. Komunikasi dalam artikel ini difokuskan pada komunikasi matematis tulis. Komunikasi matematis tulis ini akan berhubungan dengan lembar kerja siswa yang dipakai dalam proses pembelajaran. Tujuan penulisan artikel ini adalah untuk mendeskripsikan proses analisis LKS sebagai alat untuk meningkatkan komunikasi matematis tulis siswa. Jenis penelitian yang digunakan adalah kualitatif deskriptif. LKS akan dianalisis menggunakan standar indikator kemampuan komunikasi NCTM (2000 yang dimodifikasi sehingga terdapat empat indikator yaitu (1 siswa dapat menuliskan ide yang dimiliki dengan jelas dan tepat (2 siswa dapat menuliskan alasan untuk jawaban yang diberikan (3 siswa dapat memberikan tanggapan untuk ide atau jawaban siswa lain (4 siswa dapat menuliskan kembali ide orang lain menggunakan bahasanya sendiri. Berdasarkan hasil penelitian dapat disimpulkan bahwa LKS oleh Tim MGMP Kota Malang tidak dapat digunakan sebagai alternatif untuk meningkatkan kemmapuan komunikasi matematis tulis siswa.

  10. Analisis Implementasi Akuntansi Berbasis Akrual pada Inspektorat Jenderal Kementerian Keuangan

    Directory of Open Access Journals (Sweden)

    Eliada Herwiyanti

    2017-05-01

    Full Text Available Penelitian ini merupakan penelitian kualitatif terhadap penerapan Sistem Akuntansi Pemerintahan berbasis akrual di lingkungan Inspektorat Jenderal Kementerian Keuangan. Tujuan dari penelitian ini adalah untuk mengetahui bagaimana kesiapan dan penerapan SAP Berbasis Akrual di instansi tersebut. Data dalam penelitian ini dikumpulkan melalui observasi, studi kepustakaan, serta wawancara terhadap sepuluh orang informan yang terkait langsung dengan penerapan SAP berbasis akrual. Data yang telah dikumpulkan kemudian dianalisis dan diinterpretasikan secara naratif dengan menggunakan metode analisis data kualitatif yang direkomendasikan oleh Creswell (2012. Hasil penelitian ini menunjukkan bahwa secara umum, kesiapan Itjen Kemenkeu dalam menerapkan sistem akuntansi akrual sudah baik, mulai dari aspek komunikasi, sumber daya, komitmen organisasi, dan struktur birokrasi. Dengan kesiapan yang baik, penelitian ini juga menun­juk­kan bahwa penerapan sistem akuntansi akrual di Itjen Kemenkeu sudah dilakukan dengan sangat memuaskan, yang ditunjukkan dengan nilai sebesar 93,40%.

  11. ANALISIS PERANCANGAN BUSINESS INTELLIGENCE BERBASIS SAAS CLOUD COMPUTING

    Directory of Open Access Journals (Sweden)

    I Gede Adnyana

    2014-05-01

    Full Text Available Persaingan bisnis yang ketat, mendorong setiap perusahaan menyusun strategi bisnis agar dapat bertahan dari para pesaing. Penyusunan strategi bisnis mutlak memerlukan informasi yang tepat dan akurat, pengolahan hingga analisis data yang menghasilkan informasi yang tepat dan akurat menjadi proses yang sangat penting. Business Intelligence (BI menawarkan solusi bisnis untuk menganalisis data dan memungkinkan suatu perusahaan untuk mengambil keputusan untuk meningkatkan keuntungan dan kinerja bisnis. Namun, BI mahal untuk diimplementasikan, memerlukan biaya pemeliharaan yang tidak sedikit dan infrastruktur yang kuat. Hal ini mendorong perusahaan mengurangi biaya tetapi masih memiliki teknologi yang tepat untuk memungkinkan mereka untuk membuat keputusan, mengidentifikasi peluang dan proaktif mengidentifikasi risiko yang dapat mempengaruhi bisnis. Konsep Software as a Service (SaaS Cloud Computing dapat menjawab tantangan yang dihadapi BI. Sebelum merancang BI berbasis SaaS perlu diketahui parameter-parameter evaluasi hingga kelebihan dan kekurangannya.

  12. Analisis Kekuatan Struktur Pallet Menggunakan Metode Elemen Hingga

    Directory of Open Access Journals (Sweden)

    Tria Mariz Arief

    2015-07-01

    Full Text Available Pallet sebagai suatu alat bantu untuk mempermudah proses bongkar-muat logistik. Palletdigunakan hampir dalam berbagai lingkungan transportasi logistik. Pada bahasan berikutdikhususkan dalam lingkup transportasi di dalam pesawat udara khususnya pada pesawatangkut militer. Di lingkungan militer pallet digunakan untuk transport logistik baik secara normalmuat (loading dan bongkar (unloading maupun kondisi bongkar dengan diterjunkan daripesawat udara. Untuk pemenuhan penggunaan tersebut dilakukan perancangan ulang (reverseengineering struktur pallet yang dapat dimanufaktur secara lokal. Hipotesis awal menunjukkanbahwa berdasarkan kondisi pembebanan pada pallet dapat diperkirakan bahwa kondisitegangan dan regangan maksimum akan terjadi pada posisi sudut struktur pallet yang ditransferbebannya ke komponen plat besi penahan siku-siku dan baut. Material yang digunakan padastruktur pallet adalah Allumunium Alloy 7075-T6 dengan kekuatan tarik sebesar 503 MPa.Analisis dilakukan dengan menggunakan simulasi numerik dengan metoda elemen hingga(FEM. Proses simulasi numerik kekuatan struktur pallet difokuskan pada pembebanan statis(termasuk pengaruh factor G dalam interval beban statis 4 ton sampai 7 ton. Analisis dilakukanpada perubahan variabel tegangan dan regangan terhadap variasi beban yang diberikan untukmendapatkan tingkat keamanan struktur (margin safety. Pemodelan dilakukan denganidealisasi model ¼ bagian menggunakan elemen terstruktur dengan jenis elemen hexahedral(brick dengan jumlah 73803 elemen dan 360323 node. Hasil analisis menunjukkan teganganekuivalen maksimum struktur Pallet adalah 94 MPa yang terjadi di penguat sudut (anglebracket. Sedangkan pada struktur penguat lapis (sandwich structure berbahan thick blockyang mempunyai kekuatan sebesar 20 MPa adalah sebesar 0.84 MPa. Tingkat keamanansecara keseluruhan struktur dengan mempertimbangkan factor G hingga 2 adalah 5.3.Kata kunci: Analisis struktur, pallet, logistik, reverse engineering, FEM

  13. The fast reactor and electricity supply, a utility view

    International Nuclear Information System (INIS)

    Wright, J.K.; Hall, R.S.; Kemmish, W.B.; Thorne, R.T.

    1982-01-01

    The significance of the fast reactor is discussed from the viewpoint of the Central Electricity Generating Board. The need for the fast reactor and a possible timescale for its introduction are examined. It is emphasised that demonstration of the commercial and environmental acceptability of the fuel cycle will be needed before any commitment can be made to fast reactors. (U.K.)

  14. ANALISIS FAKTOR-FAKTOR YANG MEMPENGARUHI INDEPENDENSI PENAMPILAN AKUNTAN PUBLIK

    Directory of Open Access Journals (Sweden)

    Ardiani Ika S.

    2012-03-01

    Full Text Available Tujuan dari penelitian ini adalah untuk menguji secara empiris faktor-faktor yang mempengaruhi independensi penampilan akuntan publik baik secara parsial dan simultan. Faktor-faktor tersebut adalah financial interests, hubungan bisnis dengan klien, pelayanan asuransi dan audit, hubungan antara klien atau yg diaudit dengan auditor, kompetisi antara Kantor Akuntan Publik (KAP, ukuran KAP dan audit fee. Populasi dalam penelitian ini adalah para auditor di akuntan publik di Semarang tahun 2009. Metode penyeleksian sampel yang digunakan adalah convenience sampling dan jumlah respondennya 35. Alat analisis yang digunakan adalah multiple regression analysis. Dimulai dengan analisis kuantitatif untuk mengetes validitas dan reabilitas. Kemudian dilanjutkan uji asumsi klasik termasuk normality, multicollinearity, and heteroscedastisity. Hasil menunjukkan bahwa 6 variabel yang sudah dikaji secara simultan dan partial tersebut mempunyai efek yang signifikan terhadap independensi penampilan akuntan publik dengan R square 0.749. The objective of this study is to test empirically the factors that influence the independence of public accountant appearance both partially and simultaneously. The factors cover financial interests, business relationships with clients, assurance services and audit services, the length of relationship between client or auditee and auditor, the competition between Public Accountan Offices (KAPs, the size of KAP, and audit fee. The population in this study was the auditors who worked in the public accountant’s office in Semarang in 2009. The sample selection method is a convenience sampling and the  number of  respondents are 35. The Analysis tools used is multiple regression analysis. It starts by applying quantitative analysis to test the validity and reliability. Then, it is continued by testing the classical assumptions which include normality, multicollinearity, and heteroscedastisity. The result shows that the six

  15. ENCAPAI SUMBER DAYA MANUSIA UNGGUL (ANALISIS KINERJA DAN KUALITAS PELAYANAN

    Directory of Open Access Journals (Sweden)

    Ketut Sudarma

    2012-03-01

    Full Text Available Penelitian ini  bertujuan untuk menganalisis pengaruh kemampuan individu, kepuasan kerja, komitmen organisasi terhadap kinerja dan kinerja terhadap kualitas pelayanan. Sampel penelitian berjumlah 76 orang. Teknik pengambilan sampel menggunakan proportional random sampling. Variabel penelitian terdiri dari kemampuan individu, kepuasan kerja, komitmen organisasi, dan kinerja serta kualitas pelayanan  Analisis data menggunakan regresi dua tahap. Hasil penelitian menunjukkan bahwa kemampuan individu, kepuasan kerja dan komitmen organisasi mempunyai pengaruh positif signifikan terhadap kinerja dan kinerja berpengaruh positif signifikan terhadap kualitas pelayanan. Ini berarti semakin meningkat kinerja, maka semakin meningkat juga kualitas pelayanan. Dari hasil analisis deskriptif persentase tampak secara rata-rata  semua variabel penelitian  menunjukkan kategori baik, namun pada aspek-aspek tertentu pada masing-masing variabel masih terdapat kekurangan. Hasil penelitian ini diharapkan dapat menjadi masukan bagi pimpinan dalam meningkatkan kinerja dan kualitas pelayanan. Upaya perbaikan dimulai dari peningkatan kemampuan melalui pendidikan dan latihan, monitoring pelaksanaan kerja secara rutin, menumbuhkan komitmen kerja dan perbaikan standar operasi prosedur.The aim of the study is toanalyze the influence of individual abilities, job satisfaction, organizational commitment to performanceand performance againstservice quality. This samplingmethod is using 76 samples by the proportionalrandom sampling techniques. Variables consisted of individual ability, job satisfaction, organizational commitment, and performance andservice qualitydata analysisusingtwo-stageregression. The results showedthat theability of individuals, job satisfaction and organizational commitment had asignificant positive effecton performance and the performance ofa significant positive effecton quality of service. It means the higher performance, the higher service

  16. Il difficile cammino dell’analisi musicale in Italia

    Directory of Open Access Journals (Sweden)

    Claudio Annibaldi

    2014-10-01

    Full Text Available Si immaginino gli atti d’un convegno sull’analisi musicale che abbia avuto luogo in un paese come la Francia, la Germania, l’ Inghilterra o gli Stati Uniti. Potrebbe mai accadere che essi vengano pubblicati sostituendo il discorso ufficiale d’apertura dei lavori con un testo tutto nuovo epperò simulante d’esser quello effettivamente pronunciato dall’autore? E potrebbe mai accadere - essendo costui un noto critico musicale e il direttore della collana editoriale comprendente gli atti in questione - che questo nuovo testo sia da lui dedicato a uno sfoggio della propria competenza analitica capace solo di esibire una visione dilettantesca della tecnica musicale tout court? Penso proprio di no. Eppure questo è accaduto in Italia non molti anni fa, quando le Edizioni Unicopli pubblicarono, nella collana dei "Quaderni di Musica/Realtà", gli atti di un convegno sull’analisi musicale tenuto nel 1989 a Reggio Emilia: il primo del genere negli annali della musicologia italiana. L’episodio rende bene l’idea dei pericoli incombenti sul cammino di quegli studiosi che, a far data dal convegno suddetto, si sono adoperati a che la pratica analitica acquisisse anche da noi la dignità scientifica di cui gode, appunto, in paesi come la Francia, la Germania, l’Inghilterra o gli Stati Uniti. Quei pericoli si chiamano ‘dilettantismo tecnico’, ‘arroganza intellettuale’, ‘ vezzo d’ imporre l’uno e l’altra grazie a un qualche tipo di potere personale’, ‘necessità di subire tale imposizione in cambio di qualche vantaggio pratico’.

  17. ANALISIS KENDALA POTENSIAL PENERAPAN TOTAL QUALITY MANAGEMENT HOTEL PLAZA SEMARANG

    Directory of Open Access Journals (Sweden)

    Hendrajaya -

    2010-03-01

    Full Text Available Penelitian ini bertujuan untuk menemukan faktor-faktor yang terbentuk dari kendala penerapan Total Quality Management (TQM, sebagai upaya untuk menganalisis masalah-masalah potensial dari penerapan TQM di Hotel Plaza, Semarang. Sampel dari penelitian ini sejumlah 65 karyawan Hotel Plaza, Semarang yang terdiri dari manajer dan staf. Teknik analisis menggunakan Faktor Analisis. Hasil penelitian menunjukkan, bahwa kendala potensial dari implementasi TQM dapat disimpulkan menjadi lima faktor, yaitu faktor inkonsistensi, visi-misi, transformasi budaya, manajerial dan manajemen kualitas. Penelitian ini memberikan rekomendasi bahwa peningkatan fungsi-fungsi korporat melalui optimalisasi kualitas sebagai strategi bisnis dan orientasi pada kepuasan konsumen dengan melibatkan seluruh anggota organisasi, akan menjadi dasar untuk memaksimalkan daya saing perusahaan dalam hal produk, layanan, SDM, lingkungan dan seluruh proses yang dapat mendukung upaya perbaikan produktivitas. This study aims to determine the constraint factors and to analyze the potential problems of TQM implementation of Plaza Semarang Hotel. The sample of 65 employees of TQM implementation of Plaza Semarang Hotel, consist of managers and staffs. Factor analysis is used to achieve the results of the potential constraint implementation of Total Quality Management which can be summarized into five factors, they are: the factor of inconsistencies, the factor of vision and mission, cultural transformation factors, managerial factors and the factors of quality management. In order to increase the corporate functions through the optimization of quality as a business strategy and to achieve customer satisfaction, this study suggests that all members of the organization should be involved by the company as on-going basis to maximize the competitiveness of the organization on products, services, human resources, environment and all processes that support productivity improvement.

  18. Failure analysis to the weights of balance of a 350 MW turbo-generator; Analisis de falla a los pesos de balanceo de un turbogenerador de 350 MW

    Energy Technology Data Exchange (ETDEWEB)

    Vital Flores, Francisco; Gamero Arroyo, Jose Manuel [LAPEM, Comision Federal de Electricidad (Mexico)

    2007-11-15

    The selection of materials and the quality control in the supply of the components, as well as the involved operative variables in the process of work to which an equipment, device or a system of a power station of electrical generation are subjected, impact in the same in their useful life in a decisive way. In this document it is presented an analysis of a failure occurred in a 350 MW turbo-generator by the loosening of the balance weights, in which it is mentioned the flaws occurred by this cause and a metallographic analysis that indicates the main fault for the happening. [Spanish] La seleccion de material y el control de calidad en los suministros de los componentes, asi como las variables operativas involucradas en el proceso de trabajo al cual es sometido un equipo, dispositivo o un sistema de una central de generacion electrica, impactan en los mismos de manera decisiva en su vida util. En este documento se presenta un analisis de falla ocurrido en un turbogenerador de 350 MW, por el desprendimiento de los pesos de balanceo, el cual se menciona de los desperfectos ocurridos por esta causa y un analisis metalografico que indica la falla principal por lo ocurrido.

  19. Reactor head shielding apparatus

    International Nuclear Information System (INIS)

    Schukei, G.E.; Roebelen, G.J.

    1992-01-01

    This patent describes a nuclear reactor head shielding apparatus for mounting on spaced reactor head lifting members radially inwardly of the head bolts. It comprises a frame of sections for mounting on the lifting members and extending around the top central area of the head, mounting means for so mounting the frame sections, including downwardly projecting members on the frame sections and complementary upwardly open recessed members for fastening to the lifting members for receiving the downwardly projecting members when the frame sections are lowered thereto with lead shielding supported thereby on means for hanging lead shielding on the frame to minimize radiation exposure or personnel working with the head bolts or in the vicinity thereof

  20. Perumusan Strategi Bersaing pada Perusahaan Ban dengan Metode Analisis Portofolio Produk (Studi Kasus: PT Multistrada Arah Sarana, Tbk

    Directory of Open Access Journals (Sweden)

    Nathanael August Zefanya

    2017-01-01

    Full Text Available Industri ban di Indonesia mengalami perkembangan pesat dalam kurun waktu 10 tahun terakhir. Namun, terjadinya krisis ekonomi global menjadi penyebab menurunnya pendapatan, salah satunya adalah PT MASA dengan produk utamanya yaitu ban mobil Achilles dan ban motor Corsa yang digunakan sebagai objek penelitian ini. Telah diilakukan analisis PESTEL dan Porter’s Five Forces, identifikasi faktor lingkungan internal dan eksternal dengan analisis SWOT serta merumuskan alternatif strategi bersaing untuk direkomendasikan kepada PT MASA. Perumusan strategi alternatif didapat dari hasil analisis Matriks BCG dan Matriks IE sebagai analisis portofolio untuk mendapatkan tema strategi alternatif dalam pembuatan Matriks SWOT. Strategi alternatif kemudian diperingkatkan dengan QSPM dan dilanjutkan pembuatan rencana aksi bagi PT MASA dalam waktu 5 tahun ke depan. Setelah dilakukan analisis industri, diketahui bahwa ancaman terbesar datang dari pesaing produsen ban. Dari hasil analisis portofolio, PT MASA berada di kuadran I karena memiliki koordinat IFE serta EFE 3,32 dan 3,26. Dari hasil analisis Matriks IE, PT MASA direkomendasikan untuk melakukan strategi grow and build. Hasil Matriks BCG menunjukkan bahwa Achilles berada di dogs, sementara Corsa berada di question marks. Terdapat 13 strategi alternatif hasil dari formulasi strategi dengan menggunakan matriks TOWS. Dari hasil analisis QSPM, terdapat 7 alternatif strategi terbaik dan rencana aksi..

  1. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

    Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

    2003-01-01

    Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

  2. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  3. SOLASE: a conceptual laser fusion reactor design

    International Nuclear Information System (INIS)

    Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.

    1977-12-01

    The SOLASE conceptual laser fusion reactor has been designed to elucidate the technological problems posed by inertial confinement fusion reactors. This report contains a detailed description of all aspects of the study including the physics of pellet implosion and burn, optics and target illumination, last mirror design, laser system analysis, cavity design, pellet fabrication and delivery, vacuum system requirements, blanket design, thermal hydraulics, tritium analysis, neutronics calculations, radiation effects, stress analysis, shield design, reactor and plant building layout, maintenance procedures, and power cycle design. The reactor is designed as a 1000 MW/sub e/ unit for central station electric power generation

  4. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Prescott, R F; George, B V; Baglin, C J

    1978-05-10

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given.

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  6. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  7. PEMODELAN TERAS UNTUK ANALISIS PERHITUNGAN KONSTANTA MULTIPLIKASI REAKTOR HTR-PROTEUS

    Directory of Open Access Journals (Sweden)

    Zuhair Zuhair

    2015-04-01

    Full Text Available PTRKN sebagai salah satu unit kerja di BATAN dengan tugas pokok dan fungsi yang berkaitan erat dengan teknologi reaktor dan keselamatan nuklir, menaruh perhatian khusus pada konsep reaktor pebble bed. Dalam makalah ini pemodelan reaktor pebble bed HTR-PROTEUS dilakukan dengan program transport Monte Carlo MCNP5. Partikel bahan bakar berlapis TRISO dimodelkan secara detail dan eksak dimana distribusi acak partikel ini dalam bola bahan bakar didekati menggunakan array teratur kisi SC dengan fraksi packing 5,76% tanpa zona eksklusif. Model teras pebble bed didekati dengan memanfaatkan kisi teratur dari bola yang disusun sebagai kisi BCC berdasarkan sel berulang yang digenerasi dari sejumlah sel satuan. Hasil perhitungan MCNP5 memperlihatkan kesesuaian yang sangat baik dengan eksperimen, walaupun teras HTR-PROTEUS diprediksi lebih reaktif daripada pengukuran, khususnya di teras 4.2 dan 4.3. Pustaka ENDF/B-VI menunjukkan konsistensi dengan estimasi keff paling akurat dibandingkan pustaka ENDF/B-V, terutama ENDF/B-VI (66c. Deviasi estimasi keff yang dihitung dengan eksperimen dikaitkan sebagai konsekuensi dari komposisi reflektor grafit yang dispesifikasikan. Komparasi yang dibuat memperlihatkan bahwa MCNP5 menghasilkan keff teras HTR-PROTEUS lebih presisi daripada hasil dari MCNP4B dan MCNPBALL. Hasil ini menyimpulkan bahwa, sukses metodologi pemodelan ini menjustifikasi aplikasi MCNP5 untuk analisis reaktor pebble bed lainnya. Kata kunci: pemodelan teras HTR-PROTEUS, konstanta multiplikasi, MCNP5   PTRKN as a working unit in BATAN whose main duties and functions are related to reactor technology and nuclear safety, consern attention to pebble bed reactor concept. In this paper modeling of HTR-PROTEUS pebble bed reactor was done using Monte Carlo transport code MCNP5. The TRISO coated fuel particle is modeled in detailed and exact manner where random distributions of these particles in fuel pebble is approximated by using regular array of SC lattice

  8. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

    An improvement of the accessibility of that part of a nuclear reactor serving for biological shield is proposed. It is intended to provide within the biological shield, distributed around the circumference of the reactor pressure vessel, several shielding chambers filled with shielding material, which are isolated gastight from the outside by means of glass panes with a given bursting strength. It is advantageous that, on the one hand, inspection and maintenance will be possible without great effort and, on the other, a large relief cross section will be at desposal if required. (UWI) [de

  9. NEUTRONIC REACTOR

    Science.gov (United States)

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  10. ENFOQUE MULTIOBJETIVO DE LA MEJORA DE LA EFICIENCIA DE CENTRALES ELECTRICAS: ANALISIS ENERGETICO Y ECONOMICO

    Directory of Open Access Journals (Sweden)

    Ruiz, Ana B.

    2014-06-01

    Full Text Available The auxiliary services of power plants have raised their energy consumption given that, nowadays, power plants usually operate at partial loads. This paper presents a multiple criteria study about the efficiency improvement of the auxiliary services through a series of strategies. Besides the energy savings, two economic criteria are considered: the economic investment required and the Internal Rate of Return to maximize the profitability of the investment. In order to solve this multiobjective problem, we have developed a scheme which combines several approaches in order both to make use of the main advantages of each method and to progressively adapt the solution process to the decision maker’s preferences. Finally, we solve the multiobjective problem associated to a real case study using the scheme designed. With this case study, we show the usefulness of the scheme proposed, and we highlight the importance of an understandable feedback and an adaptive process.

  11. The Analisis Sentimen Sosial Media Twitter Dengan Algoritma Machine Learning Menggunakan Software R

    Directory of Open Access Journals (Sweden)

    Jaka Aulia Pratama

    2017-10-01

    Full Text Available Media sosial adalah wadah untuk mengungkapkan opini terhadap suatu topik tertentu. Ketersediaan informasi dan opini dari para pengguna media sosial merupakan kumpulan dokumen data berupa teks yang amat sangat besar dan berguna untuk kepentingan penelitian maupun membuat suatu keputusan bagi pihak – pihak tertentu. Text Mining bisa didefinisikan sebagai proses penggalian informasi di mana pengguna berinteraksi dengan kumpulan dokumen dari waktu ke waktu dengan menggunakan suatu alat analisis. Analisis sentimen atau Opinion Mining adalah salah satu studi di bidang komputasi yang berhubungan dengan kasus publik mengenai opini, penilaian, sikap, dan emosi. Penelitian ini akan menggunakan metode Machine Learning pada analisis sentimen pengguna layanan jejaring sosial Twitter terhadap Donald Trump dan Barack Obama dalam 20000 tweets. Nilai akurasi metode Machine Learning yang diperoleh cukup tinggi yaitu 87.52% untuk Data Training dan 87.4% untuk Data Testing.

  12. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  13. Reactor facility

    International Nuclear Information System (INIS)

    Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

    1997-01-01

    The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  15. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

    Purpose: To decrease the thickness of a reactor container and reduce the height and the height and plate thickness of a roof slab without using mechanical vibration stoppers. Constitution: Earthquake proofness is improved by filling fluids such as liquid metal between a reactor container and a secondary container and connecting the outer surface of the reactor container with the inner surface of the secondary container by means of bellows. That is, for the horizontal seismic vibrations, horizontal loads can be supported by the secondary container without providing mechanical vibration stoppers to the reactor container and the wall thickness can be reduced thereby enabling to simplify thermal insulation structure for the reduction of thermal stresses. Further, for the vertical seismic vibrations, verical loads can be transmitted to the secondary container thereby enabling to reduce the wall thickness in the same manner as for the horizontal load. By the effect of transferring the point of action of the container load applied to the roof slab to the outer circumferential portion, the intended purpose can be attained and, in addition, the radiation dose rate at the upper surface of the roof slab can be decreased. (Kamimura, M.)

  17. Reactor system

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Narabayashi, Naoshi.

    1990-01-01

    The represent invention concerns a reactor system with improved water injection means to a pressure vessel of a BWR type reactor. A steam pump is connected to a heat removing system pipeline, a high pressure water injection system pipeline and a low pressure water injection system pipeline for injecting water into the pressure vessel. A pump actuation pipeline is disposed being branched from a main steam pump or a steam relieaf pipeline system, through which steams are supplied to actuate the steam pump and supply cooling water into the pressure vessel thereby cooling the reactor core. The steam pump converts the heat energy into the kinetic energy and elevates the pressure of water to a level higher than the pressure of the steams supplied by way of a pressure-elevating diffuser. Cooling water can be supplied to the pressure vessel by the pressure elevation. This can surely inject cooling water into the pressure vessel upon loss of coolant accident or in a case if reactor scram is necessary, without using an additional power source. (I.N.)

  18. Reactor core

    International Nuclear Information System (INIS)

    Matsuura, Tetsuaki; Nomura, Teiji; Tokunaga, Kensuke; Okuda, Shin-ichi

    1990-01-01

    Fuel assemblies in the portions where the gradient of fast neutron fluxes between two opposing faces of a channel box is great are kept loaded at the outermost peripheral position of the reactor core also in the second operation cycle in the order to prevent interference between a control rod and the channel box due to bending deformation of the channel box. Further, the fuel assemblies in the second row from the outer most periphery in the first operation cycle are also kept loaded at the second row in the second operation cycle. Since the gradient of the fast neutrons in the reactor core is especially great at the outer circumference of the reactor core, the channel box at the outer circumference is bent such that the surface facing to the center of the reactor core is convexed and the channel box in the second row is also bent to the identical direction, the insertion of the control rod is not interfered. Further, if the positions for the fuels at the outermost periphery and the fuels in the second row are not altered in the second operation cycle, the gaps are not reduced to prevent the interference between the control rod and the channel box. (N.H.)

  19. ANALISIS USAHA PENGOLAHAN AMPLANG IKAN PIPIH (Notopterus chilata SKALA RUMAH TANGGA DI KOTA PALANGKA RAYA PROVINSI KALIMANTAN TENGAH

    Directory of Open Access Journals (Sweden)

    Saptami Utami Evi

    2016-06-01

    Full Text Available Usaha pengolahan amplang ikan  pipih di Kota Palangka Raya untuk pengembangan usaha kedepan sangat baik.  Dengan adanya dukungan tersedianya terus menerus bahan baku ikan pipih, baik dari tangkapan perairan, tangkapan alam, maupun usaha budidaya ikan pipih dan modal yang dikucurkan oleh pemerintah baik berupa peralatan usaha maupun pelatihan-pelatihan bagi para pengusaha untuk dapat terus berkembang. Penelitian ini dilakukan dengan tujuan Penelitian ini dilakukan di Kota Palangka Raya Provinsi Kalimantan Tengah. Data yang digunakan adalah data primer dan sekunder. Metode yang digunakan dalam pengolahan dan analisis data dalam penelitian ini adalah purposive sampling Amplang datar ikan pengolahan rumah tangga bisnis keuntungan sebesar Rp. 12.169 juta, - per tahun. Dari lapangan menunjukkan fakta bahwa bisnis ini tetap menguntungkan dengan kelangsungan hidup dalam waktu yang lamaBerdasarkan nilai analisis keuangan dengan menggunakan kriteria investasi Net Benefit Cost Ratio ( Net BCR 5 % = 3,032073039 dan B / C ratio Bersih 13,5% = 1,526361382 lebih besar dari 1 berarti bahwa usaha ini layak untuk dilanjutkan .Khusus untuk datar usaha pengolahan ikan amplang ( Notopterus chilata rumah tangga di kota Palangka Raya Kalimantan Tengah Provinsi amplang permintaan produk ikan dengan menawarkan flat atau D = S yang sama , berarti ampalng produksi ikan untuk memenuhi pasar datar. Flat fish processing business amplang household in the city of Palangka Raya for future business development very well with the support of continuous availability of raw materials and capital flat fish are disbursed by the government in cash, business equipment and training for entrepreneurs to be able to continue developed.  The research was conducted in the City of Palangka Raya Central Kalimantan Province. The data used were primary and secondary data. The method used in processing and analyzing data in this study was purposive sampling. Amplang flat fish processing

  20. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

    The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

  1. ANALISIS KELAYAKAN FINANSIAL PROYEK NARROWNECK PRESS AND BLOW UNTUK PROSES PRODUKSIBOTOL MINUMAN BERENERGI DI PT. ABC

    Directory of Open Access Journals (Sweden)

    Toni MT Munthe

    2015-08-01

    Full Text Available PT. ABC merupakan salah satu pabrik yang memproduksi botol kemasan kaca. Penelitian ini bertujuan untuk mengetahui layak atau tidaknya rencana investasi pada proyek Narrow Neck Press and Blow secara finansial di PT. ABC pada periode bulan April 2014 hingga bulan Juni 2014. Analisis kelayakan finansial proyek Narrow Neck Press and Blow, menggunakan metode analisis Net Present Value, Internal Rate of Return, Payback Period dan Sensitivity Analysis. Perbedaan antara nilai sekarang dari semua kas masuk dengan nilai sekarang dari semua kas keluar dari suatu proyek atau suatu investasi diperoleh dengan metode NPV, sedangkan untuk mencari tingkat bunga yang menyamakan nilai sekarang dari aliran kas bersih dan investasi diperoleh dengan metode IRR. Metode analisis yang dapat digunakan untuk mengetahui berapa lamakah waktu yang diperlukan untuk menutup dana yang dikeluarkan untuk suatu proyek dapat diperoleh dengan metode Payback Period. Setelah itu, dilakukan pengujian menggunakan sensitivitas analisis untuk mengetahui tingkat sensitivitas untuk tiap-tiap parameter terhadap persentase kenaikan dan penurunan. Dari hasil analisis data diperoleh nilai NPV sebesar Rp. 1.179.728.649.900,06, nilai IRR sebesar 56,36% dan periode pengembalian terletak pada 2 tahun 2 bulan 9 hari. Dengan menggunakan analisis sensitivitas dapat diketahui bahwa proyek ini sangat sensitif terhadap penurunan volume produksi. Berdasarkan hasil perhitungan, titik impas akan dicapai apabila volume produksi 213.403.267 unit per tahun atau 88,92% dari volume produksi awal. Nilai ini menunjukkan bahwa apabila volume produksi pada suatu periode mengalami penurunan lebih dari 11,08% dari volume produksi awal, maka investasi tersebut akan merugikan.

  2. Space reactor preliminary mechanical design

    International Nuclear Information System (INIS)

    Meier, K.L.

    1983-01-01

    An analysis was performed on the SABRE reactor space power system to determine the effect of the number and size of heat pipes on the design parameters of the nuclear subsystem. Small numbers of thin walled heat pipes were found to give a lower subsystem mass, but excessive fuel swelling resulted. The SP-100 preliminary design uses 120 heat pipes because of acceptable fuel swelling and a minimum nuclear subsystem mass of 1875 kg. Salient features of the reactor preliminary design are: individual fuel modules, ZrO 2 block core mounts, bolted collar fuel module restraints, and a BeO central plug

  3. ANALISIS PENGARUH VARIABILITAS TANAH PADA VARIABILITAS SPEKTRUM RESPON GEMPABUMI

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    I Nyoman Sukanta

    2010-11-01

    Full Text Available Salah satu komplek perkantoran yang terletak di Jalan Thamrin, Jakarta, dipilih sebagai lokasi penelitian. Hasil pemodelan data tanah, menghasilkan 3 lapisan tanah yang berbeda dengan kriteria jenis tanahnya cenderung lunak, dengan nilai N-SPT rata–rata = 11,23. Perhitungan percepatan puncak muka tanah (PGA dan nilai spektrum respon di permukaan tanah menggunakan metoda analisis linier equivalen dengan simulasi Monte Carlo. Program aplikasi SHAKE2000 merupakan alat bantu dalam simulasi, dengan memasukkan beberapa asumsi sebagai data masukan. Data masukan dinamik menggunakan sumber gempabumi Elcentro dan Mexico yang mempunyai kandungan frekuensi berbeda. Asumsi nilai percepatan puncak batuan dasar (PBA untuk kedua sumber gempabumi tersebut sebesar 0,18 g. Hasil analisis menunjukkan nilai spektrum respon dan percepatan puncak muka tanah sangat bervariasi. Gempabumi Elcentro menghasilkan nilai rata–rata PGA = 0,36 g dengan spektrum responnya = 1,0 g  pada Tc = 0,6 detik. Untuk gempabumi Mexico menghasilkan nilai rata–rata PGA = 0,30 g dengan spektrum responnya = 0,9 g pada Tc = 0,6 detik. Artinya, variabilitas jenis tanah sangat berpengaruh tehadap variabilitas spektrum respon di permukaan tanah.   One of the office complex located at Jalan Thamrin, Jakarta, was chosen as the location of the reseach. Results of data modeling soil, produces 3 different soil layers with soil type criteria tend to be soft, with a value of N-SPT  average = 11.23. Calculation of peak ground acceleration (PGA and the value of the response spectrum at ground surface using the method of equivalent linear analysis with Monte Carlo simulation. SHAKE2000 application software  is a tool in the simulation, by including some assumptions as input data. Dynamic input data using Elcentro and Mexican  earthquakes  which have different frequency contents. Assumed value of peak base acceleration (PBA for the two earthquakes was 0.18 g. The result of analysis was the value

  4. LA COMUNICAZIONE POLITICA SUI SOCIAL NETWORK: UN’ANALISI LINGUISTICA

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    Daniele Spoladore

    2014-07-01

    Full Text Available Questo lavoro si propone di analizzare le scelte linguistiche dei soggetti politici che utilizzano Facebook e Twitter per rivolgersi al sempre più frammentato panorama dei potenziali elettori. In particolare, analizza le tendenze linguistiche comuni che questi social network hanno fatto emergere nel rapporto tra politica, web e lettori. Cominciando dall’analisi della presenza di parlamentari e senatori su Facebook e Twitter, si cerca di riassumere le principali caratteristiche delle due piattaforme, per giungere ad una classificazione dei testi prodotti attraverso di esse; si analizza la scrittura di post e tweet, sottolineando la presenza di espedienti tipici del mezzo e valutando il loro effetto sui lettori, e si studiano le scelte sintattiche e morfosintattiche in relazione alla struttura e alle possibilità dei due social network. In ultima analisi si osservano le scelte lessicali dei soggetti politici, studiandone i campi semantici e la quantità di tecnicismi. Infine, si cerca di compiere una valutazione delle due differenti tipologie di trasmesso scritto rinvenute nei campioni, osservando come ognuna di esse abbia uno scopo ben preciso nell’economia della comunicazione politica sui social network. Political communication policy in social networks: a language analysis  Daniele Spoladore This paper aims to analyze the linguistic choices of politicians who use Facebook and Twitter to address the increasingly fragmented landscape of potential voters. In particular, it analyzes the common language trends that these social networks have revealed in the relationship between politics, the web and readers. Starting from the analysis of the presence of MPs and senators on Facebook and Twitter, we try to summarize the key features of the two platforms, in order to arrive at a classification of the texts produced using them.  We analyzed posts and tweets, emphasizing the  typical characteristics of these means and evaluating their effect on

  5. Analisis komoditas unggulan perikanan budidaya Kabupaten Pidie Jaya

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    Farok Afero

    2015-06-01

    Full Text Available Abstract. Snapper (Lates calcarifer, grouper (Epinephelus coioides, tiger shrimp (Penaeus monodon, vannamei shrimp (Litopenaeus vannamei and tilapia (Oreochromis niloticus are leading commodity worthly cultivated in Pidie Jaya. Bandar Baru and Tringgadeng an appropriate areas for black tiger shrimp while Jangka Buya and Ulim approriate areas for vannamei cultivation. AHP analysis showed black tiger shrimp is top priority based on the economic value while vannamei shrimp is top priority based on enterprise sustainability. Financial analysis of snapper, grouper, black tiger shrimp, vannamei shrimp and tilapia farming generated positive cash flow and NPV, IRR > 100%, the ratio of benefit to cost of production > 1,30 and payback period of investment costs  < 1 year, thus demonstrating the feasibility of cultivation of these leading commodities. Vannamei shrimp cultivation showed positive prospect as long the market offers premium price. Grouper and snapper had a positive outlook because high demand of high-quality fish in the international market. Keywords: Leading commodity; financial analysis; aquaculture; Pidie Jaya Abstrak. Komoditas kakap (Lates calcarifer, kerapu (Epinephelus coioides,udang windu (Penaeus monodon, udang vannamei (Litopenaeus vannamei dan nila (Oreochromis niloticus adalah komoditas unggulan yang layak dibudidaya di Kabupaten Pidie Jaya. Bandar Baru dan Tringgadeng merupakan kawasan yang layak untuk pengembangan komoditas udang windu sedangkan Jangka Buya dan Ulim layak untuk pengembangan komoditas udang vannamei. Analisis AHP menunjukkan komoditas udang windu menjadi prioritas utama untuk dikembangkan berdasarkan nilai ekonomi sedangkan udang vannamei menjadi prioritas utama berdasarkan keberlanjutan usaha. Analisis indikator keuangan budidaya kakap, kerapu, udang windu, vannamei dan nila menunjukkan usaha budidaya komoditas unggulan menghasilkan arus kas kumulatif dan NPV positif, nilai  IRR diatas 100%, rasio keuntungan

  6. ANALISIS PERILAKU SEKSUAL BERISIKO PADA REMAJA TERINFEKSI HIV DAN AIDS

    Directory of Open Access Journals (Sweden)

    Afritayeni Afritayeni

    2018-03-01

    penelitian eksplanatory research dengan pendekatan kuantitatif.Penelitian ini dilaksanakan dari bulan April-Oktober 2017.Jumlah sampel dalam penelitian ini adalah sebanyak 95 orang remaja yang terinfeksi HIV/ AIDS di Yayasan Sebaya Lancang Kuning dengan teknik pengambilan sampel accidental sampling. Pengumpulan data dilakukan dengan menggunakan data primer dan sekunder. Analisis data menggunakan analisis multivariat dengan uji regresi logistik berganda. Berdasarkan hasil penelitian dapat disimpulkan bahwa faktor yang paling dominan mempengaruhi perilaku seksual remaja adalah dorongan seksual.

  7. ANALISIS KEMAMPUAN KEUANGAN DAERAH PEMERINTAH PROPINSI NUSA TENGGARA BARAT

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    Hery Susanto

    2015-04-01

    Full Text Available This research aims to analyze the regional finance capability in West Nusa Tenggara province. This research uses secondary data of primary source. The data are obtained from the government of West Nusa Tenggara Province in the form of data that has been processed and published and become a legitimate document such as calculation data of APBD in Budgetary Year of 2003-2007. The instruments are used in collecting the data is the analysis of the regional finance capability through Calculation and Work Analysis of PAD, which is the measurement of share and growth, thus classified the result with mapping the financial region capability based on quadrant method. This research draws some conclusions namely: (1 generally, contribution of PAD (share to the total region income of NTB Province TA 2003- 2007 was low, in spite of the growth of PAD was high; (2 based on the measurement of Index Financial Capability (IKK, NTB Province was in the scale index of 0,541. Furthermore, the classification based on the criteria level of regional finance capability, the regional finance capability in NTB Province in 2003 -2007 was a province with high financial capability. There are some suggestions that could be offered to the Government of NTB Province; first, improving PAD share in NTB Province through the excavation of PAD potential sources. Second, concerning with the region cost efficiency, considering that the proportion of PAD achievement was fairly small comparing to the allocation of Region Cost. Penelitian ini bertujuan untuk menganalisis kemampuan keuangan daerah di Propinsi Nusa Tenggara Barat . Penelitian ini menggunakan data sekunder dari sumber utama. Data diperoleh dari pemerintah Propinsi Nusa Tenggara dalam bentuk data yang telah diolah dan dipublikasikan dan menjadi dokumen yang sah seperti data perhitungan APBD Tahun Anggaran 2003-2007. Instrumen yang digunakan dalam pengumpulan data adalah analisis kemampuan keuangan daerah melalui Perhitungan dan

  8. Analisis Reduksi Intensitas Cahaya Pada Smartphones’ Screen Protector Dan Dampaknya Pada Mata

    Directory of Open Access Journals (Sweden)

    Bhekti Kumorowati

    2017-04-01

    Full Text Available Analisis reduksi intensitas cahaya yang melewati screen protector dan identifikasi kemampuan screen protector sebagai pelindung mata dilakukan dengan mengukur reduksi intensitas cahaya menggunakan luxmeter, kemudian menetapkan fokus bahasan yang mencakup kemampuan cahaya menembus screen protector dan analisis fisis screen protector sebagai pelindung mata. Peran sebagai pelindung mata dikaji melalui pendekatan peristiwa polarisasi yaitu proses terserapnya sebagian arah getar cahaya. Dihasilkan sebagian arah getar cahaya layar smartphone sebelum masuk ke mata akan terserap oleh screen protector sehingga dapat memperlambat terjadinya degenerasi makula. Rekomendasi pemilihan screen protector bergantung pada besarnya koefisien atenuasi (koefisien penyerapan yang dimiliki masing-masing screen protector. Koefisien atenuasi terbesar dimiliki oleh screen protector jenis anti spy.

  9. ANALISIS PENGEMBANGAN POTENSI EKONOMI DAERAH DI KAWASAN BANGLOR TAHUN 2007-2011

    Directory of Open Access Journals (Sweden)

    Abdul Bakhirnudin

    2013-11-01

    Full Text Available Abstrak ___________________________________________________________________ Kawasan Banglor merupakan salah satu Kawasan di Provinsi Jawa Tengah yang memiliki tingkat pertumbuhan yang paling rendah dan terletak jauh lebih rendah dibandingkan dengan kawasan lainnya. Diantara kawasan-kawasan lainnya hanya kawasan Banglor sajalah yang memiliki pertumbuhan di bawah 4 persen yaitu 3,5 dan hal tersebut terletak jauh dibawah rata-rata dengan nilai rata-rata sebesar 4,89 persen pada tahun 2011. Sedangkan untuk kawasan lainnya memiliki pertumbuhan diatas 4 persen pada tahun 2011. Populasi penelitian ini adalah PDRB Kabupaten Rembang dan Blora atas dasar harga konstan tahun 2000, sedangkan sampel penelitian ini adalah PDRB Kab. Rembang dan Blora serta Jawa Tengah tahun 2007-2011 atas dasar harga konstan tahun 2000. Variabel yang dikaji dalam penelitian ini yaitu PDRB, pertumbuhan ekonomi, sektor-sektor ekonomi, penduduk, komponen Shift Share, dan SWOT. Metode pengumpulan data yang digunakan adalah metode dokumentasi dan kuesioner. Dalam penelitian ini digunakan analisis SLQ, DLQ dan Shift Share guna menentukan potensi ekonomi daerah yang dapat dijadikan sektor basis atau sektor unggulan. Selain itu penelitian ini juga bertujuan mengetahui tingkat ketimpangan antar daerah dalam kawasan Banglor. Berdasarkan analisis LQ dan Shift Share dapat diketahui potensi ekonomi daerah di kabupaten dalam kawasan Banglor, yaitu sektor industri pengolahan, sektor pertambangan dan penggalian, sektor Listrik,Gas, dan Air bersih, sektor perdagangan, hotel dan restoran di Kabupaten Rembang. Sedangkan di Kabupaten Blora Potensi Ekonomi Daerahnya adalah sektor Pertambangan dan Penggalian, sektor Industri Pengolahan, sektor perdagangan, hotel dan restoran, sektor Keuangan, Persewaan dan jasa perusahaan serta sektor Listrik,Gas, dan Air bersih. Selanjutnya digunakan analisis SWOT guna menganalisis strategi kebijakan pengembangan sektor Industri Pengolahan, sektor Perdagangan

  10. Analisis dan Desain BI-Dashboard Monitoring Realisasi Daftar Isian Pelaksanaan Anggaran (DIPA pada Kantor Pelayanan Perbendaharaan Negara (KPPN

    Directory of Open Access Journals (Sweden)

    Ernestina Rahmanasari

    2013-09-01

    Full Text Available Transaksi keuangan badan pemerintahan tingkat daerah dipertanggungjawabkan kepada Kementrian Keuangan melalui Kantor Pelayanan Perbendaharaan Negara (KPPNsetiap bulan dalam bentuk Laporan Keuangan Pemerintah Pusat (LKPP. Laporan Keuangan, didukung dengan teknologi Business Intelligence(BI dashboarddapat dimanfaatkan sebagai data-driven decision support system yang mendorong performa kinerja. Analisis dan desainterhadap pembuatan BI dashboard menunjukkanbagaimana Laporan Keuangan dapat digunakan untuk monitoring realisasi penyerapan dana DIPA dan kinerja instansi secara tepat waktu dan interaktif.Analisis terdiri dari analisis Indikator Kinerja Utama (IKU dan analisis Laporan Keuangan. IKUpada analisis dan desain ini mencakup ketercapaian estimasi dengan penerimaan, ketercapaian pagu dengan belanja, ketepatan waktu pengiriman rekonsiliasi oleh instansi, validasi, akurasi, dan ketepatan data. Desain terdiri dari katalog dashboard, alur analisis, sumber data, desain User-Interface, dan desain objek dashboard. Sedangkan dashboard yang dirancang menggunakan aplikasi Vera sebagai Enterprise System, mengakses basis data MySQL, dan menampilkan data dengan teknologi data-driven business-intelligence Qlikview. Desain aplikasi yang telah dibuat akan menampilkan 4 (empat Tab yaitu: Dashboard utama, Analisis, Monitoring, dan Laporan

  11. ANALISIS KETERKAITAN KETERSEDIAAN INFRASTRUKTUR DENGAN PERTUMBUHAN EKONOMI DI INDONESIA: PENDEKATAN ANALISIS GRANGER CAUSALITY

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    Lesta Karolina B Sembanyang

    2015-12-01

    Full Text Available The aims of this study are to analyze the causal relationship of public service provision (infrastructure, economic growth and tax inIndonesiaand to formulate the policy implications of causal link and infrastructure inIndonesia’s economic growth. The data used was time series data, from 1987 up to 2009. They were from many sources such as Government Expenditure (APBN, Central Bureau of Statistics (BPS and the International Financial Statistics (IFS. The method used is a causal analysis approach or the Granger causality. The findings of this study is that there is a direct relationship between GDP to infrastructure and the GDP to tax revenue. The conclusions of this study are Gross Domestic Product (GDP can lead the availability of infrastructure (for example road length in Indonesia,there is a causal connection between the economic growth and the tax revenue in Indonesia, andthe increased tax revenue will increase the availability of infrastructure, especially road.

  12. Comparison between a finite difference model (PUMA) and a finite element model (DELFIN) for simulation of the reactor of the atomic power plant of Atucha I; Comparacion entre un modelo de diferencias finitas (PUMA) y uno de elementos finitos (DELFIN) para la simulacion del reactor de la CNA-I (central nuclear Atucha-I)

    Energy Technology Data Exchange (ETDEWEB)

    Grant, C R [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

    1997-12-31

    The reactor code PUMA, developed in CNEA, simulates nuclear reactors discretizing space in finite difference elements. Core representation is performed by means a cylindrical mesh, but the reactor channels are arranged in an hexagonal lattice. That is why a mapping using volume intersections must be used. This spatial treatment is the reason of an overestimation of the control rod reactivity values, which must be adjusted modifying the incremental cross sections. Also, a not very good treatment of the continuity conditions between core and reflector leads to an overestimation of channel power of the peripherical fuel elements between 5 to 8 per cent. Another code, DELFIN, developed also in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and current among elements and a more realistic representation of the hexagonal lattice of the reactor. A comparison between results obtained using both methods in done in this paper. (author). 4 refs., 3 figs.

  13. Perbandingan Penilaian Saham Dengan Metode Analisis Fundamental Dan Analisis Tehknical, Penggorengan Saham, Serta Keputusan Penilaian Saham Jika Hasil Berlawanan Arah Untuk Kedua Metode Analisis Pada Saham Bakrie Group Untuk Periode 2005- 2009

    OpenAIRE

    Harwaningrum, Miranti

    2016-01-01

    Beberapa tahun belakangan ini, dunia investasi mengalami peningkatan. Hal ini dapat terlihat dari data rata-rata perdagangan saham yang dimiliki oleh Bapepam. Salah satu jenis instrumen investasi yang sering diminati oleh investor adalah saham. Apabila dibandingkan dengan obligasi, saham memiliki expected return yang lebih tinggi. Namun, saham memiliki resiko yang lebih tinggi bila dibandingkan dengan obligasi. Untuk melakukan penilaian saham ada dua analisis yang dapat dilakukan, yaitu funda...

  14. ANALISIS ATRIBUT-ATRIBUT YANG MEMPENGARUHI TINGKAT KEPUASAN PELANGGAN TELEPON RUMAH (FIXED WIRELINE MENGGUNAKAN METODE ANALISIS DISKRIMINAN (STUDI KASUS DI PT. TELKOM KANDATEL SEMARANG

    Directory of Open Access Journals (Sweden)

    Diana Puspita Sari

    2012-02-01

    Full Text Available PT Telkom memiliki misi untuk memberikan layanan One Stop Infocom dengan kualitas prima dan harga kompetitif. Kenyataannya, PT. Telkom Kandatel Semarang mengalami penurunan pendapatan. Semakin berkembangnya layanan jasa fixed wireless yang lebih mudah dan murah, menyebabkan penurunan pemakaian jasa fixed wireline. Dengan konsumen melakukan pembelian pertama pada suatu produk tertentu dengan harga terjangkau, kualitas terjamin, maka konsumen akan kembali membeli produk tersebut, dan dampaknya dari fenomena ini adalah kepuasan pelanggan (customer satisfaction terhadap produk tertentu karena telah memberikan kepuasan dan terjaminnya kualitas, walaupun banyak pesaing lain.  Oleh sebab itu, penelitian ini membahas dan melakukan analisis kepuasan pelanggan fixed wireline PT. Telkom Kandatel Semarang, menggunakan variabel kepuasan pelanggan untuk dikelompokkan menjadi tiga tingkatan yaitu pelanggan yang sangat puas, puas, dan tidak puas dengan menggunakan analisis klaster, kemudian dilakukan analisis variabel 4P Customer Relationship Management (CRM menggunakan analisis diskriminan, sehingga diketahui atribut yang mempengaruhi tingkat kepuasan pelanggan agar PT. Telkom Kandatel Semarang dapat terus mempertahankan dan meningkatkan kepuasan pelanggan dengan berusaha memenuhi kebutuhan dan keinginan pelanggan dengan maksud kepuasan pelanggan tidak menurun agar dapat meningkatkan intensitas pemakaian fixed wireline. Kata kunci : analisis klaster, analisis diskriminan, kepuasan pelanggan, fixed wireline      PT Telkom has a mission to provide a One Stop Infocom services with excellent quality and competitive price. In fact, PT. Telkom Semarang Kandatel income decreased. The growing fixed wireless service is easier and cheaper, causes a decrease in the use of fixed wireline services.With the first consumer purchase a given product at an affordable price, guaranteed quality, then consumers will buy the product again, and the impact of this phenomenon is

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Sasaki, Tomozo.

    1987-01-01

    Purpose: To improve the nuclear reactor availability by enabling to continuously exchange fuels in the natural-slightly enriched uranium region during operation. Constitution: A control rod is withdrawn to the midway of a highly enriched uranium region by means of control rod drives and the highly enriched uranium region is burnt to maintain the nuclear reactor always at a critical state. At the same time, fresh uranium-slightly enriched uranium is continuously supplied gravitationally from a fresh fuel reservoir through fuel reservoir to each of fuel pipes in the natural-slightly enriched uranium region. Then, spent fuels reduced with the reactivity by the burn up are successively taken out from the bottom of each of the fuel pipes through an exit duct and a solenoid valve to the inside of a spent fuel reservoir and the burn up in the natural-slightly enriched uranium region is conducted continuously. (Kawakami, Y.)

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Sakurai, Mikio; Yamauchi, Koki.

    1983-01-01

    Purpose: To improve the channel stability and the reactor core stability in a spontaneous circulation state of coolants. Constitution: A reactor core stabilizing device comprising a differential pressure automatic ON-OFF valve is disposed between each of a plurality of jet pumps arranged on a pump deck. The stabilizing device comprises a piston exerted with a pressure on the lower side of the pump deck by way of a pipeway and a valve for flowing coolants through the bypass opening disposed to the pump deck by the opening and closure of the valve ON-OFF. In a case where the jet pumps are stopped, since the differential pressure between the upper and the lower sides of the pump deck is removed, the valve lowers gravitationally into an opened state, whereby the coolants flow through the bypass opening to increase the spontaneous circulation amount thereby improve the stability. (Yoshino, Y.)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  19. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

    Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

  20. Reactor container

    International Nuclear Information System (INIS)

    Oyamada, Osamu; Furukawa, Hideyasu; Uozumi, Hiroto.

    1979-01-01

    Purpose: To lower the position of an intermediate slab within a reactor container and fitting a heat insulating material to the inner wall of said intermediate slab, whereby a space for a control rod exchanging device and thermal stresses of the inner peripheral wall are lowered. Constitution: In the pedestal at the lower part of a reactor pressure vessel there is formed an intermediate slab at a position lower than diaphragm floor slab of the outer periphery of the pedestal thereby to secure a space for providing automatic exchanging device of a control rod driving device. Futhermore, a heat insulating material is fitted to the inner peripheral wall at the upper side of the intermediate slab part, and the temperature gradient in the wall thickness direction at the time of a piping rupture trouble is made gentle, and thermal stresses at the inner peripheral wall are lowered. (Sekiya, K.)

  1. Analisis Vegetasi di Hutan Mbeji Daerah Wonosalam Jombang

    Directory of Open Access Journals (Sweden)

    Anita Munawwaroh

    2016-03-01

    Full Text Available Analisis vegetasi terhadap hutan perlu dilakukan untuk mengetahui keanekaragaman hayati yang terdapat di hutan tersebut sehingga mempermudah didalam melakukan pemeliharaan dan pemberdayaan hutan.Tujuan dari penelitian ini adalah untuk mengetahui keanekaragaman hayati dan struktur vegetasi (frekuensi, kerapatan, dominansi, dan Indeks Nilai Penting di hutan mbeji, Wonossalam, Jombang. Pada penelitian ini digunakan metode point centered quarter. Pennelitian dilakukan pada bulan Mei 2015. Hasil penelitian menujukkan padaHutan Mbeji terdapat 11 jenis pohon yang teridentifikasi dan 15 spesies tumbuhan, dimana ada 10 spesies yang telah teridentifikasiNilai penting  tumbuh-tumbuhan di Hutan Mbeji di daerah Wonosalam Jombang  pada tingkat pohon paling tinggi adalah pohon randu (Ceiba petandra  sebesar 57,42 % sedangkan nilai INP paling rendah dari jenis pohon andong (Rhadamnia cinerea yaitu sebesar 6,06 %. Pada sapling nilai penting yang paling tinggi adalah talas (Colocasia esculenta yaitu sebesar 49,23 %. Sedangkan, nilai INP paling rendah dari jenis nanas (Ananas comosus, nangka (Artocarpus heterophyllus, tapak liman (Elephantopus scaber, semak A, semak B, semak C, semak E, dan semak F yaitu sebesar 6,35 %. Tingginya nilai INP menunjukkan bahwa jenis-jenis tersebut dapat menyesuaikan diri dengan lingkungan sekitarnya yang lebih baik dibanding jenis lainnya.

  2. ANALISIS MODEL PENERIMAAN PENGGUNA SISTEM PELAPORAN PAJAK ONLINE

    Directory of Open Access Journals (Sweden)

    Muhammad Malik Hakim

    2016-04-01

    Full Text Available Direktorat Jenderal Pajak saat ini telah menerapkan e-SPT dan e-Filing sebagai sarana digitalisasi dan otomasi pelaporan pajak. Untuk meningkatkan transformasi bisnis proses dalam sistem pelayanan perpajakan dari sistem manual ke digital, diperlukan kesiapan dan penerimaan pengguna yang cukup memadai. Studi dan analisis perlu dilakukan untuk mengetahui sejauh mana tingkat penerimaan pengguna dalam menggunakan sistem e-SPT dan e- Filing. Studi dilakukan secara kuantitatif menggunakan model UTAUT yang telah dimodifikasi untuk menganalisis model penerimaan pengguna yang merupakan Wajib Pajak Orang Pribadi yang telah menggunakan e-SPT dan e- Filing. Jumlah responden dalam penelitian ini sejumlah 235 responden yang disebarkan dengan cara snow ball sampling. Hasil penelitian menunjukkan perbedaan model penerimaan e-SPT dan e-Filing dari jenis kelamin dan kelompok umur. Pengaruh harapan kinerja (PE dan pengaruh sosial (SI terhadap niat perilaku (BI, serta pengaruh niat perilaku (BI pada penggunaan aktual (AU pada pria lebih kuat dibandingkan pada wanita. Sebaliknya, pengaruh harapan usaha (EE terhadap niat perilaku (BI dan fasilitas pendukung / penunjang (FC terhadap penggunaan aktual (AU pada wanita dijumpai memberikan pengaruh yang lebih kuat. Selain itu, di dalam kelompok umur, pengaruh terhadap semua variabel yang diteliti ternyata lebih kuat pada kelompok umur 25 35 tahun. Kata kunci: model penerimaan pengguna, UTAUT, pelaporan pajak, e-SPT, e-filing.

  3. ANALISIS TINGKAT PENDAPATAN PEDAGANG CANANG DI PASAR BADUNG

    Directory of Open Access Journals (Sweden)

    Surya Dewi Rustariyuni

    2015-12-01

    Full Text Available This studyanalyzes thecharacteristic of “canang”sellers, their economicactivities, their revenues, the factors which influencethem to chooseBadung Market for selling their products and theircontributions in their household economy. As a matter of fact,all of Hindu ismpeoplein Bali use canang everyday for conductingall ceremonies, but only few people whomake canang. It has occured foryears. The method used for analizing the data isdescriptive analysis. The result shows thatthe canang sellersare mostlyfrom Bali. They are dominated by married women atthe age of 15 up to 35 years old. Then, theireducational backgroundaresenior high schools. They start selling early in the morning and stop their activities in the evening.Finally, usually the sellers get much money when there is a big ceremony.Penelitian ini menganalisis karakteristik penjual "canang", kegiatan ekonominya, pendapatannya, faktor-faktor yang mempengaruhi penjual canang untuk memilih Pasar Badung sebagai tempat untuk menjual canangnya dan kontribusi penjual canang dalam perekonomian rumah tangga. Sebenarnya, semua orang Hindu di Bali menggunakan canang setiap hari untuk melakukan semua upacara, tetapi hanya sedikit orang yang membuat canang. Ini telah terjadi selama bertahun-tahun. Metode yang digunakan untuk menganalisis data disini adalah analisis deskriptif. Hasil penelitian menunjukkan bahwa para penjual canang sebagian besar dari Bali. Mereka didominasi oleh perempuan yang sudah menikah danusianya antara 15 hingga 35 tahun. Kemudian, latar belakang pendidikan mereka adalah sekolah menengah atas. Mereka mulai menjual canang di pagi hari dan selesai di malam hari. Biasanya para penjual mendapatkan uang banyak ketika ada upacara besar.

  4. Analisis Cost-Volume-Profit Kaitannya dengan Perencanaan Laba

    Directory of Open Access Journals (Sweden)

    Rian Andriani

    2018-01-01

    Full Text Available Tujuan penelitian  ini adalah untuk menganalisis cost, volume, profit Break Event Point dan Margin Of Safety L.A English Course Baleendah Bandung pada kuartal I – IV. Metode penelitian yang digunakan adalah metode penelitian kuntitatif deskriptif. Teknik pengumpulan data menggunakan studi pustaka, observasi, wawancara, dan dokumentasi yang memiliki hubungan dengan pokok permasalahan. Teknik analisis data yang digunakan metode regresi kuadrat terkecil, break event point dan margin of safety.  Hasil menunjukan, biaya tertinggi terdapat pada kuartal I, volume penjualan  tertinggi terdapat pada kuartal I, laba tertinggi terdapat pada kuartal I, Break Event Point tertinggi terdapat pada kuartal I. Sedangkan Margin of safety (% tertinggi pada kuartal IV yaitu 91.9%. Masalah yang timbul dalam  perencanaan  laba yaitu pertama  pendapatan L.A English Course  naik turun  dalam satu  tahunnya, kedua  kurangnya promosi untuk beberapa program kecuali program regular. Upaya dalam mengatasi masalah yang timbul di L.A English Course yaitu pertama memberikan gratis biaya daftar, dan memberi voucher untuk siswa L.A yang memasukan siswa baru., kedua membagikan brosur, dan menawarkan program L.A. dengan melakukan follow up semua nomor telepon tamu yang pernah berkunjung.

  5. ANALISIS PENGARUH PERUBAHAN EARNINGS DAN RISIKO PASAR TERHADAP STRUKTUR MODAL

    Directory of Open Access Journals (Sweden)

    Endi Sarwoko

    2006-05-01

    Full Text Available Penelitian ini bertujuan untuk menguji perbedaan rata-rata struktur modal antar industri, menguji pengaruh perubahan earnings perusahaan terhadap struktur modal, dan menguji pengaruh risiko pasar dengan struktur modal perusahaan. Struktur modal dalam penelitian ini diproksikan dengan debt to equity ratio dan debt to total assets. Data diperoleh dari Pojok Bursa Efek Jakarta (BEJ Universitas Brawijaya, sampel sebanyak 40 perusahaan yang diambil secara Purposive dengan kriteria perusahaan-perusahaan tersebut aktif mencatatkan laporan keuangannya di BEJ dan aktif melakukan perdagangan saham selama 6 tahun terakhir. Hasil analisis menunjukkan bahwa terdapat pengaruh terbalik antara perubahan earnings perusahaan terhadap D/E tetapi perubahan earnings ternyata tidak berpengaruh signifikan terhadap D/A. Risiko pasar tidak berpengaruh signifikan terhadap debt to equity, hasil ini menunjukkan bahwa ketika akan melakukan pembelian saham investor tidak mempertimbangkan risiko pasar. Sedangkan berdasarkan pengaruh terhadap D/A diperoleh hasil risiko pasar berpengaruh signifikan terhadap debt to total assets,  manajemen perusahaan sangat memperhatikan dampak risiko pasar dalam menentukan kebijakan struktur modal perusahaan, karena dalam memberikan pinjaman kreditur biasanya sangat mempertimbangkan aset yang dimiliki perusahaan didanai dari mana, hutang atau modal sendiri.

  6. Analisis ergonomi postur kerja operator pada proses pembuatan batako

    Directory of Open Access Journals (Sweden)

    Regina Anggraini

    2017-03-01

    Full Text Available Abstrak: Proses pembuatan batako merupakan salah satu pekerjaan yang membutuhkan penanganan material secara manual,sehingga tenaga fisik pekerja diperlukan meskipun mesin bantu cetak sudah tersedia. Berdasarkan pengamatan dilapangandiketahui bahwa seluruh aktivitas pembuatan batako banyak membutuhkan tenaga fisik. Pekerjaan membuat batako dapatdibagi menjadi beberapa elemen kerja dan setiap elemen kerja memberikan postur kerja yang bervariasi. Hasil analisis posturkerja dengan menggunakan REBA menunjukkan pekerja pada proses pemindahan batako basah memiliki nilai 11 dengan levelrisiko sangat tinggi. Perbaikan dilakukan dengan menambahkan kursi pekerja dan berhasil menurunkan skor REBA menjadi 5.Kata Kunci: Postur kerja, REBA Abstract: Brick-making process is one of those jobs that require manual materials handling, so that the physical exertion of workersneeded though a production machine is already available. Based on observations in the field note that the entire activity ofbrick-making requires a lot of physical exertion. Brick-making can be divided into several working elements and each element ofthe work provides a varied work posture. The results of the analysis work posture using REBA showed workers in the processof moving the wet concrete blocks have a value of 11 with a very high risk level. Improvement of working conditions by adding aseat for workers reduce the REBA score to 5 .Keywords: Work Posture , REBA

  7. ANALISIS PENGARUH TINGKAT KESEHATAN BANK TERHADAP RETURN ON ASSET

    Directory of Open Access Journals (Sweden)

    Andy Setiawan

    2017-10-01

    Full Text Available Penelitian  ini  dilakukan  untuk  menganalisis pengaruh  tingkat kesehatan bank terhadap return on asset (ROA berdasarkan metode risk based bank rating (RBBR. Variabel independen yang diteliti adalah Non  Performing  Loan  (NPL, Loan to Deposit Ratio (LDR, Net Interest Margin (NIM, Capital Adequacy Ratio (CAR,  BOPO   (Biaya   Operasional/Pendapatan Operasional, Good Corporate Governance (GCG dan Posisi  Devisa  Netto  (PDN terhadap variabel dependen Return On Asset (ROA. Sampel yang digunakan  adalah  seluruh bank BUKU 4 di Indonesia selama periode 2007-2014. Teknik analisis data yang  digunakan  adalah  regresi  linier  berganda. Hasil penelitian ini menunjukkan bahwa tingkat kesehatan bank dengan metode RBBR berpengaruh signifikan secara bersama terhadap ROA. Secara parsial LDR, NIM, BOPO, dan PDN berpengaruh signifikan terhadap ROA. Sedangkan variabel NPL, GCG dan CAR tidak berpengaruh signifikan. Kemampuan prediksi dari ketujuh variabel  tersebut  terhadap  ROA  dalam  penelitian  ini  sebesar  93,7%,  sedangkan sisanya 6,3% dipengarui oleh faktor lain yang tidak dimasukkan ke dalam model penelitian.

  8. ANALISIS KADAR SIKLAMAT PADA ES KRIM DI KOTA BANJARBARU

    Directory of Open Access Journals (Sweden)

    Nurlailah Nurlailah

    2017-07-01

    Full Text Available Pemanis merupakan salah satu komponen yang sering ditambahkan dalam bahan makanan. Pemanis buatan yang banyak beredar di masyarakat adalah siklamat. Konsumsi siklamat yang melebihi dosis akan mengakibatkan kanker kandung kemih. Selain itu akan menyebabkan tumor paru, hati, dan limfa. Tujuan penelitian ini adalah untuk mengetahui adanya siklamat dalam es krim yang melebihi ambang batas yang dipersyaratkan. Jenis penelitian ini adalah survey deskriptif. Sampel penelitian adalah es krim produksi rumah tangga dari seluruh pedagang es krim di Banjarbaru utara yaitu dengan jumlah 11 pedagang es krim. Variabel dalam penelitian ini adalah kadar siklamat yang terdapat dalam es krim. Hasil penelitian menunjukkan dari 11 sampel es krim yang diperiksa, 9 sampel mengandung siklamat dengan kadar tertinggi 7,37 g/kg sebagai asam siklamat. Kesimpulan penelitian ini adalah es krim yang mengandung siklamat ditemukan sebanyak 82% (9 sampel, sedangkan 18% (2 sampel lainnya negatif, dari 9 sampel yang positif mengandung siklamat, 89% tidak memenuhi syarat PERMENKES Nomor 208 tahun 1985 yaitu melebihi 2 gr/kg sebagai asam siklamat. Perlu dilakukan pemeriksaan yang lebih spesifik untuk analisis kadar siklamat dengan metode lain seperti Kromatografi Cair Kinerja Tinggi (KCKT

  9. ANALISIS OMNICHANNEL CUSTOMER EXPERIENCE MATURITY DI PT. TELEKOMUNIKASI INDONESIA

    Directory of Open Access Journals (Sweden)

    Andreas W. Yanuardi

    2017-02-01

    Full Text Available Customer Experience yang baik mampu meningkatkan kepuasan pelanggan, sehingga membuat pelanggan menjadi setia terhadap penyedia jasa. Pentingnya Customer Experience ini membuat banyak perusahaan ber fokus dalam membangun strategi Customer Experience - nya. Salah satu strategi C ustomer Experience untuk meningkatkan kepuasan pelanggan adalah dengan Omnichannel Customer Experience . Prinsip Omnichannel adalah melakukan integrasi data di semua saluran komunikasi pelanggan sehingga perusahaan mendapatkan pandangan 360 o terhadap pelang gan, atau disebut “ single customer view ”. Integrasi data memungkinkan pelanggan melakukan interaksi dengan perusahaan melalui saluran manapun yang diinginkannya, tanpa harus mengulang informasi ketika ia berpindah saluran. Single customer view kemudian mem ungkinkan perusahaan melakukan personalisasi, yaitu memberikan pelayanan kepada pelanggan secara personal sesuai profil, aktivitas, perilaku, dan ketertarikan pelanggan tersebut. PT Telekomunikasi Indonesia Tbk , sebagai salah satu Communication Service Provider (CSP , telah mengimplementasikan strategi Omnichannel . Penelitian ini bertujuan mengukur maturity level dari implementasi Omnichannel Customer Experience PT Telekomunikasi Indonesia Tbk berdasarkan aspek - aspek dalam Omnichannel Maturity Model , men ggunakan metode expert judgment. Hasil analisis menunjukkan bahwa Telkom telah melakukan inisiasi implementasi Omnichannel Customer Experience dengan diterapkannya platform single window yang terintegrasi di semua saluran pelanggan dan dari sembilan dimensi p engukuran Omnichannel Maturity Model mayoritas sudah berada pada level Cross Channel .

  10. Analisis Kesulitan Belajar Mahasiswa Dalam Memahami Konsep Bilangan Real

    Directory of Open Access Journals (Sweden)

    Lalu Sucipto

    2017-02-01

    Full Text Available [Bahasa]: Penelitian ini bertujuan untuk mengetahui jenis-jenis kesulitan dan faktor-faktor penyebab kesulitan yang dihadapi oleh mahasiswa dalam mengerjakan soal bilangan real. Penelitian ini merupakan penelitian kualitatif dengan menggunakan analisis deskriptif. Data dikumpulkan melalui observasi, tes dan wawancara. Hasil tes dikelompokkan berdasarkan tujuh kategori kesalahan Watson kemudian dilakukan wawancara untuk mengklarifikasi kesalahan tersebut.Hasil penelitian ini menunjukkan bahwa jenis kesalahan yang dominan terjadi pada jawaban mahasiswa berupa jenis kesalahan data tidak tepat, prosedur yang tidak tepat, konflik level respon, dan masalah hirarkhi keterampilan. Kesalahan mahasiswa dalam mengerjakan soal memberikan gambaran kesulitan yang dialami dalam memahami konsep bilangan real. Faktor yang mempengaruhi kesulitan mahasiswa yaitu: materi yang sulit dipahami dan diaplikasikan dalam pemecahan masalah; dan faktor pribadi yang mencakup pola belajar yang tidak baik, sarana pendukung, dan faktor dosen. [English]: This research aims to identify undergraduate students’ difficulties and the factors which caused them in solving real analysis problems. This qualitative research applies descriptive analysis. Data is collected through observation, test, and interview. Students’ answers on test are categorized into Watson’s seven categories of errors then the students are interviewed to clarify the errors. This research reveals that dominant errors encounterd by the students are inappropriate data, inappropriate procedure, response level conclict, and skill hierarchy problem. The errors portrait the difficulties the students encountered. The factors which cause the difficulties are the material is hard to understand and apply to problem solving; and personal factor such as bad learning habits, supporting tools, and the lecturers.

  11. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

    Disclosed is a graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels

  12. Nuclear reactors

    International Nuclear Information System (INIS)

    Humphreys, P.; Davidson, D.F.; Thatcher, G.

    1980-01-01

    The cooling system of a liquid metal cooled fast breeder nuclear reactor of the pool kind is described. It has an intermediate heat exchange module comprising a tube-in-shell heat exchanger and an electromagnetic flow coupler in the base region of the module. Primary coolant is flowed through the heat exchanger being driven by electromagnetic interaction with secondary liquid metal coolant flow effected by a mechanical pump. (author)

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Jungmann, A.

    1975-01-01

    Between a PWR's reactor pressure vessel made of steel and the biological shield made of concrete there is a gap. This gap is filled up with a heat insulation facting the reactor pressure vessel, for example with insulating concrete segments jacketed with sheet steel and with an additional layer. This layer serves for smooth absorption of compressive forces originating in radial direction from the reactor pressure vessel. It consists of cylinder-segment shaped bricks made of on situ concrete, for instance. The bricks have cooling agent ports in one or several rows which run parallel to the wall of the pressure vessel and in alignment with superposed bricks. Between the layer of bricks and the biological shield or rather the heat insulation, there are joints which are filled, however, with injected mortar. That guarantees a smooth series of connected components resistant tom compression. Besides, a slip foil can be set between the heat insulation and the joining joint filled with mortar for the reduction of the friction at thermal expansions. (TK) [de

  14. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  16. Reactor container

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Hatamiya, Shigeo; Kawasaki, Terufumi; Fukui, Toru; Suzuki, Hiroaki; Kataoka, Yoshiyuki; Kawabe, Ryuhei; Murase, Michio; Naito, Masanori.

    1990-01-01

    In order to suppress the pressure elevation in a reactor container due to high temperature and high pressure steams jetted out upon pipeway rupture accidents in the reactor container, the steams are introduced to a pressure suppression chamber for condensating them in stored coolants. However, the ability for suppressing the pressure elevation and steam coagulation are deteriorated due to the presence of inactive incondensible gases. Then, there are disposed a vent channel for introducing the steams in a dry well to a pressure suppression chamber in the reactor pressure vessel, a closed space disposed at the position lower than a usual liquid level, a first channel having an inlet in the pressure suppression chamber and an exit in the closed space and a second means connected by way of a backflow checking means for preventing the flow directing to the closed space. The first paths are present by plurality, a portion of which constitutes a syphon. The incondensible gases and the steams are discharged to the dry well at high pressure by using the difference of the water head for a long cooling time after the pipeway rupture accident. Then, safety can be improved without using dynamic equipments as driving source. (N.H.)

  17. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1989-01-01

    In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

  18. 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)

  19. Verification of reactor safety codes

    International Nuclear Information System (INIS)

    Murley, T.E.

    1978-01-01

    The safety evaluation of nuclear power plants requires the investigation of wide range of potential accidents that could be postulated to occur. Many of these accidents deal with phenomena that are outside the range of normal engineering experience. Because of the expense and difficulty of full scale tests covering the complete range of accident conditions, it is necessary to rely on complex computer codes to assess these accidents. The central role that computer codes play in safety analyses requires that the codes be verified, or tested, by comparing the code predictions with a wide range of experimental data chosen to span the physical phenomena expected under potential accident conditions. This paper discusses the plans of the Nuclear Regulatory Commission for verifying the reactor safety codes being developed by NRC to assess the safety of light water reactors and fast breeder reactors. (author)

  20. Analisis Zona Permeabel Fluida Sistem Panas Bumi Gunungapi Slamet Berdasarkan Analisis Kerapatan Kelurusan Citra SRTM Dan Struktur Geologi

    Directory of Open Access Journals (Sweden)

    Sachrul Iswahyudi

    2016-03-01

    Full Text Available Keberadaan manifestasi panasbumi di sekitar Gunungapi Slamet tidak dapat dipisahkan dari zona-zona permeabilitas yang berkembang. Lokasi-lokasi lulus air tersebut (zona permeabel yang memungkinkan terbentuknya sirkulasi fluida tempat air masuk untuk mengisi reservoir panas bumi dan air keluar ke permukaan bumi sebagai manifesatasi mata air panasbumi di sekitar Gunungapi Slamet. Publikasi yang berupa hasil penelitian ini mencoba mengidentifikasi zona-zona permeabel tersebut berdasarkan anaslisis kerapatan kelurusan yang terekam dalam citra SRTM. Identifikasi kelurusan-kelurusan pada citra berdasarkan komponen-komponen interpretasi citra, yaitu tona, tekstur, pola, bentuk dan relief. Hasil analisis tersebut dikompilasi dengan data struktur geologi regional yang sebelumnya telah diidentifikasi dan data lapangan berupa manifestasi mata air panas. Lokasi-lokasi dengan kerapatan kelurusan yang tinggi pada citra SRTM umumnya bersesuaian dengan zona struktur geologi regional keberadaan manifestasi mata air panas. Daerah tersebut memanjang relatif utara-selatan di bagian barat dan timur-barat di bagian selatan peta. Daerah-daerah inilah yang merupakan daerah lulus air tempat fluida bersirkulasi membentuk sistem panasbumi Gunungapi Slamet.

  1. Molten salt reactors: reactor cores

    International Nuclear Information System (INIS)

    1983-01-01

    In this critical analysis of the MSBR I project are examined the problems concerning the reactor core. Advantages of breeding depend essentially upon solutions to technological problems like continuous reprocessing or graphite behavior under neutron irradiation. Graphite deformation, moderator unloading, control rods and core instrumentation require more studies. Neutronics of the core, influence of core geometry and salt composition, fuel evolution, and thermohydraulics are reviewed [fr

  2. Research reactor spent fuel management in Argentina

    International Nuclear Information System (INIS)

    Audero, M.A.; Bevilacqua, A.M.; Mehlich, A.M.; Novara, O.

    2002-01-01

    The research reactor spent fuel (RRSF) management strategy will be presented as well as the interim storage experience. Currently, low-enriched uranium RRSF is in wet interim storage either at reactor site or away from reactor site in a centralized storage facility. High-enriched uranium RRSF from the centralized storage facility has been sent to the USA in the framework of the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The strategy for the management of the RRSF could implement the encapsulation for interim dry storage. As an alternative to encapsulation for dry storage some conditioning processes are being studied which include decladding, isotopic dilution, oxidation and immobilization. The immobilized material will be suitable for final disposal. (author)

  3. Analisis Efektivitas Perangkat pada Program Desa Broadband Terpadu [Analysis of Device Effectiveness in Integrated Broadband Village Program

    Directory of Open Access Journals (Sweden)

    Hilarion Hamjen

    2016-12-01

    Full Text Available Pemerintah berkomitmen mendukung pertumbuhan e-commerce dan ekonomi digital di Indonesia untuk mencapai visi Indonesia 2020 sebagai negara ekonomi digital terbesar di Asia Tenggara. Secara fundamental diperlukan dukungan konektivitas nasional dari tingkat pusat sampai ke tingkat lokal, salah satunya melalui program KPU/USO yaitu program DBT (Desa Broadband Terpadu. Penelitian ini bertujuan untuk mengetahui efektivitas perangkat pada program DBT phase 1 dan keterkaitannya dengan konektivitas, dengan menggunakan metode analisis kepentingan kinerja dan uji statistik Chi square. Berdasarkan hasil penelitian diketahui bahwa efektivitas perangkat meliputi variabel kondisi, fungsi, pemeliharaan dan pemanfaatan rata-rata adalah 84,5 persen. Dengan nilai efektivitas tersebut diketahui bahwa keseluruhan variabel kondisi perangkat, fungsi dan pemanfaatannya tidak mempengaruhi konektivitas.  *****The Indonesian government has a strong commitment in supporting the growth of e-commerce and Digital Economy in Indonesia to attain Indonesia’s vision by 2020 as the largest digital economy nation in Southeast Asia. Fundamentally, the national connectivity supports from central level to local level are needed, where one of them comes from Integrated Broadband Village program. This research determines the effectiveness of devices in the DBT program and its correlation to the connectivity, by using importance-performance analysis method and Chi-square statistical test. It is known from the result that the effectiveness of devices, including condition, function, maintenance, and utilization variables, achieves 84.5 percent on average. The value shows that all mentioned variables have insignificant correlations to the connectivity.

  4. Analisis Neraca Air Lahan untuk Tanaman Padi dan Jagung Di Kota Bengkulu

    Directory of Open Access Journals (Sweden)

    Jaka A. I. Paski

    2018-01-01

    Citation: Paski, J.A.I., Faski, G.I.S.L., Handoyo, M.F. dan Pertiwi, D.A.S. (2017. Analisis Neraca Air Lahan untuk Tanaman Padi dan Jagung di Kota Bengkulu. Jurnal Ilmu Lingkungan, 15(2, 83-89, doi:10.14710/jil.15.2.83-89

  5. ANALISIS RASIO ALTMAN MODIFIKASI PADA PREDIKSI KEBANGKRUTAN PERUSAHAAN PROPERTY DAN REAL ESTATE YANG TERDAFTAR DI BEI

    OpenAIRE

    Anita Tri Widiyawati; Supri Wahyudi Utomo; Nik Amah

    2015-01-01

    Penelitian ini bertujuan untuk mengetahui pengaruh rasio Altman Modifikasi terhadap prediksi kebangkrutan. Jenis penelitian ini termasuk penelitian kuantitatif. Populasi dalam penelitian ini adalah perusahaan property dan real estate yang terdaftar di BEI. Teknik pengambilan sampel menggunakan purposive sampling sehingga diperoleh sampel sejumlah 32 perusahaan property dan real estate yang menerbitkan laporan keuangannya selama tahun 2011-2013. Teknik analisis data menggunakan regresi logisti...

  6. Analisis Perbandingan Material Slab Beton Pada Perkerasan Apron Dengan Menggunakan Program Bantu Elemen Hingga

    Directory of Open Access Journals (Sweden)

    Hendrawan Setyo Warsito

    2016-04-01

    Full Text Available Kekuatan slab beton sangat dipengaruhi oleh jenis material yang dipakai. Jenis material yang dimaksud adalah material beton dengan menggunakan PC (Portland Cement dan penggunaan geopolimer dalam komposisi campuran slab beton. Beton geopolimer merupakan beton yang ramah lingkungan. Permasalahan lain yang timbul adalah letak roda pesawat tidak selalu berada pada titik yang sama disuatu permukaan slab beton apron. Pada tugas akhir ini dimaksudkan untuk menganalisis suatu slab beton yang dibebani roda pesawat dengan campuran variasi material beton dan variasi letak roda pesawat pada slab beton dengan program bantu metode elemen hingga. Dengan data pergerakan pesawat, spesifikasi apron bandara Juanda kondisi eksisting. Dilakukan perhitungan tebal slab beton menggunakan software FAARFIELD dan diperoleh tebal slab beton sebesar 442,5 mm. Dari analisis program bantu elemen hingga dapat diperoleh tegangan pada slab beton yang ditimbulkan oleh pembebanan roda pesawat. Hasil validasi dari analisis tegangan menggunakan program bantu elemen hingga dengan analisis Westergaard yaitu memiliki nilai tegangan yang hampir sama pada ketebalan slab beton 450mm. Nilai tegangan tiap-tiap material beton menunjukan nilai tebal slab beton yang diijinkan untuk tipe pesawat tertentu. Dari analisis menggunakan program bantu elemen hingga tebal slab beton yang diijinkan untuk material slab beton PC yaitu sebesar 425mm. Sedangkan untuk material beton geopolimer yaitu sebesar  415 mm.

  7. Analisis Faktor Pembentuk Ekuitas Merek Toyota dan Daihatsu di Indonesia (Studi Komparasi pada Masyarakat Bandung)

    OpenAIRE

    Sigiro, Cristine Afriani; Rachma Putri, Yuliani; Ilfandy Imran, Ayub

    2016-01-01

    Toyota dan Daihatsu merupakan dua merek otomotif (mobil) yang sangat fenomenal di kalangan masyarakat Indonesia. Produk dari kedua merek tersebut memiliki persamaan yang identik, namun Toyota memasarkan produknya lebih mahal dibandingkan Daihatsu. Tujuan penelitian ini untuk mengetahui perbandingan ekuitas merek Toyota dan Daihatsu menurut masyarakat Bandung. Penelitian ini menggunakan paradigma penelitian positivistik dengan metode penelitian studi komparatif melalui teknik analisis data yan...

  8. ANALISIS PENGARUH CUSTOMER RELATIONSHIP MANAGEMENT TERHADAP KEPUASAN PELANGGAN PADA PT TELKOMSEL DI MAKASSAR

    OpenAIRE

    ANANDA, RACHMA RESKY

    2015-01-01

    2015 Analisis Pengaruh Customer Relationship Management Terhadap Kepuasan Pelanggan Pada PT Telkomsel di Makassar Analysis of Customer Relationship Management Influence to Customer Satisfaction at PT Telkomsel in Makassar Rachma Resky Ananda Muh. Asdar Yansor Djaya Tujuan dari penelitian ini adalah untuk menganalisis pengaruh Customer Relationship (continuity marketing, one to one marketing dan partnering atau co-marketing) terhadap k...

  9. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  10. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

  11. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Jolly, R.

    1979-01-01

    The support grid for the fuel rods of a liquid metal cooled fast breeder reactor has a regular hexagonal contour and contains a large number of unit cells arranged honeycomb fashion. The totality of these cells make up a hexagonal shape. The grid contains a number of strips of material, and there is a window in each of three sidewalls staggered by one sidewall. The other sidewalls have embossed protrusions, thus generating a guide lining or guide bead. The windows reduce the rigidity of the areas in the middle between the ends of the cells. (DG) [de

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  14. Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

    International Nuclear Information System (INIS)

    Wittenbrock, N.G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

  15. ANALISIS PENGARUH IRADIASI FLUENS NEUTRON CEPAT TERHADAP BERILIUM REFLEKTOR REAKTOR RSG-GAS

    Directory of Open Access Journals (Sweden)

    Sri Kuntjoro

    2015-04-01

    Full Text Available Telah dilakukan analisis iradiasi fluens neutron cepat terhadap berilium reflektor reaktor RSG-GAS. Analisis dilakukan dengan cara melakukan pengukuran fluks neutron di posisi berilium elemen dan berilium blok yang berfungsi sebagai reflector. Selanjutnya dilakukan perhitungan untuk menentukan apakah ada pengaruh fluens neutron selama berilium berada di teras reaktor. Selain cara tersebut dilakukan pula visualisasi untuk memastikan ada tidaknya deformasi pada berilium akibat iradiasi. Hasil pengukuran fluks dan fluens neutron cepat maksimal pada daya 200 kW untuk berilium elemen posisi E-2 sebesar 2,30E+07 n/cm2s dan 4,19E+17 n/cm2, J-8 sebesar 3,70E+07 n/cm2s dan 6,74E+17 n/cm2. Hasil pengukutan pada posisi B-3 sebesar 2,19E+12 n/cm2s dan 3,99E+22 n/cm2, G-10 sebesar 2,12E+12 n/cm2s dan 3,86E+22 n/cm2, serta berilium blok posisi (5-6 sebesar 5,02E+07 n/cm2s dan 9,15E+17 n/cm2, (C-D sebesar 2,32E+07 n/cm2s dan 4,23E+17 n/cm2. Deformasi yang diperoleh untuk berilium elemen (∆L/L posisi E-2 sebesar 1,12E-08, J-8 sebesar 1,84E-08, B-3 sebesar 1,60E-03, posisi G-10 sebesar 1,55E-03, sedangkan pada berilium blok di posisi 5-6 sebesar 2,52E-08 dan C-D sebesar 1,13E-08. Dari hasil ini disimpulkan tidak terjadi deformasi pada berilium elemen dan berilium blok. Hasil ini dibuktikan pula dari pengamatan visual, dimana tidak terlihat adanya deformasi pada berilium tersebut. Kata kunci : fluks, fluens, berilium elemen, berilium blok   Analysis of influence fast neutron fluence irradiated to the RSG-GAS beryllium reflector have been done. Methods of analysis was carried out by measuring fluxs neutron in beryllium element and block positio that function as reflector. The calculation done for determination it is there any influence of neutron as long as beryllium in the core. Bisede that, visualization done to make sure it there is any deformation at beryllium as efect of irradiation. Fluxs and fluences of beryllium element measurement result in 200 k

  16. APLIKASI METODE-METODE AGGLOMERATIVE DALAM ANALISIS KLASTER PADA DATA TINGKAT POLUSI UDARA

    Directory of Open Access Journals (Sweden)

    Dewi Rachmatin

    2014-09-01

    Full Text Available ABSTRAK   Analisis Klaster merupakan analisis pengelompokkan data yang mengelompokkan data berdasarkan informasi yang ditemukan pada data. Tujuan dari analisis klaster adalah agar objek-objek di dalam satu kelompok memiliki kesamaan satu sama lain sedangkan dengan objek-objek yang berbeda kelompok memiliki perbedaan. Analisis klaster dibagi menjadi dua metode yaitu metode hirarki dan metode non-hirarki. Metode hirarki dibagi menjadi dua, yaitu metode agglomerative (pemusatan dan metode divisive (penyebaran. Metode-metode yang termasuk dalam metode agglomerative adalah Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward’s Method, Centroid Method dan Median Method. Pada artikel ini dibahas metode-metode agglomerative tersebut yang diterapkan pada data tingkat polusi udara. Masing-masing metode tersebut memberikan jumlah klaster yang berbeda.   Kata Kunci : Analisis Klaster, Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward’s Method, Centroid Method dan Median Method.     ABSTRACT Cluster analysis is an analysis of the data classification based on information found in the data.The objective of cluster analysis is that the objects in the group have in common with each other, while the different objects have different groups. Cluster analysis is divided into two methods : the method of non-hierarchical and hierarchical methods.Hierarchical method is divided into two methods, namely agglomerative methods (concentration and divisive methods (deployment. The methods included in the agglomerative method is Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward 's Method, Method and Median Centroid Method. In this article discussed the agglomerative methods were applied to the data rate of air pollution. Each of these methods provides a different number of clusters.   Keywords: Cluster Analysis , Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward

  17. Reactors set for mini market

    International Nuclear Information System (INIS)

    Knox, Richard.

    1988-01-01

    Commercial nuclear power generation on a large-scale has an uncertain future. However, it is hoped that a small nuclear reactor could form the basis for providing heating, cooling or electricity in large buildings. Based on the Slowpoke research reactor, the Slowpoke energy system concept is simple. The concept and the way in which the small-scale reactor would work are discussed. The system consists of a stainless steel tank surrounded by reinforced concrete and let into the ground. The tank is full of light water which is heated to about 90 deg C by a central core of 2.4 percent enriched uranium fuel. The resulting natural circulation causes the water to pass through a heat exchanger. The water from the heat exchanger can be used for building or district heating, to operate air-conditioners or to generate small quantities of electricity. It is hoped to automate the operation of the reactor so that continuous supervision by a team of engineers would be unnecessary. A single operator on call in the building would be able to take control actions if the reactor's safety system failed. (UK)

  18. Australia needs to replace the HIFAR reactor

    International Nuclear Information System (INIS)

    Garnett, Helen

    1993-01-01

    Central to the execution of ANSTO's objectives has been the operation since 1958 of the multipurpose HIFAR research reactor and related infrastructure. However, HIFAR's irradiation facilities, which are used for the provision of radiopharmaceuticals essential for nuclear medicine in Australia, have a limited capacity. The author stated that HIFAR's neutron beam facilities, which are needed by Australian scientists to undertake basic structural studies on a wide range of materials, are unable to provide the resolution and information required to keep Australia in the league of technologically advanced nations. The neutron flux and design limitations of older reactors such as HIFAR inhibit the upgrading of neutron beam facilities to modern standards. It is emphasised that while the cost of the new reactor is a vital issue, what is a prevailing importance is analyses of the cost-benefit and effectiveness of the new reactor, which will be undertaken by the Research Reactor Review. Some of these benefits are briefly outlined. ills

  19. Operational and reliability experience with reactor instrumentation

    International Nuclear Information System (INIS)

    Dixon, F.; Gow, R.S.

    1978-01-01

    In the last 15 years the CEGB has experienced progressive plant development, integration and changes in operating regime through nine nuclear (gas-cooled reactor) power stations with corresponding instrumentation advances leading towards more refined centralized control. Operation and reliability experience with reactor instrumentation is reported in this paper with reference to the progressive changes related to the early magnox, late magnox and AGR periods. Data on instrumentation reliability in terms of reactor forced outages are presented and show that the instrumentation contributions to loss of generating plant availability are small. Reactor safety circuits, neutron flux and temperature measurements, gas analysis and vibration monitoring are discussed. In reviewing the reactor instrumentation the emphasis is on reporting recent experience, particularly on AGR equipment, but overall performance and changes to magnox equipment are included so that some appreciation can be obtained of instrumentation requirements with respect to plant lifetimes. (author)

  20. Developments in the regulation of research reactors

    International Nuclear Information System (INIS)

    Loy, J.

    2003-01-01

    The International Atomic Energy Agency (IAEA) has data on over 670 research reactors in the world. Fewer than half of them are operational and a significant number are in a shutdown but not decommissioned state. The International Nuclear Safety Advisory Group (INSAG) has expressed concerns about the safety of many research reactors and this has resulted in a process to draw up an international Code of Conduct on the Safety of Research Reactors. The IAEA is also reviewing its safety standards applying to research reactors. On the home front, regulation of the construction of the Replacement Research Reactor continues. During the construction phase, regulation has centred around the consideration of Requests for Approval (RFA) for the manufacture and installation of systems, structures and components important for safety. Quality control of construction of systems, structures and components is the central issue. The process for regulation of commissioning is under consideration

  1. MENENTUKAN PRIORITAS PILIHAN MAHASISWA DALAM MEMILIH KAMPUS MENGGUNAKAN ANALISIS CONJOINT

    Directory of Open Access Journals (Sweden)

    Maxsi Ary

    2016-03-01

    menganalisis preferensi mahasiswa Jurusan Manajemen Informatika AMIK BSI Bandung dalam memilih kampus. Penelitian preferensi mahasiswa dalam memilih kampus dilakukan dengan mengaplikasikan analisis conjoint menggunakan SPSS 17.0. Cara yang dilakukan adalah dengan memperoleh skor kegunaan yang dapat mewakili setiap aspek faktor jasa kampus yang dimiliki, sehingga dari skor tersebut dapat ditarik kesimpulan tentang atribut apa saja yang paling dipertimbangkan oleh mahasiswa dalam memilih kampus. Hasil preferensi responden yang bernilai paling tinggi adalah faktor Lapangan (14.92%, Kurikulum (13.21%, Akreditasi (12.75%, Dosen (12.13%, Gedung (11.96%, Perpustakaan (11.87%, Jarak (11.66%, dan Iklan (11.46%. Hasil utilitas agregat level faktor/atribut pilihan responden, bahwa responden menyukai jasa pendidikan dalam pemilihan kampus adalah kampus memiliki lapangan, kurikulum terbuka (pihak administasi menyampaikan terlebih dahulu diawal pendaftaran, kampus telah terakreditasi, pilihan dosen senior, ukuran gedung biasa saja (kurang diperhatikan, perpustakaan memiliki banyak koleksi buku, jarak antara rumah dan kampus dekat, dan iklan kurang diperhatikan. Kata Kunci: Statistik Multivariat, Analisis Conjoint, Preferensi

  2. Kembalikan Lagu Anak-anak Indonesia: Sebuah Analisis Struktur Musik

    Directory of Open Access Journals (Sweden)

    Ardipal - -

    2015-12-01

    . Yaitu musik sebagai pengembangan seni di lingkungan tertentu  dan musik sebagai seni komersial. Dari sisi musik komersial, hampir dua dekade terakhir  ini lagu anak-anak menghilang di media massa. Digantikan oleh lagu orang dewasa. Hal ini tentu mempengaruhi perkembangan psikologis, fisik, dan mental anak-anak. Secara teoritik, masalah ini hal ini dapat ditinjau dari produksi musik melalui pendekatan (1 konfik (hegemoni dan (2 interpretasi/makna. Penelitian ini bertujuan untuk membandingkan struktur musik lagu anak-anak dan struktur musik orang dewasa. Data diambil dari lagu anak-anak dan lagu pop orang dewasa. Metoda analisis difokuskan pada fitur lagu berdasarkan struktur musik dan dampaknya. Instrumen kunci dalam penelitian adalah peneliti sendiri dan instrumen pembantu berupa panduan kodifikasi data. Kemudian mendeskripsikan unsur-unsur tersebut yang terdapat dalam beberapa lagu anak-anak dan dewasa. Untuk menjaga keabsahan data, dilakukan kegiatan triangulasi data. Kegiatan analisis data dimulai dari tahap memilih dan mengodifikasi data, menganalisis data sesuai dengan fitur musiknya masing-masing, dan tahap menarik kesimpulan serta verifikasi. Dari data lagu yang diambil sebagai sampel penelitian, terlihat bahwa pola ritmis, melodis, interval, tempo, hingga rentang nada belum laik  dinyanyikan oleh anak-anak. Pemaksaan anak-anak untuk meniru lagu tersebut dapat berakibat fatal seperti kerusakan pita suara, kram otot rahang. Akhirnya, disarankan agar partisipan seni, dan juga Demikian juga jaringan infrastuktur seni, harus dapat memiliki pandangan yang sama dan kuat  dalam pengembangan seni musik di Indonesia, khususnya untuk lagu anak-anak. Kata Kunci: lagu anak-anak, lagu perjuangan, lagu orang dewasa, struktur musik

  3. Analisis Penerapan E-Government di Kabupaten Sragen

    Directory of Open Access Journals (Sweden)

    Yan Andriariza AS

    2013-09-01

    Full Text Available ABSTRAK Kabupaten Sragen merupakan salah satu pemerintah kabupaten yang menerapkan e-government dengan baik, dan merupakan kabupaten yang menjadi percontohan dalam suksesnya penerapan e-government. Karenanya perlu untuk dilakukan analisis penerapan e-government di Kabupaten Sragen, sebagai contoh bagi daerah lain dalam membangun e-government di daerah tersebut. Analisa yang dilakukan antara lain melihat seberapa jauh penerapan G2C, G2B dan G2G di Pemerintah Kabupaten Sragen. Selain itu juga dilakukan analisa menggunakan The UN Web Measure Index, dan analisa terakhir melakukan analisa deskriptif untuk 5 faktor kesuksesan penerapan e-government, yaitu Hukum dan Peraturan, Struktur Organisasi, Proses Bisnis, Teknologi Informasi dan Visi, Objektif dan Strategi. Dari hasil analisis diperoleh kesimpulan bahwa Kabupaten Sragen telah menerapkan G2B dan G2G, serta berada pada tahap awal penerapan G2C, selain itu Kabupaten Sragen juga telah mencapai pemerintahan yang online, tanpa kertas dan transparan. Implementasi e-government di kabupaten Sragen tersebut dapat dikatakan sukses karena telah memenuhi beberapa faktor dalam mencapai kesuksesan implementasi e-government, yaitu hukum dan peraturan, struktur organisasi, teknologi informasi dan visi, objektif dan strategi. Bila dilihat berdasarkan UN Web Measured Index, Kabupaten Sragen telah mencapai tahap 4. Saran yang dapat diberikan melalui penelitian ini adalah untuk unit kerja yang menangani TIK di Kabupaten Sragen akan lebih baik bila dipegang oleh unit kerja setingkat eselon 2 dan perlunya SOP dan peraturan tambahan terkait TIK di Kabupaten Sragen. ABSTRACT Sragen is one of the districts that implement well e-government, and being a model for the successful implementation of e-government. It is necessary to do the analysis of the application of e-government in Sragen, as an example for other regions in developing e-government in the area. Analysis was carried out to see how far the application of G2C

  4. Analisis Karaterisasi Konsentrasi dan Komposisi Partikulat Udara (Studi Case : Surabaya

    Directory of Open Access Journals (Sweden)

    Eka Fithriani Ahmad

    2016-12-01

    Full Text Available Abstrak Pencemaran udara merupakan dampak yang sangat merugikan, tidak hanya bagi manusia tetapi juga akan berdampak buruk bagi ekosistem hewan dan tumbuhan. Pada penelitian ini akan mengkaji pencemaran udara dari Oktober 2012 hingga Februari 2014 melalui penelitian konsentrasi dan komposisi dari partikulat udara dengan ukuran PM 2.5. Penelitian ini bertujuan untuk menentuan sumber asal pencemaran di Surabaya sehingga dapat dijadikan referensi berbasis ilmiah sebagai langkah untuk membuat keputusan dan kebijakan yang tepat dalam menanggulangi dampak pencemaran. Metode pengolahan data dalam penelitian ini adalah dengan menggunakan analisis reseptor modeling yaitu Positif Matrix Factorization (PMF untuk mengetahui sumber asal pencemaran. Hasil pengukuran yang diperoleh pada konsentrasi PM 2,5 adalah 15.05 μg/m3 sehingga telah melebihi baku mutu tahunan yang telah ditetapkan PP 41 tahun 1999, USEPA, maupun WHO. Dalam partikulat terdapat konsentrasi black carbon (BC sebesar 3.20 μg/m3 dan unsur Pb dengan konsentrasi 0.28 μg/m3 yang telah melebihi nilai baku mutu USEPA. Sedangkan hasil analisis reseptor modeling di dapatkan sumber asal polutan berasal dari biomass, vehicle, soil, industri Pb, industri Zn dan indutri Fe. Kata kunci: Partikulat mater 2.5, black carbon, Pb, positive matrix factorization, Surabaya   Abstract Air pollution is a very adverse impact, not only for humans but also the ecosystem of plants and animals. This research examine air pollution from October 2012 until February 2014 through the research of concentration and composition of airborne particulates with a size of PM 2.5 μm. This study aims to determine the origin and location of pollution sources in Surabaya so that it can be used as scientific reference as a step to make the right decisions and policies in tackling the impact of pollution. Data processing method in this research used analysis of receptor modeling that is Positive Matrix Factorization (PMF to determine

  5. ANALISIS POTENSI RETRIBUSI PELAYANAN PASAR DI KABUPATEN KENDAL

    Directory of Open Access Journals (Sweden)

    Herru Dwi Haryono

    2017-06-01

    Full Text Available Selama periode 2008-2012, realisasi retribusi pelayanan pasar ini mengalami tren naik turun. Sedangkan dari target yang ditentukan dalam komponen retribusi pelayanan pasar yakni retribusi pasar, retribusi sampah/kebersihan dan retribusi sewa kios rata-rata selalu terealisasi melebihi target. Penelitian ini bertujuan untuk mengetahui potensi retribusi pelayanan pasar di Kabupaten Kendal dan apakah target yang ditentukan sudah berdasarkan potensi yang ada. Data yang digunakan dalam penelitian ini adalah data sekunder. Data sekunder dalam penelitian ini berupa data yang bersumber dari BPS Kabupaten Kendal, DPPKAD    Kabupaten Kendal, Disperindag  Kabupaten  Kendal dan  UPTD Dinas  Pasar Kabupaten  Kendal.  Metode analisis yang digunakan yakni analisis deskriptif yakni menghitung potensi retribusi pelayanan pasar di Kabupaten Kendal dan membandingkan potensi dengan target dan apakah target yang ditentukan sesuai berdasarkan potensi yang ada. Hasil penelitian menunjukkan bahwa (1 potensi retribusi pelayanan pasar di Kabupaten Kendal sebesar Rp.5.130.789.600 pertahun. (2 target retribusi pelayanan pasar di Kabupaten Kendal selalu berada dibawah potensi yang ada, jadi kesimpulannya bahwa mekanisme penentuan target tidak berdasarkan potensi yang ada. Berdasarkan hasil anasilis data tersebut, saran yang dapat disampaikan adalah agar pemerintah daerah ataupun pengelola pasar dapat memanfaatkan secara maksimal potensi yang ada agar realisasi penerimaan retribusi pelayanan pasar dapat ditingkatkan lagi dan hendaknya mengevaluasi mekanisme penetapan target berdasarkan potensi yang ada agar kinerja pemerintah maupun pengelola pasar dapat ditingkatkan lagi yang akan berdampak pada realisasi penerimaan retribusi pelayanan pasar. During the period 2008-2012, the actual levy of service this market has been trending up and down. While the targets specified in the component market services levy market fees, garbage fees / levies hygiene and the average

  6. ANALISIS FAKTOR-FAKTOR YANG MEMPENGARUHI IMPOR BAJA DI INDONESIA

    Directory of Open Access Journals (Sweden)

    Jhonson Agustinus Pasaribu

    2017-06-01

    Full Text Available Impor baja terus mengalami peningkatan dari tahun 1980-2012, hal ini disebabkan karena tingkat produksi baja tidak mampu mengimbangi dan memenuhi tingkat konsumsi baja. Penelitian ini bertujuan untuk menganalisis faktor-faktor yang mempengaruhi impor baja di Indonesia. Metode analisis yang digunakan adalah Error Corection Model (ECM. Pengujian secara parsial digunakan uji t-statistik dan pengujian secara serempak digunakan uji F-statistik. Hasil penelitian ini menunjukan bahwa Produksi baja berpengaruh negatif dan signifikan terhadap impor baja dalam jangka panjang dan jangka pendek. Konsumsi baja menunjukan pengaruh positif dan signifikan terhadap impor baja dalam jangka panjang dan jangka pendek. Gross Domestic Product (GDP menunjukan pengaruh yang negatif dan tidak signifikan terhadap impor baja dalam jangka panjang dan jangka pendek. Nilai tukar rupiah (Kurs menunjukan pengaruh yang positif dan tidak signifikan terhadap impor baja dalam jangka panjang dan jangka pendek.  The steel import keep having enhancement from 1980 to 2012, it’s because of steel production level can’t fulfill the steel consumption level. If the high level of the steel import volume continues, domestic steel industries will run into a low impact for Indonesian’s economy. The goal of this research analize the affecting factors of steel import in Indonesia. The analytical method use the Error Correction Model (ECM. The partial test use t-statistic and the simultan test use F-statistic. The results showed that the steel production has negative and significant effect on steel import in the long term and short term. The steel consumption has positive and significant effect on steel import in the long term and short term. The Gross Domestic Product (GDP has negative and not significant effect on steel import in the long term and short term. The exchange rate indicates positive and not significant effect on steel import in the long term and short term.

  7. ANALISIS REKRUITMEN TENAGA PENDIDIK PADA SD KALAM KUDUS PEKANBARU

    Directory of Open Access Journals (Sweden)

    Murnawati Murnawati

    2015-04-01

    Full Text Available Abstrak: Penelitian ini dilakukan untuk mengetahui sistem rekrutmen tenaga pendidik pada SD kalam kudus kota Pekanbaru. Populasi dalam penelitian ini adalah tenaga pendidik di SD Kalam Kudus Kota Pekanbaru, kebutuhan guru sebanyak 65 sedangkan guru tetap sebanyak 40 guru dan sisanya guru honor sebanyak 25 guru. Dalam penelitian ini penulis mengambil sampel seluruh populasi. Pengambilan sampel dilakukan secara sensus. Data yang digunakan adalah data primer yang diperoleh dari wawancara langsung dan penyebaran kuesioner. Analisis data dalam penelitian ini adalah menggunakan metode deskriptif. Berdasarkan hasil penelitian dapat disimpulkan bahwa persyaratan administrasi dalam rekruitmen guru diperoleh rata – rata skor sebesar 3,49. Artinya persyaratan administrasi dalam rekruitmen guru pada SD Kalam Kudus Pekanbaru dinilai baik. Abstract: This research aimed to determine the system of teachers’s recruitment in Kalam Kudus elementary school of Pekanbaru. The population in this study were educators in in Kalam Kudus elementary school of Pekanbaru, the teacher needs as much as 65 while the teacher remains as much as 40 teachers and teacher salaries remaining 25 teachers. In this study the authors took samples of the entire population. Sampling was done by census. The data used is primary data obtained from interviews and questionnaires. Data analyzed by descriptive method. Based on the results of this study concluded that the administrative requirements for the recruitment of teachers obtained average - average score of 3.49. This means that the administrative requirements for the recruitment of teachers in elementary Holy Kalam Pekanbaru considered good. Kata Kunci : Rekruitmen, Tenaga Pendidik

  8. ANALISIS EFEKTIVITAS PEMBERIAN PINJAMAN PROGRAM PEMBIAYAAN UMKM OLEH KOPERASI

    Directory of Open Access Journals (Sweden)

    Hadi Ismanto

    2014-10-01

    Full Text Available Abstrak: Analisis Efektivitas Pemberian Pinjaman Program Pembiayaan UMKM Oleh Koperasi. Program Pembiayaan memiliki peran yang penting bagi UMKM, namun sering menghadapi masalah penunggakan dan kemacetan pembayaran angsuran. Penelitian ini berupaya untuk mengetahui sebab-sebab tidak lancarnya pengembalian Program Pembiayaan UJKS sehingga diharapkan dapat menyusun strategi yang lebih baik lagi dalam menyeleksi calon peminjam agar angka pinjaman bermasalah dapat ditekan. Populasi dalam penelitian ini adalah semua UMKM yang menjadi Peminjam (peminjam program pembiayaan UJKS Mitra Usaha dan masih tergolong aktif hingga bulan November 2013 dan telah memperoleh fasilitas pembiayaan sekurang-kurangnya enam bulan berjalan. Penelitian ini menemukan bahwa faktor-faktor yang berpengaruh positif terhadap tingkat pengembalian pinjaman (lancar atau menunggak adalah omzet usaha, lama usaha dan nilai plafon pinjaman. Hal ini dapat dijadikan bahan pertimbangan bagi UJKS dalam menjalankan program pembiayaan sehingga menjadi lebih efektif dalam menjalankannya.   Kata Kunci: UMKM, UJKS, Program Pembiayaan, Lancar, dan Macet.   Abstract: Effectiveness Analysis of SMEs Financing Program by Cooperative. Financing programs have an important role to SMEs, but often face the problem of repayment failures and installment payments. This study examines the causes of saving and loan cooperatives’ repayment problems. The population of this study is all SMEs borrowing from Mitra Usaha saving and loan cooperative. Furthermore these SMEs must be categorized as active SMEs until November 2013 and they had been receiving loan for at least six months. The study found that the variables such as: the length of the business, the business volume, and the value of the loan have a positive impact on repayment rate.   Keywords: SMEs, Saving and Loan Cooperative, Financing Program

  9. Analisis Kinerja Penerapan Container untuk Load Balancing Web Server

    Directory of Open Access Journals (Sweden)

    Muhammad Agung Nugroho

    2016-12-01

    Full Text Available Container merupakan teknologi virtualisasi terbaru. Container memudahkan system administrator dalam mengelola aplikasi pada server. Docker container dapat digunakan untuk membangun, mempersiapkan, dan menjalankan aplikasi. Dapat membuat aplikasi dari bahasa pemrograman yang berbeda pada lapisan apapun. Aplikasi dapat di bungkus dalam container, dan aplikasi dapat berjalan pada lingkungan apapun dimana saja.  Dalam perkembangannya container ini dapat digunakan untuk load balancing, dengan memanfaatkan HA Proxy. Load Balancing dapat digunakan untuk menyelesaikan permasalahan beban kinerja web server yang terlalu berat (overload terhadap permintaan. Load Balancing merupakan salah satu metode untuk meningkatkan skalabilitas web server sekaligus mengurangi beban kerja web server. Ujicoba dilakukan dengan memberikan beban request pada single container dan multi container, dan membandingkan kinerjanya. Analisis kinerja dapat dilakukan dengan menggunakan parameter performance pada processor, memori dan proses layanan. Penerapan ujicoba dilakukan pada raspberry pi. Hasil yang diperoleh multi container dapat digunakan untuk mengembangkan metode load balancing, hasil ujicoba menunjukkan performance raspberry pi dapat optimum karena pembagian beban processor.

  10. ANALISIS FAKTOR-FAKTOR YANG MEMPENGARUHI PENERIMAAN PAJAK

    Directory of Open Access Journals (Sweden)

    Phany Ineke Putri

    2013-09-01

    Full Text Available The purpose of this study was to analyze the influence of population, income per capita, inflation and the number of Trade Permit toward billboard tax revenue in Purbalingga. The results of this study is expected to provide benefit and input to the Local Government of Purbalingga, especially Departement of management of financial income and regional asset. Analysis tool used is multiple linear regression (Multiple Linear Regression Method by the method of least squares Ordinary Least Square (OLS. Jointly test results showed that overall independent variables (population, income per capita, inflation, and the number of trade permit together to show their effects on the billboard tax revenue. Adjusted R-Squared value of 0,951, which means 95,1 percent of the four independent variables. While the remaining 4,9 percent is explained by other causes outside the model. The results showed that the per capita income variable and the number of trade permit have a significant positive effect, the inflation variable has a significant negative effect, whereas a number of population variable have a positive effect which is not significant at α = 5 percent of tax revenue in Purbalingga billboard. Tujuan dari penelitian ini adalah untuk menganalisis pengaruh jumlah penduduk, pendapatan per kapita, inflasi dan jumlah surat ijin usaha perdagangan (SIUP terhadap penerimaan pajak reklame di Kabupaten Purbalingga. Manfaat penelitian ini diharapkan menjadi bahan masukan Pemerintah Kabupaten Purbalingga khususnya Dinas Pengelolaan, Pendapatan, Keuangan dan Aset Daerah. Teknik analisis yang digunakan adalah regresi berganda dengan metode Ordinary Least Square (OLS. Hasil penelitian menunjukkan ada pengaruh secara bersama-sama variabel jumlah penduduk, pendapatan per kapita, inflasi dan jumlah surat ijin usaha perdagangan terhadap penerimaan pajak reklame. Koefisien determinasi 95,1% dapat dijelaskan oleh variabel independen terhadap variabel dependen, dan sisanya

  11. Analisis Elektron Beam Profile Constancy pada Pesawat Linac

    Directory of Open Access Journals (Sweden)

    Edi Guritna

    2018-02-01

    Full Text Available Radioterapi adalah pengobatan penyakit terutama tumor atau kanker ganas dengan menggunakan radiasi elektromagnetik (Sinar-X dan Gamma dan radiasi partikel (elektron, proton, dan neutron. Salah satu alat radioterapi modern yang digunakan dalam pengobatan penyakit kanker adalah linear accelerator (linac. Alat radioterapi ini menghasilkan elektron dan sinar-X (foton yang dibangkitkan oleh generator dan mempunyai energi yang bervariasi. Dalam penelitian profil dosis, digunakan pesawat liner accelerator (linac Siemens Primus berkas elektron 5 MeV dengan luas lapangan radiasi berkisar dari 5×5 cm2 sampai 25×25 cm2. Pengukuran profil dosis dilakukan dengan menggunakan water phantom,  detektor farmer chamber dan condenser chamber yang dilengkapi dengan  computer control units (CCU serta dilakukan untuk arah crossline dan inline pada kedalaman Dmax dan kedalaman tertentu. Penelitian ini bertujuan untuk menganalisis profil berkas sinar elektron energi 5 MeV pada kedalaman tertentu dan Dmax dengan variasi luas lapangan 5×5 cm2, 10×10 cm2, 15×15 cm2, 20×20 cm2, 25×25 cm2. Hasil analisis profil dosis pada berkas elektron 5 MeV menunjukkan bahwa lapangan 5×5 cm2 memiliki nilai flatness yang cukup besar sehingga dalam kalibrasi maupun terapi radiasi perlu diperhatikan penggunaan  luas lapangan tersebut. Dalam penelitian ini juga didapatkan bahwa nilai flatness paling ideal (nilai flatness rendah terjadi pada lapangan 15×15 cm2. Sehingga ada luas lapangan lain yang bisa digunakan untuk treatment maupun kalibrasi selain 10×10 cm2 yaitu 15×15 cm2 yang memiliki nilai flatness rendah.

  12. ANALISIS JENIS, JUMLAH DAN MUTU SARAPAN PAGI SISWA SEKOLAH DASAR

    Directory of Open Access Journals (Sweden)

    Sopiyandi Sopiyandi

    2016-01-01

    Full Text Available Abstract: Type Analysis, Number and Quality Breakfast of Children on Elementary School. The research objective is to analyze the full breakfast at the elementary school students in District Rasau Jaya covering aspects of the type, quantity and quality of the breakfast. This research is an analytic with Cross sectional study design. Subjects were students at SDN 1 Rasau Jaya aged 8-12 years, a large sample of 215 respondents. The results showed that as many as 98.6% of students breakfasts with ten types of food most consumed by children during breakfast ie eggs, white rice, fried rice, yellow rice, tempeh, bulb meatballs, dumplings, bread, sausages and porridge. While the five types of beverage most consumed by children during breakfast was tea, milk, juice, water, and syrup. 54% of the number of good energy, 51% protein and 68.4% fat in both categories. 61.9% carbohydrate intake is not good. The nutritional quality of food is quite good kid. Abstrak : Analisis Jenis, Jumlah Dan Mutu Sarapan Pagi Siswa Sekolah Dasar. Tujuan penelitian yaitu untuk menganalisis sarapan pagi pada siswa Sekolah Dasar di Kecamatan Rasau Jaya meliputi aspek jenis, jumlah dan mutu sarapan. Penelitian ini bersifat analitik dengan desain penelitian Cross sectional. Subjek penelitian adalah siswa SDN 1 Rasau Jaya usia 8-12 tahun, besar sampel penelitian sebanyak 215 responden. Hasil penelitian menunjukkan bahwa sebanyak 98,6 % siswa sarapan dengan sepuluh jenis makanan yang paling banyak dikonsumsi oleh anak selama sarapan yaitu telur ayam, nasi putih, nasi goreng, nasi kuning, tempe, pentol bakso, siomay, roti, sosis, dan bubur. Sedangkan lima jenis minuman yang paling banyak dikonsumsi oleh anak selama sarapan adalah teh, susu, air jeruk, air putih, dan sirup. Sebanyak 54% jumlah energi baik, protein 51 % dan lemak 68,4% pada kategori baik. 61,9% asupan karbohidrat tidak baik. Mutu gizi pangan anak tergolong baik.

  13. ANALISIS STILISTIKA WACANA TERJEMAHAN RESMI NASKAH PRASASTI PLUMPUNGAN (KAJIAN HISTORIS

    Directory of Open Access Journals (Sweden)

    Hristina Nikolic

    2008-12-01

    Full Text Available This article mainly deals with the Plumpungan manuscript discourse, an ancient stone inscription found in the Salatiga area. The manuscript dates back to the 8th century and is one of the main historical sources of the Salatiga municipality. There is a tight connection involving the above mentioned inscription with the legitimacy of the Javanese court at that time, as well as with the monarch, who was seen as half- man, half-deity. The monarch drew on the labor of his subjects in maintaining reli- gious sites to ensure his place on earth, and in heaven. The Plumpungan manuscript was a ‘legal document’ used to reassure inhabitants of the area that the monarch is the legitimate ruler, and to prevent further revolt. The monarch’s subjects in the Salatiga area at the time were farmers disheartened with high taxes and the fear of volcanic eruptions, which later caused great migrations to East Java. Consequently, the mon- arch, using the Plumpungan manuscript as a medium, decreed that the Hampra vil- lage (present-day Salatiga become a tax-free area due to the excellent care that its citizens provided for the religious sites, in addition to the obeisance shown to the monarch. It becomes clear, however, that all the way through the discourse analysis, the king wanted to ensure his legitimacy. Socio-historical context confirms that the monarch, Bhanu, was a successful ruler who held power over four regions, analogi- cally with Indra, the king of all deities. Discourse analysis is detained under three main dimensions, which is grammatical, lexical and contextual, unified from be- ginning to end in a particular style that reveals genuinely hidden meaning.     Key words: manuscript, Plumpungan, kodikologi, dan analisis stilistika.

  14. KONDISI CURAH HUJAN PADA KEJADIAN BANJIR JAKARTA DAN ANALISIS KONDISI UDARA ATAS WILAYAH JAKARTA BULAN JANUARI – FEBRUARI 2013

    OpenAIRE

    Syaifullah, M. Djazim

    2018-01-01

    IntisariKondisi curah hujan di wilayah Jakarta pada kejadian banjir besar tanggal 17 Januari 2013 telah dianalisis yang dihubungkan dengan kondisi atmosfer pada selang waktu tersebut. Data curah hujan menggunakan data TRMM sedangkan analisis kondisi atmosfer menggunakan data rawinsonde. Hasil analisis menunjukkan bahwa puncak kejadian banjir Jakarta musim hujan tahun 2013 terjadi pada tanggal 17 Januari 2013 disebabkan oleh faktor lokal yang sangat kuat ditambah dengan faktor global yang mend...

  15. A trolley mounted magazine for reactor maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Brennan, P.J.; Madani, M.; Ridgway, G.H. [GE Hitachi Nuclear Energy Canada, Peterborough, Ontario (Canada)], E-mail: patrick1.brennan@ge.com, mehdi.madani@ge.com, guy.ridgway@ge.com; Lundy, E.; Knight, D. [IM and CS (Inspection, Maintenance and Commerical Services), Ontario Power Generation, Ajax, Ontario (Canada)], E-mail: erroll.lundy@opg.com, david.knight@opg.com

    2009-03-15

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  16. A trolley mounted magazine for reactor maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Brennan, P.J.; Madani, M.; Ridgway, G.H., E-mail: patrick1.brennan@ge.com, E-mail: mehdi.madani@ge.com, E-mail: guy.ridgway@ge.com [GE Hitachi Nuclear Energy Canada, Peterborough, Ontario (Canada); Lundy, E.; Knight, D., E-mail: erroll.lundy@opg.com, E-mail: david.knight@opg.com [Ontario Power Generation, Inspection, Maintenance and Commercial Services, Ajax, Ontario (Canada)

    2008-07-01

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  17. A trolley mounted magazine for reactor maintenance

    International Nuclear Information System (INIS)

    Brennan, P.J.; Madani, M.; Ridgway, G.H.; Lundy, E.; Knight, D.

    2009-01-01

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  18. Developments in gaseous core reactor technology

    International Nuclear Information System (INIS)

    Diaz, N.J.; Dugan, E.T.

    1979-01-01

    An effort to characterize the most promising concepts for large, central-station electrical generation was done under the auspices of the Nonproliferation Alternative Systems Assessment Program (NASAP). The two leading candidates were identified from this effort: The Mixed-Flow Gaseous Core Reactor (MFGCR) and the Heterogeneous Gas Core Reactor (HGCR). Key advantages over other nuclear concepts are weighed against the disadvantages of an unproven technology and the cost-time for deployment to make a sound decision on RandD support for these promising reactor alternatives. 38 refs

  19. SOLASE: a conceptual laser fusion reactor design

    International Nuclear Information System (INIS)

    Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.

    1977-12-01

    The SOLASE conceptual laser fusion reactor has been designed to elucidate the technological problems posed by inertial confinement fusion ractors. This report contains a detailed description of all aspects of the study including the physics of pellet implosion and burn, optics and target illumination, last mirror design, laser system analysis, cavity design, pellet fabrication and delivery, vacuum system requirements, blanket design, thermal hydraulics, tritium analysis, neutronics calculations, radiation effects, stress analysis, shield design, reactor and plant building layout, maintenance procedures, and power cycle design. The reactor is designed as a 1000 MW/sub e/ unit for central station electric power generation

  20. A trolley mounted magazine for reactor maintenance

    International Nuclear Information System (INIS)

    Brennan, P.J.; Madani, M.; Ridgway, G.H.; Lundy, E.; Knight, D.

    2008-01-01

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  1. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1979-01-01

    In a nuclear reactor (e.g. one having coolant down-flow through a core to a hearth below) thermal insulation (e.g. of a floor of the hearth) comprises a layer of bricks and a layer of tiles thereon, with smaller clearances between the tiles than between the bricks but with the bricks being of reduced cross-section immediately adjacent the tiles so as to be surrounded by interconnected passages, of relatively large dimensions, constituting a continuous chamber extending behind the layer of tiles. By this arrangement, lateral coolant flow in the inter-brick clearances is much reduced. The reactor core is preferably formed of hexagonal columns, supported on diamond-shaped plates each supported on a pillar resting on one of the hearth-floor tiles. Each plate has an internal duct, four upper channels connecting the duct with coolant ducts in four core columns supported by the plate, and lower channels connecting the duct to a downwardly-open recess common to three plates, grouped to form a hexagon, at their mutually-adjacent corners. This provides mixing, and temperature-averaging, of coolant from twelve columns

  2. Reactor container

    International Nuclear Information System (INIS)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-01-01

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.)

  3. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Matheson, J.E.

    1983-01-01

    A nuclear reactor has an upper and a lower grid plate. Protrusions project from the upper grid plate. Fuel assemblies having end fittings fit between the grid plates. An arrangement is provided for accepting axial forces generated during the operation of the nuclear reactor by the flow of the cooling medium and thermal expansion and irradiation-induced growth of the fuel assembly, which comprises rods. Each fuel assembly rests on the lower grid plate and its upper end is elastically supported against the upper grid plate by the above-mentioned arrangement. The arrangement comprises four (for example) torsion springs each having a torsion tube and a torsion bar nested within the torsion tube and connected at one end thereto. The other end of the torsion bar is connected to an associated one of four lever arms. The torsion tube is rigidly connected to the other end fitting and the springs are disposed such that the lever arms are biassed against the protrusions. (author)

  5. An Analysis of the Thermal and Structure Behaviour of the UO{sub 2}-PuO{sub 2}-Fuel in the Irradiation Experiment of the UO{sub 2}-PuO{sub 2}-Fuel in the Irradiation Experiment FR2 Capsule Test Series 5a; Analisis termico y estructural del combustible UO{sub 2}-PuO{sub 2} irradiado en el reactor FR2 dentro del experimento KVE-Vg.5a

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Jimenez, J.; Helmut, E.

    1981-07-01

    In the Karlsruhe research reactor FR2 nine fuel pins were irradiated within three irradiation capsules in the course of the test series 5a. The pins contained UO{sub 2}-PuO{sub 2} fuel pellets. They reached bump values of about 6, 17 and 47 Mwd/Kg Me with linear rod powers of 400 to 600 W/cm and clad surface temperature between 500 and 700 degree centigree. A detailed analysis of the fuel structuration data (columnar-grain and equiaxed- -grain growth regions) have allowed to determine, with the help of physic-mathematical models, the radii of these regions and the heat transfer through the contact zone between fuel and clad depending on the bump. The results of the analysis showed that the fuel surface temperature rose with increasing burnup. (Author) 16 refs.

  6. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  7. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  8. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-11-01

    This single page document is the November 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the production reactor.

  9. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-01

    This single page document is the October 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  10. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-15

    This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  11. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-09-15

    This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  12. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-15

    This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  13. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-01

    This single page document is the December 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  14. Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

    Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

  15. The CEA research reactors

    International Nuclear Information System (INIS)

    Schwartz, J.P.

    1993-01-01

    Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

  16. Atomic reactor thermal engineering

    International Nuclear Information System (INIS)

    Kim, Gwang Ryong

    1983-02-01

    This book starts the introduction of atomic reactor thermal engineering including atomic reaction, chemical reaction, nuclear reaction neutron energy and soon. It explains heat transfer, heat production in the atomic reactor, heat transfer of fuel element in atomic reactor, heat transfer and flow of cooler, thermal design of atomic reactor, design of thermodynamics of atomic reactor and various. This deals with the basic knowledge of thermal engineering for atomic reactor.

  17. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

  18. Nuclear reactor core

    Energy Technology Data Exchange (ETDEWEB)

    Prescott, R F

    1974-07-11

    The core of the fast neutron reactor consisting, among other components, of fuel elements enriched in plutonium is divided into modules. Each module contains a bundle of four or six elongated components (fuel elements and control rods). In the arrangement with four components, one is kept rigid while the other three are elastically yielding inclined towards the center and lean against the rigid component. In the modules with six pieces, each component is elastically yielding inclined towards a central cavity. In this way, they form a circular arc. A control rod may be placed in the cavity. In order to counteract a relative lateral movement, the outer surfaces of the components which have hexagonal cross-sections have interlocking bearing cushions. The bearing cushions consist of keyway-type ribs or grooves with the wedges or ribs gripping in the grooves of the neighbouring components. In addition, the ribs have oblique entering surfaces.

  19. Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

    International Nuclear Information System (INIS)

    Wati, Nurokhim

    2008-01-01

    Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

  20. Fuel analysis of a PBMR; Analisis de combustible de un PBMR

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2015-09-15

    In this paper a neutronic analysis of fuel for a Pebble Bed Modular Reactor is presented, based on their composition and geometric distribution, having as main objective the use and utilization of thorium for the production of fuel for the operation of this reactor. For the study of these characteristics is necessary to use a code capable of carry out a reliable calculation of the main parameters of the fuel. Using the Monte Carlo method is suitable for simulating the neutron transport in the reactor core, which is the basis of Serpent code, with which the calculations for the analysis will be made. The results show the desirability of the use of thorium, since presents good conversion levels of fertile material to fissile, to produce U{sup 233} by neutron capture, taking as a very important factor the distribution of materials in the core, which in this work had better results based on the neutron multiplication effective factor, formed by three right circular cylinders circumscribed, making that the core has three areas constituted by a mixture of plutonium oxide in the central and external areas, and thorium oxide in the intermediate area. (Author)

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  3. Reactor container

    International Nuclear Information System (INIS)

    Furukawa, Hideyasu; Oyamada, Osamu; Uozumi, Hiroto.

    1976-01-01

    Purpose: To provide a container for a reactor provided with a pressure suppressing chamber pool which can prevent bubble vibrating load, particularly negative pressure generated at the time of starting to release exhaust from a main steam escape-safety valve from being transmitted to a lower liner plate of the container. Constitution: This arrangement is characterized in that a safety valve exhaust pool for main steam escape, in which a pressure suppressing chamber pool is separated and intercepted from pool water in the pressure suppressing chamber pool, a safety valve exhaust pipe is open into said safety valve exhaust pool, and an isolator member, which isolates the bottom liner plate in the pressure suppressing chamber pool from the pool water, is disposed on the bottom of the safety valve exhaust pool. (Nakamura, S.)

  4. 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)

  5. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  6. Nuclear reactor instrumentation power monitor

    International Nuclear Information System (INIS)

    Suzuki, Shigeru.

    1989-01-01

    The present invention concerns a nuclear reactor instrumentation power monitor that can be used in, for example, BWR type nuclear power plants. Signals from multi-channel detectors disposed on field units are converted respectively by LPRM signal circuits. Then, the converted signals are further converted by a multiplexer into digital signals and transmitted as serial data to a central monitor unit. The thus transmitted serial data are converted into parallel data in the signal processing section of the central monitor unit. Then, LPRM signals are taken out from each of channel detectors to conduct mathematical processing such as trip judgment or averaging. Accordingly, the field unit and the central monitor unit can be connected by way of only one data transmission cable thereby enabling to reduce the number of cables. Further, since the data are transmitted on digital form, it less undergoes effect of noises. (I.S.)

  7. Analisis Strategi Peningkatan Produksi Mebel di Sentra Industri Kayu

    Directory of Open Access Journals (Sweden)

    Yunida Sofiana

    2011-04-01

    Full Text Available In the latest couple years, both public and private sectors are doing some efforts and innovations to promote several arts and furniture in Indonesia; through media, cooperation program and exhibitions all over the world. However, this is not effective enough to increase furniture production to better level, especially regarding micro central industry. The micro central industry, especially wood central industry in several areas in Java, mostly has stagnant condition in both local and international. Based on the research in wood central industry in Java, there are factors as the effects: the scarcity and quality of wood material, technology dominance of limited woods, less innovation in designing, unintegrated promotion and marketing and also less strategic planning from the government to develop minor industry. This needs to be analysed according to the condition and need of minor central industry. 

  8. Modeling atmospheric dispersion for reactor accident consequence evaluation

    International Nuclear Information System (INIS)

    Alpert, D.J.; Gudiksen, P.H.; Woodard, K.

    1982-01-01

    Atmospheric dispersion models are a central part of computer codes for the evaluation of potential reactor accident consequences. A variety of ways of treating to varying degrees the many physical processes that can have an impact on the predicted consequences exists. The currently available models are reviewed and their capabilities and limitations, as applied to reactor accident consequence analyses, are discussed

  9. Analisis Perencanaan dan Penganggaran Pada Dinas Pendidikan Provinsi Jambi

    Directory of Open Access Journals (Sweden)

    Meri Darlina

    2016-06-01

    Full Text Available Abstract This research tried to investigate the analysis of consistency between planning and budgeting in education departement of Jambi Province year 2011 to 2015 which viewed by the planning and budgeting document of education in Jambi Province such as; RPJMD year 2010-2015, Renstra year 2010-2015, RKPD yaer 2011-2015, Renja year 2011-2015, PPAS year 2011-2015, RKA year 2011-2015, and DPA of APBD Education department year 2011-2015. The result of the analysis continuosly was analyzed by using Matrik of Planning and Budgeting Consolidation (MKPP for investigate level of consistency that occur and analyzed what kind of factors which caused inconsistency and what kind of effort has been done to create consistency between planning and budgeting.             The result showed level of planning and budgeting consistency between document of planning and budgeting still low. The highest consistency available in PPAS document and APBD document. The cause of inconsistency is leader policy, human resources limitedness, less coordination between sub-department and SKPD, high frequency of leader commutation and goverment’s role changing. Efforts are being made to achieve consistency between planning and budgeting is the functional improvement of human resource planning, improved coordination between field and education and the establishment of an electronic planning system (E-Planning. Keyword : Consistency, Planning, Budgeting, Education, Region Goverment   Abstrak. Penelitian ini bertujuan untuk menganalisis konsistensi antara perencanaan dan penganggaran pada Dinas Pendidikan Provinsi Jambi Tahun 2011-2015 yang dilihat dari dokumen perencanaan dan pengaggaran pendidikan di Provinsi Jambi seperti RPJMD Tahun 2010-2015, Renstra Tahun 2010-2015, RKPD Tahun 2011-2015, Renja 2011-2015, PPAS Tahun 2011-2015, RKA Tahun 2011-2015, dan DPA Dinas Pendidikan APBD Tahun 2011-2015.Hasil analisa tersebut selanjutnya di analisis dengan menggunakan Matrik

  10. Analisis Sikap Pengguna Paytren Menggunakan Technology Acceptance Model

    Directory of Open Access Journals (Sweden)

    Moh Siri

    2017-04-01

    Full Text Available Abstrak Semakin pesatnya aplikasi berbasis android mendorong masyarakat beralih dan menggunakan. Melakukan transaksi dan pembayaran ke loket-loket Paymen Point Online Bank (BPOB yang dirasa kurang membantu masyarakat dalam kegiatan transkasi. Oleh karenanya hadir sebuah layanan terknologi dibidang micropayment dengan perangkat lunak bernama PayTren yang dapat digunakan untuk pembayaran transaksi dalam jumlah kecil  (micropayment berbasis android yang merupakan salah satu alternatif tepat dan bermanfaat untuk sarana mempermudah pengguna dalam melakukan transaksi atau pembayaran serta mampu menggeser jenis pembayaran pada loket-loket pembayaran pada umumnya. Tujuan dalam penelitian ini adalah untuk menganalisis sikap pengguna aplikasi PayTren berbasis android dengan menggunakan metode Technology Acceptance Model (TAM, serta pengujian menggunakan analisis regresi. Manfaat penelitian ini adalah sebagai referensi untuk penelitian selanjutnya dengan menggunakan metode TAM dan ditambahkan variabel yang lain. Hasil dari penelitian ini persepsi kegunaan (perceived usefullness dan persepi kemudahan (perceived easy of use memiliki pengaruh yang dikategorikan kuat dan lemah terhadap (attitude toward using sikap pengguna. Kata Kunci: Aplikasi, Android, PayTren, Technology Acceptance Model.                                                                                                                             Abstract The more rapid the android-based applications are pushing the community move on and use. Transaction and payment to the counter-the counter of Paymen Point Online Bank (BPOB where less help the community in dealings. Therefore present a terknologi service in the field of micropayment with software called PayTren that can be used for payment transactions in small amounts (micropayment android-based which is one of the alternatives is right and beneficial for the means of

  11. ANALISIS HOMOGENITAS DATA CURAH HUJAN TAHUNAN KOTA MAKASSAR

    Directory of Open Access Journals (Sweden)

    Wahidah Sanusi

    2016-12-01

    Full Text Available Abstract. Homogeneity Analysis Of Annual Rainfall Data Of Makassar City. Testing the homogeneity of rainfall series is often required in climate and hydrology studies to ensure that rainfall data can be used reliability. The objective of this study is to identify homogeneity of annual rainfall data for three rainfall stations in Makassar for the period from 1985 to 2014. These stations are Paotere station, station of Biring Romang, and station of  BBMKG region IV. Four tests for homogeneity were applied for each station. These tests include the Standard Normal Homogeneity (SNH test, Buishand Range (BR test, Pettitt test and the von Neumann Ratio test. The SNH, BR, and Pettitt tests indicate that there was no break point for all station, except at Paotere station, Pettitt test shows that there was a break point in 1994. However, based on four homogeneity tests, the results reveal that rainfall series of Makassar city is homogeneous. The study results are usefull information for rainfall modeling of Makassar city.Abstrak. Analisis Homogenitas Data Curah Hujan Tahunan Kota Makassar. Pengujian homogenitas data runtun curah hujan sering diperlukan dalam kajian iklim dan hidrologi untuk menjamin kehandalan data yang digunakan. Tujuan penelitian ini adalah untuk mendeteksi kehomogenan data jumlah curah hujan tahunan di tiga stasiun hujan di kota Makassar dalam kurun waktu 1985 hingga 2014. Ketiga stasiun hujan tersebut adalah stasiun Paotere, stasiun Biring Romang, dan stasiun BBMKG wilayah IV. Ada empat uji homogenitas yang digunakan pada setiap stasiun, yaitu uji Standard Normal Homogeneity (SNH, uji Rentang Buishand (BR, uji Pettitt, dan uji Rasio von Neumann. Uji SNH, BR, dan Pettitt menunjukkan bahwa tidak terjadi perubahan jumlah curah hujan tahunan pada semua stasiun kajian, kecuali di stasiun Paotere, uji Pettitt menunjukan bahwa telah terjadi perubahan pada tahun 1994. Namun demikian, berdasarkan empat uji homogenitas tersebut menunjukkan

  12. Analisis Kesesuaian Kursi Pembatik Terhadap Kondisi Antropometri Pekerja Batik Tulis

    Directory of Open Access Journals (Sweden)

    Joni Setiawan

    2016-04-01

    Full Text Available ABSTRAKSejak diakuinya Batik sebagai warisan budaya tak benda oleh UNESCO, perkembangan industri batik mengalami perkembangan seiring dengan peningkatan permintaan pasar. Pada saat ini peralatan utama untuk membatik (kursi, gawangan, canting, kompor, meja cap, canting cap, wajan cap, dan lain-lain masih menggunakan peralatan batik yang lama, yang belum diteliti mengenai usability dan safety-nya. Tujuan dari penelitian ini adalah untuk mengkaji ukuran kursi dan gawangan pembatikan yang beredar di pasaran apakah telah sesuai dengan kebutuhan pembatik dan sesuai dengan konsep ergonomi. Pengumpulan data kursi dan gawangan dari berbagai tempat industri batik. Data yang diperlukan diwakili oleh N = 30 buah. Data-data ini kemudian dilakukan analisis statistik dengan metode histogram. Penggunaan kursi pembatikan di industri batik masih sangat jauh dari kondisi ideal (minimum tinggi 370 mm, lebar 380 mm dan kedalaman 380 mm. Ukuran tinggi kursi pembatik yang ada, rata-rata hanya berketinggian alas duduk 263,7 mm, lebar alas duduk 353 mm, kedalaman alas duduk 305 mm, dan tanpa menggunakan sandaran punggung.Kata kunci: kursi pembatikan, ergonomi, antropometriABSTRACTSince the approval of batik as an intangible cultural heritage by UNESCO, the improvement of batik industry have evolved along with the increase in market demand. At this time the main equipment for batik processes are still using the old batik equipment that has not been studied regarding its usability and safety. The purpose of this study was to assess the size of the seat and gawangan batik on the market whether in accordance with the requirements in accordance with the concept of batik and ergonomics. The data collected from several places batik industry. The data required to make is represented by N = 30 pieces. These data are then performed statistical analysis with the histogram method. The use of seat batik batik industry is still very far from ideal conditions. The size of the existing

  13. ANALISIS BANTUAN KREDIT TERHADAP PERKEMBANGAN KELOMPOK USAHA BERSAMA

    Directory of Open Access Journals (Sweden)

    Priyo Harsono

    2012-09-01

    Full Text Available The object of research is KUB Rukun Mina Barokah in Juwana, Pati. The purpose of research is to investigate the differences of KUB Rukun Mina Barokah development before and after getting the credit assistance from the Department of Marine and Fisheries, Pati in terms of capital, labor, thenumber of buyers, the total sales, and profits. The population for this research is 45 small micro enterprises. The type of data collected are primary and secondary data. The methods of data analysis are validity test, reliability test, and Wilcoxon sign rank test statistics. Based on the results of Wilcoxon sign rank test statistics which focuses on the variables of capital, labor, number of buyers, total sales and profit , it is obtained that p-value is 0.000 (0.000 <0,05. It shows that the credit assistance of the Department of Marine and Fisheries, Pati has given the changes in the joint venture group, Rukun Mina Barokah. The changes here means an increase in the variables before and after getting the credit assistance. Therefore, besides financial aid in the form of business loans, collaboration expansion is also needed to develop the business groups (KUB Objek dalam penelitian ini adalah KUB Rukun Mina Barokah di Kecamatan Juwana Kabupaten Pati. Tujuan penelitian ini untuk mengetahui perbedaan perkembangan KUB Rukun Mina Barokah sebelum dan sesudah mendapatkan bantuan kredit dari Dinas Kelautan dan Perikanan Kabupaten Pati ditinjau dari modal usaha, tenaga kerja, jumlah pembeli, total penjualan, dan keuntungan. Populasi penelitian sebanyak 45 usaha mikro kecil.Jenis datanya adalah data primer dan data sekunder.Metode analisis data meliputi uji validitas, uji reabilitas, dan uji statistic pangkat tanda wilcoxon.Berdasarkan hasil uji statistik pangkat tanda wilcoxon, baik variabel modal usaha, variabel tenaga kerja,variabel jumlah pembeli, variabel total penjualan maupun variabel keuntungan didapatkan nilai -p sebesar 0,000 (0,000 < 0,05. Hal itu

  14. Evaluasi dan Analisis Dampak Program Corporate Social Responsibility Badak LNG

    Directory of Open Access Journals (Sweden)

    Hanes Utama

    2017-08-01

    Full Text Available Program CSR Badak LNG telah melibatkan masyarakat dalam proses perencanaan, pelaksanaan, sampai pada proses monitoring dan evaluasi. Hal ini tentu berdampak pada peningkatan kualitas program serta meningkatkan peran partisipasi masyarakat sebagai kelompok sasaran penerima program CSR. Tujuan dari penelitian ini adalah mengukur tingkat kepuasan masyarakat terhadap program CSR yang telah dijalankan dan mengevaluasi dampak program CSR yang telah dilakukan. Adapun metode yang digunakan adalah  melalui pendekatan kajian input, output, outcome dan impact melalui analisis Indeks Kepuasan Masyarakat, Importance Performance Analysis, dan Compass Sustainability Analysis. Hasil penelitian menunjukkan secara keseluruhan kepuasan masyarakat terhadap pelayanan program CSR Badak LNG menunjukkan parameter sangat baik. Tingkat kesesuaian antara kepuasan kinerja dengan tingkat kepentingan masyarakat masuk dalam kategori sangat baik. Indikator kejelasan petugas pendamping,  tanggung jawab petugas pendamping, kemampuan petugas pendamping,  kesopanan petugas pendamping, dan kepastian biaya pelayanan adalah indikator yang memiliki harapan tinggi dari masyarakat penerima manfaat, dan perusahaan memiliki kinerja yang sangat baik dalam hal tersebut. Dampak positif yang diterima dari  kegiatan CSR pada dimensi nature, wellbeing, economy, social di Kota Bontang sangat tinggi, di antaranya terjadinya peningkatan kualitas lingkungan, pemanfaatan potensi alam, peningkatan pendapatan masyarakat, pengentasan kemiskinan, peningkatan kemandirian UMKM, semakin dikenalnya kebudayaan masyarakat, dan tingginya tingkat kepuasan masyarakat terhadap kegiatan-kegiatan CSR Badak LNG. The CSR program from Badak LNG has been involving the society in the planning, implementation, monitoring and evaluation process. It has an impact to the improvement quality program and increase peoples participation as a CSR awardee. This research aims to measure the peoples satisfactory towards CSR

  15. ANALISIS FAKTOR-FAKTOR YANG MEMPENGARUHI IMPOR KAPAS DI INDONESIA

    Directory of Open Access Journals (Sweden)

    Ari Budi Basuki

    2017-06-01

    Full Text Available Penelitian ini bertujuan untuk menganalisis pengaruh produksi kapas domestik, konsumsi kapas, GDP riil dan kurs rupiah ke dollar AS terhadap impor kapas. Jenis penelitian ini adalah penelitian kuantitatif dengan data time series berdasarkan tahun 1980-2013. Data diperoleh dari Indexmundi, International Monetary Fund dan United Nations Conference on Trade and Development (UNSCAD. Hasil analisis Error Correction Model (ECM menunjukkan bahwa variabel produksi kapas domestik dalam jangka pendek dan jangka panjang tidak berpengaruh terhadap impor kapas, variabel konsumsi kapas dalam jangka pendek dan jangka panjang berpengaruh positif terhadap impor kapas, variabel GDP riil dalam jangka pendek dan jangka panjang tidak berpengaruh terhadap impor kapas, dan variabel kurs rupiah terhadap dollar dalam jangka pendek dan jangka panjang tidak berpengaruh terhadap impor kapas. Kesimpulan dari penelitian ini adalah faktor produksi kapas, GDP riil dan kurs dalam jangka pendek dan jangka panjang tidak berpengaruh terhadap impor kapas, namun dalam jangka pendek dan jangka panjang faktor konsumsi kapas mempengaruhi impor kapas. Saran yang berkaitan dengan hasil penelitian ini adalah Pemerintah perlu meningkatkan total produksi kapas dalam negeri dengan cara mengembangkan penelitian dan pembenihan kapas dalam negeri termasuk jenis transgenic. Pemerintah perlu mengurangi penggunaan kapas terutama dengan cara mensubtitusi kapas tersebut dengan kapas sintetis This study aimed to analyze the influence of domestic cotton production, cotton consumption, real GDP and the exchange rate rupiah to the US dollar against the import of cotton. This research is a quantitative study with time series data based on years of 1980-2013. Data obtained from Indexmundi, International Monetary Fund and the United Nations Conference on Trade and Development (UNSCAD. Results of analysis Error Correction Model (ECM shows that domestic cotton production variables in the short term and the

  16. Evaluasi Konsumen di "RM. Pak Kardi" Pemalang dengan Analisis Diskriminan

    Directory of Open Access Journals (Sweden)

    Tuis Susanto

    2017-02-01

    Full Text Available Penelitian ini bertujuan mengetahui apakah ada perbedaan yang siqnifikan dalam variabel dependen (Y yang meliputi konsumen sering Beli (YO, Cukup (Y I dan Jarang Beli (Y2, serta bertujuan mengetahui perilaku konsumen yang benar-benar berbeda, perbedaan dalam  arti perilaku   mereka  sering  membeli, cukup dan jarang membeli. Metode analisis  yang digunakan adalah dengan Wilk's Lambda, Pairwise, F test. Canonical  corellation,   untuk  mencari ada dan tidak perbedaan antar group variabel dependen dan  menginterpretasikan     berdasarkan function at group centroid untuk mengetahui variabel independen mana yang   menjadi  faktor diskriminannya. Hasil yang didapat dari penelitian ini adalah  bahwa  variabel  menu  merupakan faktor pembeda (diskriminan.  Artinya konsumen grup (sering  beli,  cukup  dan jarang   beli  tidak terpengaruh   dengan  usia,  harga,  pendapatan,   dan pelayanan  yang  diberikan oleh RM. Pak Kardi ditunjukkan dengan tanda (+ padafunction I. Jadi  konsumen  yang  membeli  di RM. Pak  Kardi adalah  mereka  yang  benar-benar   menyukai menu  (masakan  khas kepiting RM. Pak Kardi.  Jarak antara  grup  Sering  Beli  dengan grup  Jarang   Beli  adalah yang  terbesar, yakni 7,350. Sedangkan jarak   terkecil   adalah antara grup  Cukup  dengan  grup  Jarang   Beli  (0.522. Dengan demikian dapat  dikatakan   bahwa  Konsumen   di grup  Sering  Beli paling berbeda  selera  Menu  masakannya. Sebaliknya   Menu yang  disukai  oleh  konsumen di RM. Pak Kardi yang termasuk konsumen Cukup mempunyai perbedaan yang  kecil dengan  mereka  yang jarang membeli

  17. ANALISIS KANDUNGAN GARAM GUNUNG ASAL KRAYAN KABUPATEN NUNUKAN KALIMANTAN TIMUR

    Directory of Open Access Journals (Sweden)

    Herman Herman

    2012-06-01

    Full Text Available Has been studied composition of mountain salt from Krayan, Nunukan, East Kalimantan. This study aims to determine the composition of the minerals contained in the  mountain salt. Mountain salt is obtained from wells Krayan District residents were further prepared for analysis using a technique using Atomic Absorption Spectrometer (AAS, further by looking at the pattern of X-ray Diffraction (XRD and Scanning electron microscopic (SEM. Based on the results obtained AAS has identified mineral deposits include: Na, K, Mg, Al, Cu, Zn, Fe, Ba, and Sr. From the results of XRD shows that the main peak of the salt Krayan shows major peaks for NaCl crystals with impurities such as KCl, CaCl2, MgCl2, and AlCl3. SEM observation showed that morphology of Krayan salt have cube shape which is the shape of NaCl crystals with space group Fm3m and lattice parameter (a 5.620 Å Keywords : Mountain Salt, krayan, AAS, XRD, SEM   Abstrak Telah dilakukan penelitian analisis kandungan garam gunung asal Krayan Kabupaten Nunukan Kalimantan Timur. Penelitian ini bertujuan untuk mengetahui komposisi mineral yang terkandung dalam garam gunung. Garam gunung diperoleh dari sumur warga Kecamatan Krayan yang selanjutnya dipreparasi untuk dianalisis dengan menggunakan menggunakan teknik Spektrometer Serapan Atom (SSA, selanjutnya dengan melihat pola Difraksi Sinar X (XRD, dan Scanning Elektron Microscopy (SEM. Berdasarkan hasil SSA telah diidentifikasi diperoleh kandungan mineral antara lain: Na, K, Mg, Al, Cu,  Zn, Fe, Ba, dan Sr. Dari hasil XRD terlihat bahwa puncak utama dari  garam krayan tersebut menunjukkan puncak utama untuk Kristal NaCl, dengan impurities antara lain KCl, CaCl2, MgCl2, dan AlCl3. Selain itu hal ini didukung pula oleh pengamatan SEM, bahwa morfologi SEM garam krayan memperlihatkan bentuk kristal kubus yang merupakan  bentuk dari  Kristal NaCl  dengan  grup ruang  Fm3m  dengan panjang  kisi kristal 5,620 Å. Kata Kunci : Garam Gunung, Krayan

  18. ANALISIS KELAYAKAN INVESTASI PENAMBAHAN MESIN FRAIS BARU PADA CV. XYZ

    Directory of Open Access Journals (Sweden)

    Febri Muhammad Rachadian

    2013-04-01

    Full Text Available Perkembangan teknologi sangat pesat sehingga dunia perindustrian harus mengikuti perkembangannya. Penerapan teknologi diharapkan dapat meningkatkan proses produksi sehingga dapat menghasilkan produk yang berkualitas. Pada industri pembuatan mesin cetak di CV XYZ, mesin-mesin yang digunakan telah hampir lebih dari 20 tahun. Ada indikasi bahwa mesin-mesin tersebut sudah lewat umur pakainya. Alternatif yang digunakan selama ini ialah penggantian komponen yang rusak. Peneliti ingin membandingkan alternative tersebut dengan  penambahan mesin frais baru. Untuk itu diperlukan analisis kelayakan investasi penambahan mesin baru. Dalam perkiraan kurun waktu 10 tahun dan suku bunganya 15 % dengan menggunakan NPV, penambahan mesin frais menarik sebesar Rp 461.201.000 dibandingkan penggantian komponen yang rusak sebesar Rp 211.227.000. Sebaliknya pada PBP, penggantian komponen yang rusak masih mengungguli dengan 1 tahun 4 bulan dibandingkan penambahan mesin frais baru selama 2 tahun 1 bulan. Begitupun juga PI penggantian komponen yang rusak masih menarik sebesar 4,2 dibandingkan PI penambahan mesin frais baru sebesar 2,56. Dapat disimpulkan bahwa dalam jangka waktu 10 tahun, alternatif penggantian komponen yang rusak masih lebih baik dibandingkan penambahan mesin frais baru. Namun, untuk investasi jangka panjang, mungkin saja alternatif penambahan mesin frais baru lebih menarik. Kata Kunci: penggantian komponen rusak, mesin frais baru, mesin cetak Abstract The rapid development of technology makes the world of industry must follow its development. Application of technology is expected to improve the production process so it can be produce a quality product. On the industrial manufacture of printing machines in CV XYZ, the machines have been used almost more than 20 years. There are indications that those machines passed the age lifetime. The alternatives that have been used during this time are the replacement of defective parts. Researchers wanted to

  19. Simulation of a hypothetical liquid relief valve failure (open) at Embalse nuclear power plant when a reactor shutdown is considered; Simulacion de la evolucion de la CNE (central nuclear Embalse) en el caso hipotetico de la apertura espuria de una valvula de alivio liquido con disparo del reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bedrossian, G; Gersberg, S [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Reactores y Centrales Nucleares

    1997-12-31

    The study of the spurious opening of the liquid relief valves is of great interest in CANDU nuclear power plants because this could lead to a loss of coolant through the degasser-condenser relief valves, and implies an undesirable intermittent opening/closure of them. In fact, there is a specific procedure to follow at Embalse nuclear power plant whenever this abnormal situation occurs. This procedure contains a section where a reactor trip is considered. Really, automatic reactor trip is not accepted to occur. No trip parameters set points are through to be reached (neutronic or process). However, the procedure considers the situation where the reactor does trip. We analyzed the plant behavior when a reactor shutdown is triggered. Our objective was to assess if after this trip, the procedure can lead the plant to a safe situation, preventing high pressures in the degasser-condenser and with the inventory recovered in the storage tank. The case was analyzed with Firebird III, Mod. 1.0 code. Two situations were considered: trip at 40 sec. and trip at 180 sec. after the liquid relief valve failed opened (the latter when the degasser-condenser fills up). Procedure analysis and code simulations showed that following the steps recommended, provided the liquid relief valve can be closed manually, the inventory that enters the degasser-condenser from the heat transport primary system through the failed valve could be recovered in the storage tank, leading the plant to shutdown in safe conditions, and preventing the degasser-condenser relief valves setpoint from being reached. (author). 3 refs., 10 figs.

  20. FBR type reactor

    International Nuclear Information System (INIS)

    Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

    1994-01-01

    In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

  1. The prototype fast reactor

    International Nuclear Information System (INIS)

    Broomfield, A.M.

    1985-01-01

    The paper concerns the Prototype Fast Reactor (PFR), which is a liquid metal cooled fast reactor power station, situated at Dounreay, Scotland. The principal design features of a Fast Reactor and the PFR are given, along with key points of operating history, and health and safety features. The role of the PFR in the development programme for commercial reactors is discussed. (U.K.)

  2. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  3. NCSU Reactor Sharing Program

    International Nuclear Information System (INIS)

    Perez, P.B.

    1993-01-01

    The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities

  4. Reactor safety method

    International Nuclear Information System (INIS)

    Vachon, L.J.

    1980-01-01

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

  5. Utilization of nuclear research reactors

    International Nuclear Information System (INIS)

    1980-01-01

    prior to the beginning of the course was of particular value. Interesting scientific visits and demonstrations at the Isotope Institute and at the Central Research Institute for Physics (IFKI), both of the Hungarian Academy of Sciences, were also arranged. During the Study Tour at the Central Institute for Nuclear Research in Rossendorf near Dresden, German Democratic Republic, the participants had the opportunity to observe the organization of a 10 MW nuclear reactor where radioisotopes and radiopharmaceuticals are produced on a commercial scale. Lectures were delivered by local scientists on some of their programmes in applied research in solid state physics and material sciences. At the Technical University of Dresden, the group visited the homogeneous solid-moderated zero-power training reactor (AKR), primarily dedicated to nuclear education and training. Studies on different theoretical and experimental aspects of radiation protection (solid state nuclear track and thermoluminescent detectors) are also being carried out. The last day of the Study Tour was devoted to a visit to the College for Advanced Technology at Zittau, where a training reactor with a power of a few watts has been recently installed. (author)

  6. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

    This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

  7. 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

  8. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  9. Preliminary design of a tandem mirror reactor

    International Nuclear Information System (INIS)

    Strohmayer, J.N.

    1984-04-01

    The purpose of this thesis is to examine the TARA mirror experiment as a possible tandem mirror reactor configuration. This is a preliminary study to size the coil structure based on using the smallest end cell axial length that physics and engineering allow, zeroing the central cell parallel currents and having interchange stability. The input powers are estimated for the final reactor design so a Q value may be estimated. The Q value is defined as the fusion power divided by the total injected power absorbed by the plasma. A computer study was performed on the effect of the transition size, the transition vertical spacing and transition current. These parameters affect the central cell parallel currents, the recircularization of the flux tube and the ratio of central cell beta to anchor beta needed for marginal stability. Two designs were identified. The first uses 100 keV and 13 keV neutral beams to pump the ions that trap in the thermal barrier. The Q value of this reactor is 11.3. The second reactor uses a pump beam at 40 keV. This energy is chosen because there is a resonance for the charge exchange cross section between D 0 and He 2+ at this energy, thus the alpha ash will be pumped along with the deuterium and tritium. The Q value of this reactor is 11.6

  10. Central Chile

    Science.gov (United States)

    2002-01-01

    The beginning of spring in central Chile looked like this to SeaWiFS. The snow-covered Andes mark the country's eastern border, and phytoplankton blooms and river sediment plumes fill the waters off its west coast. A large eddy due west of Concepcion is highlighted by the phytoplankton it contains.

  11. Afrique Centrale

    African Journals Online (AJOL)

    PR BOKO

    (Afrique Centrale) : peuplement de protozoaires ciliés et macro invertébrés ... Le lac d'Obili est un écosystème aquatique situé en plein cœur de Yaoundé en ...... électrique des eaux est assez stable, autour de 200 ; ce qui suppose que la ...

  12. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Yasutomi, Yoshiyuki; Nakagawa, Moroo; Sawai, Yuichi; Chiba, Akio; Suzuki, Yasutaka.

    1997-01-01

    Silicon composited with reinforcing metals is used for a divertor cooling substrate having an effect as a cooling tube to provide a silicon base composite material having increased electric resistance and toughness. The blending ratio of reinforcing materials in the form of granules, whiskers or long fibers is controlled in order to control heat conductivity, electric resistivity and mechanical performances. The divertor cooling substrate comprising the silicon base composite material is integrated with a plasma facing material. The production method therefor includes ordinary metal matrix composite forming methods such as powder metallurgy, melting penetration method, high pressure solidification casting method, centrifugal casting method and vacuum casting method. Since the cooling plate is constituted with the light metal and highly electric resistant metal base composite material, sharing force due to eddy current can be reduced, and radiation exposure can be minimized. Accordingly, a cooling structure for a thermonuclear reactor effective for the improvement of environmental problems caused by waste disposal can be attained. (N.H.)

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  14. Nuclear reactors

    International Nuclear Information System (INIS)

    Pearson, K.G.

    1977-01-01

    Reference is made to auxiliary means of cooling the nuclear fuel clusters used in light or heavy water cooled nuclear reactors. One method is to provide one or more spray cooling tubes. From holes in the side walls of those tubes coolant water may be sprayed laterally into the cluster against the rods. The flow of main coolant may thus be supplemented or even replaced by the auxiliary coolant. A difficulty, however, is that only those fuel rods close to a spray cooling tube can readily be reached by the auxiliary coolant. In the arrangement described, where the fuel rods are spaced apart by transverse grids, at least one of the interspaces between the grids is provided with an axially extending auxiliary coolant conduit having lateral holes through which an auxiliary coolant is sprayed into the cluster. A deflector is provided that extends from a transverse grid into a position in front of the holes and deflects auxiliary coolant on to parts of the fuel rods otherwise inaccessible to the auxiliary coolant. The construction of the deflector is described. (U.K.)

  15. Improvements in streaking nuclear reactors

    International Nuclear Information System (INIS)

    Pedrick, A.P.

    1976-01-01

    In this type of reactor atomic nuclei are stripped of their electron shells by heating to form a very high temperature plasma which is passed at high speed through a chamber in which they are forced into contact with a 'wall' formed by a unidirectional stream of photons from continuous laser beams. In this way it should be possible to brush off from the surface of the nuclei protons and neutrons, with release of their binding energy. The energy thus produced can be subjected to much more gentle control than with a fission or fusion reactor. Furthermore, if this concept can be successfully applied to elements of high atomic number which are normally regarded as stable and unfissionable, a vast new source of nuclear energy release will have been made available. It also seems possible that an atomic nucleus might be spun sufficiently in such a reactor to disintegrate it completely into nucleons by simple centrifugal action, with great release of binding energy. The reactor described has a central body with radial ducts through which the nuclei are passed, and a number of lasers are provided whose beams are arranged so that the nuclei are discharged at the cross-over point of two or more laser beams which form a corner at the junction of two or more photon walls. (U.K.)

  16. Pressurized water reactor inspection procedures

    International Nuclear Information System (INIS)

    Heinrich, D.; Mueller, G.; Otte, H.J.; Roth, W.

    1998-01-01

    Inspections of the reactor pressure vessels of pressurized water reactors (PWR) so far used to be carried out with different central mast manipulators. For technical reasons, parallel inspections of two manipulators alongside work on the refueling cavity, so as to reduce the time spent on the critical path in a revision outage, are not possible. Efforts made to minimize the inspection time required with one manipulator have been successful, but their effects are limited. Major reductions in inspection time can be achieved only if inspections are run with two manipulators in parallel. The decentralized manipulator built by GEC Alsthom Energie and so far emmployed in boiling water reactors in the USA, Spain, Switzerland and Japan allows two systems to be used in parallel, thus reducing the time required for standard inspection of a pressure vessel from some six days to three days. These savings of approximately three days are made possible without any compromises in terms of positioning by rail-bound systems. During inspection, the reactor refueling cavity is available for other revision work without any restrictions. The manipulator can be used equally well for inspecting standard PWR, PWR with a thermal shield, for inspecting the land between in-core instrumentation nozzles, BWR with and without jet pumps (complementary inspection), and for inspecting core support shrouds. (orig.) [de

  17. MIT pebble bed reactor project

    Energy Technology Data Exchange (ETDEWEB)

    Kadak, Andrew C. [Massachusetts Institute of Technology, Cambridge (United States)

    2007-03-15

    The conceptual design of the MIT modular pebble bed reactor is described. This reactor plant is a 250 Mwth, 120 Mwe indirect cycle plant that is designed to be deployed in the near term using demonstrated helium system components. The primary system is a conventional pebble bed reactor with a dynamic central column with an outlet temperature of 900 C providing helium to an intermediate helium to helium heat exchanger (IHX). The outlet of the IHX is input to a three shaft horizontal Brayton Cycle power conversion system. The design constraint used in sizing the plant is based on a factory modularity principle which allows the plant to be assembled 'Lego' style instead of constructed piece by piece. This principle employs space frames which contain the power conversion system that permits the Lego-like modules to be shipped by truck or train to sites. This paper also describes the research that has been conducted at MIT since 1998 on fuel modeling, silver leakage from coated fuel particles, dynamic simulation, MCNP reactor physics modeling and air ingress analysis.

  18. MIT pebble bed reactor project

    International Nuclear Information System (INIS)

    Kadak, Andrew C.

    2007-01-01

    The conceptual design of the MIT modular pebble bed reactor is described. This reactor plant is a 250 Mwth, 120 Mwe indirect cycle plant that is designed to be deployed in the near term using demonstrated helium system components. The primary system is a conventional pebble bed reactor with a dynamic central column with an outlet temperature of 900 C providing helium to an intermediate helium to helium heat exchanger (IHX). The outlet of the IHX is input to a three shaft horizontal Brayton Cycle power conversion system. The design constraint used in sizing the plant is based on a factory modularity principle which allows the plant to be assembled 'Lego' style instead of constructed piece by piece. This principle employs space frames which contain the power conversion system that permits the Lego-like modules to be shipped by truck or train to sites. This paper also describes the research that has been conducted at MIT since 1998 on fuel modeling, silver leakage from coated fuel particles, dynamic simulation, MCNP reactor physics modeling and air ingress analysis

  19. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

    A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

  20. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

    The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

  1. Text Mining Untuk Analisis Sentimen Review Film Menggunakan Algoritma K-Means

    Directory of Open Access Journals (Sweden)

    Setyo Budi

    2017-02-01

    Full Text Available Kemudahan manusia didalam menggunakan website mengakibatkan bertambahnya dokumen teks yang berupa pendapat dan informasi. Dalam waktu yang lama dokumen teks akan bertambah besar. Text mining merupakan salah satu teknik yang digunakan untuk menggali kumpulan dokumen text sehingga dapat diambil intisarinya. Ada beberapa algoritma yang di gunakan untuk penggalian dokumen untuk analisis sentimen, salah satunya adalah K-Means. Didalam penelitian ini algoritma yang digunakan adalah K-Means. Hasil penelitian menunjukkan bahwa akurasi K-Means dengan dataset digunakan 300 positif dan 300 negatif  akurasinya 57.83%,  700 dokumen positif dan 700  negatif akurasinya 56.71%%, 1000 dokumen positif dan 1000  negatif akurasinya 50.40%%. Dari hasil pengujian disimpulkan bahwa semakin besar dataset yang digunakan semakin rendah akurasi K-Means.   Kata Kunci : Text Mining, Analisis Sentimen, K-Means, Review Film 

  2. Deteksi Kerusakan Batang Rotor Pada Motor Induksi Menggunakan Analisis Arus Mula Berbasis Hilbert Transform

    Directory of Open Access Journals (Sweden)

    Isti Qomah

    2017-01-01

    Full Text Available Kerusakan batang rotor merupakan salah satu jenis kerusakan pada motor induksi yang dapat menyebabkan masalah serius. Kerusakan tersebut dapat mencapai 5% - 10% dari seluruh kasus gangguan motor induksi. Oleh karena itu, perlu adanya diagnosis awal yang mendeteksi adanya gangguan pada rotor motor induksi, agar dapat dilakukan perbaikan lebih cepat dan tanggap sebelum terjadi gangguan yang lebih besar. Tugas Akhir ini membahas terkait teknik deteksi kerusakan batang rotor pada motor induksi dengan menggunakan analisis arus mula. Sistem yang digunakan berbasis  decomposition wavelet transform terlebih dahulu kemudian dilanjutkan dengan analisis berbasis hilbert transform sebagai perangkat pengolahan sinyal sehingga mampu mendeteksi motor dalam keadaan sehat atau mengalami kerusakan. Pengujian sistem dilakukan dalam beberapa kondisi, yaitu kondisi tanpa beban dan berbeban. Selain itu, kondisi yang diberikan adalah kecacatan mulai dai 1BRB hingga 3BRB. Hasil pengujian membuktikan bahwa decomposition wavelet transform dan Hilbert transform mampu mendeteksi perbedaan kondisi pada motor induksi normal ataupun rusak pada batang rotor.

  3. Analisis Nilai Perusahaan pada Implementasi Program Kepemilikan Saham pada Karyawan/Manajemen

    Directory of Open Access Journals (Sweden)

    Dwitya Aribawa

    2016-12-01

      Penelitian ini bertujuan menganalisis economic value added (EVA sebelum dan sesudah implementasi program kepemilikan saham pada karyawan/ manajemen dengan objek penelitian ini adalah perusahaan publik yang menggunakan kebijakan ESOP/MSOP sebagai sarana benefit/incentive berupa pembagian sebagian saham untuk karyawan/ manajemen. Variabel yang digunakan sebagai indikator nilai perusahaan adalah EVA. Nilai EVA dianggap sebagai indikator yang kompleks dan mempertimbangkan faktor resiko (beta dari perusahaan. Perusahaan yang dianalisis adalah perusahaan yang listing di Bursa Efek Indonesia. Terdapat 17 perusahaan yang layak untuk dilakukan analisis berdasarkan kriteria yang ditentukan peneliti. Pengumpulan dan data dianalisis secara pooling, hal ini melihat dari tidak dibedakannya perusahaan berdasarkan industri (multi industri. Paired sample test digunakan untuk menguji hipotesis pada penelitian dan sebelumnya dilakukan uji normalitas data. Hasil analisis bahwa hasil perbandingan rata-rata EVA sebelum dan sesudah implementasi program kepemilikan saham pada karyawan/manajemen terdapat perbedaan yag signifikan.

  4. Communication system and spectral analysis for Ge-Li and GeHp detectors; Sistema de comunicaciones y analisis de espectros para detectores Ge-Li y GeHp

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, J; Castano, P; Bonino, A D; Righetti, M A

    1991-12-31

    An integral communication and spectral analysis system (SICADE) was developed and implemented to satisfy the need to optimize and automate the measurement system used in Atucha I nuclear power plant for the activity in the primary loop`s water extracted by the TV system. The importance of these measurements is based on the fact that from the spectrometric analysis of the samples extracted, the Iodines-GN and Iodines-Iodines relations, which allow to detect the presence of deficient fuel elements, are calculated. The system developed is based on two modules integrated in a unique set commanded by the operators through the screen dialogue. (Author). [Espanol] Dada la necesidad de optimizar y automatizar el sistema de medicion utilizado en la Central Nuclear Atucha I para la actividad en el agua del circuito primario extraida a traves del sistema TV se desarrollo e implemento un sistema integral de Comunicacion y Analisis de espectros (SICADE). La importancia de estas mediciones radica en el hecho que del analisis espectrometrico de las muestras extraidas se calculan las relaciones entre Iodos-GN e Iodos-Iodos que permiten detectar la presencia de elementos combustibles fallados. El sistema desarrollado esta basado en dos modulos integrados en un unico conjunto comandado por el operador a traves del dialogo por pantalla. (Autor).

  5. ANALISIS STRUKTUR AKTANSIAL DAN FUNGSIONAL DALAM VOYAGE AUCENTREDELA TERRE KARYA JULES VERNE

    OpenAIRE

    Ade Yolanda Latjuba, Dr. M.A

    2017-01-01

    Berdasarkan hasil analisis, maka dapat disimpulkan sebagai berikut: 1. Roman Voyage au centre de la terre menceritakan tentang Prof. Lidenbrock, Axel, dan Hans Bjelke melakukan perjalanan luar biasa menuju pusat bumi berdasarkan petunjuk dari Ame Saknussemm yang Axel dan si Professor dapatkan secara tidak sengaja terselip di dalam sebuah buku tua karya Snorre Tarlesson. 2. Prof. Lidenbrock, Axel dan Hans Bjelke memulai perjalanan mereka menuju pusat bumi dengan cara menuruni gunung bera...

  6. Analisis Pengaruh Konsentrasi Gas LPG Menggunakan Sensor TGS 2610 Berbasis Mikrokontroler AVR ATMega8535

    OpenAIRE

    Nurhalimah

    2011-01-01

    Telah dilakukan analisis kuantitatif gas dalam LPG. Penelitian ini dilakukan untuk mengukur konsentrasi gas LPG terhadap sensor. Metoda yang digunakan untuk mengukur konsentrasi gas LPG yaitu sensor gas semikonduktor jenis TGS 2610 keluaran Figaro yang digunakan untuk mendeteksi keberadaan gas. Sementara yang menjadi pusat pengendalian dari seluruh alat yang dirancang digunakan mikrokontroler AVR ATMega8535. Selain itu sistem yang dirancang dilengkapi LCD sebagai tampilan nilai konsentrasi ga...

  7. ANALISIS SEGMENTASI PASAR PRODUK YOGHURT BERDASARKAN PERILAKU KONSUMEN PADA HYPERMART CABANG PANAKUKANG, MAKASSAR

    OpenAIRE

    -, ANDRIANI

    2014-01-01

    2014 v ABSTRAK Andriani. I311 04 049. Analisis Segmentasi Pasar Berdasarkan Perilaku Konsumen pada Hypermart Cabang Panakukang, Makassar. Dibawah Bimbingan Ir. Hastang, M.Si sebagai Pembimbing Utama dan Muh. Ridwan, S.Pt, M.Si. sebagai Pembimbing Anggota. Perkembangan dan peningkatan bisnis khususnya pada usaha peternakan akhir-akhir ini menunjukkan banyak peningkatan. Salah satu strategi yang dapat diterapkan dalam menunjang aktivitas pemasaran oleh perusahaan dalam memasarkan pr...

  8. ANALISIS STRUKTUR MIKRO LAPISAN BOND COAT NIAL THERMAL BARRIER COATING (TBC PADA PADUAN LOGAM BERBASIS CO

    Directory of Open Access Journals (Sweden)

    Toto Sudiro

    2012-11-01

    Full Text Available Kehandalan dan umur pakai sistem Thermal Barrier Coating (TBC ditentukan oleh kestabilan lapisan bond coat dan thermal grown oxide (TGO. Sehingga sangatlah penting untuk memahami mekanisme pembentukan dan degradasi lapisan ini. Pada makalah ini akan dibahas analisis struktur mikro lapisan bond coat NiAl yang dideposisikan pada substrat CoCrNi dengan menggunakan gabungan metoda electroplating dan pack-cementation. Pada makalah ini juga dibahas mekanisme pembentukan void disepanjang interface bond coat¬-substrat setelah tes oksidasi.

  9. Analisis Algoritma Pergantian Cache Pada Proxy Web Server Internet Dengan Simulasi

    OpenAIRE

    Nurwarsito, Heru

    2007-01-01

    Pertumbuhan jumlah client internet dari waktu ke waktu terus bertambah, maka respon akses internet menjadi semakin lambat. Untuk membantu kecepatan akses tersebut maka diperlukan cache pada Proxy Server. Penelitian ini bertujuan untuk menganalisis performansi Proxy Server pada Jaringan Internet terhadap penggunaan algoritma pergantian cache-nya.Analisis Algoritma Pergantian Cache Pada Proxy Server didesain dengan metoda pemodelan simulasi jaringan internet yang terdiri dari Web server, Proxy ...

  10. Analisis Peranan Franchisor Terhadap Suksesnya Bisnis Franchise Pada Mc. Donald’s Cabang Ring Road Medan

    OpenAIRE

    Simarmata, Leonardo

    2012-01-01

    Tujuan penelitian ini adalah untuk mengetahui dan menganalisis peranan franchisor dalam promotion, support service, training, control system dan communication terhadap suksesnya bisnis franchise pada Mc Donald’s Cabang Ring Road Medan. Pengumpulan data primer diperoleh dengan cara memberikan daftar pertanyaan (questionaire) dan melakukan wawancara (interview) secara mendalam (depth interview) kepada pemilik usaha M. Donald’s Cabang Ring Road Medan. Teknik analisis data penelitian ini ad...

  11. Analisis Kelembagaan Rantai Pasok Telur Ayam Ras Peternakan Rakyat Di Jawa Barat

    OpenAIRE

    Sejati, Wahyuning K

    2011-01-01

    Dalam konteks pengembangan pasar komoditas dan peningkatan kesejahteraan peternak rakyat perlu dipahami secara baik karakteristik dan kelembagaan petani, pemasok, dan pasar. Tulisan ini bertujuan untuk menganalisis kelembagaan rantai pasok peternak-pemasok-pasar komoditas telur ayam ras yang meliputi: (1) identifikasi kelembagaan peternakan rakyat ayam ras petelur; (2) analisis kelembagaan rantai pasok komoditas telur; dan (3) antisipasi kelembagaan introduksi rantai pasok telur ayam ras pete...

  12. ANALISIS PERILAKU PENYUSUN ANGGARAN DALAM PERSPEKTIF KEAGENAN PADA KABUPATEN DAN KOTA DI PROVINSI SULAWESI SELATAN

    OpenAIRE

    ILMI, A. NURUL

    2016-01-01

    2016 Analisis Perilaku Penyusun Anggaran dalam Perspektif Keagenan pada Kabupaten dan Kota di Provinsi Sulawesi Selatan Analysis of Budget Compiler???s Behavior within the Agency Perspective in Regency and City of South Sulawesi Province A. Nurul Ilmi Mediaty Aini Indrijawati Penelitian ini bertujuan untuk menganalisis pengaruh perubahan Pendapatan Asli Daerah dan perubahan Dana Perimbangan terhadap perilaku oportunistik penyusun anggaran yang menjelaskan mengenai hubungan k...

  13. Correlacion entre metodos de analisis de Zn disponible en cuatro ordenes de suelos de Costa Rica

    OpenAIRE

    Eloy Molina; Elemer Bornemisza

    2001-01-01

    Se realizo una comparación entre métodos analisis del Zn disponible en 4 ordenes de sue- Analytilos de Costa Rica (Ultisoles, Vertisoles, Andisoles Inceptisoles, 25 de c/u), utilizando las siguientes soluciones extractoras: Olsen Modificado, Meh- lich 3, Morgan Modificado, DTPA y HC1. Las cantidades de Zn extrafdas dependieron de la natu- raleza qufmica de la solucion extractora. El HCl presento los contenidos mas altos de Zn en los chasuelos, excepto en Vertisoles....

  14. Analisi Pengaruh Store Name, Brand Name, Dan Price Discounts Terhadap Purchase Intentions Konsumen Infinite Tunjungan Plaza

    OpenAIRE

    Gunawan, Andy

    2013-01-01

    Andy Gunawan:SkripsiAnalisis pengaruh store name, brand name dan price discounts terhadap purchase intention konsumen infnite tunjungan plaza Di era globalisasi ini, persaingan dagang antara Perusahaan – Perusahaan baik lokal maupun global menjadi semakin ketat, oleh karena itu Perusahaan selalu berusaha untuk meningkatkan ketertarikan minat beli konsumen. Beberapa variabel yang menjadi fokus Perusahaan adalah store name, brand name, dan price discount. Tujuan penelitian ini adalah untuk meng...

  15. KERAGAAN WARNA IKAN CLOWN BIAK (Amphiprion percula) POPULASI ALAM DAN BUDIDAYA BERDASARKAN ANALISIS GAMBAR DIGITAL

    OpenAIRE

    Ruby Vidia Kusumah; Sawung Cindelaras; Anjang Bangun Prasetio

    2015-01-01

    Penelitian ini bertujuan untuk mengkaji keragaan warna ikan clown Biak (Amphiprion percula) populasi alam dan budidaya berdasarkan analisis gambar digital sebagai dasar upaya pemuliaannya. Gambar digital diambil dari koleksi ikan clown Biak Balai Besar Perikanan Budidaya Laut Lampung, Balai Besar Penelitian dan Pengembangan Budidaya Laut Gondol, Bali; serta pengumpul ikan hias di Denpasar, Bali menggunakan kamera digital Canon EOS 600D. Pola warna dikarakterisasi secara visual terhadap varias...

  16. ANALISIS RESIDU PESTISIDA PIRETRIN DALAM TOMAT DAN SELADA DARI BEBERAPA PASAR DI JAKARTA

    Directory of Open Access Journals (Sweden)

    D. Mutiatikum

    2012-10-01

    Full Text Available Penggunaan pestisida untuk budidaya komoditi pertanian memungkinkan adanya residu pestisida dalam sayuran sehingga konsumen berisiko tercemar pestisida yang merupakan zat toksik  sehingga diperlukan pemantmwn kadar residu dalam sayuran terutama yang langsung dikonsumsi tanpa dimasak. Penetapan  residu pestisida dilakukan dengan menggunakan kromatografi gas (GC. Hasil analisis residu pestisida golongan peretrin dalam tomat dan selada yang disampling dari pasar induk, pasar tradisional. pasar swalayan dan hipermarket yang berada diwilayah Jakarta menunjukkan hasil yang negatif (tidak terdeteksi.

  17. PESAN MORAL DALAM FILM TO KILL A MOCKINGBIRD (ANALISIS SEMIOTIKA PADA FILM TO KILL A MOCKINGBIRD

    OpenAIRE

    RENYOET, JAQUILINE MELISSA

    2014-01-01

    2014 JAQUILINE MELISSA RENYOET. Pesan Moral Dalam Film To Kill A Mockingbird (Analisis Semiotika Pada Film To Kill A Mockingbird). (Dibimbing oleh Muh. Nadjib dan Alem Febri Sonni). Tujuan Penelitian ini adalah mengidentifikasi bentuk pesan moral dan memahami makna pesan moral dalam film To Kill A Mockingbird. Penelitian ini dilakukan selama kurang lebih 2 bulan yaitu Maret ??? Mei 2014. Metode yang digunakan untuk penelitian ini adalah metode penelitian kualitatif den...

  18. ANALISIS PENERAPAN TAX PLANNING ATAS PAJAK PENGHASILAN BADAN PADA PT SEMEN TONASA PANGKEP

    OpenAIRE

    WIJAYA, AKBAR

    2014-01-01

    2014 ABSTRAK ANALISIS PENERAPAN TAX PLANNING ATAS PAJAK PENGHASILAN BADAN PADA PT SEMEN TONASA PANGKEP Implementation Analysis of Tax Planning on Board Incoming Tax of Semen Tonasa Ltd. Pangkep Akbar Wijaya Amiruddin Darmawati Penelitian ini bertujuan untuk mengetahui tax planning yang dilakukan oleh PT Semen Tonasa Pangkep, dan untuk menganalisis penerapan tax planning yang dilakukan oleh PT Semen Tonasa Pangkep dengan undang-undang perpajakan yang berlaku. Data...

  19. Analisis “Brand Equity” Siaran Berita Stasiun Televisi Swasta Indonesia

    OpenAIRE

    Arif Sugiono; Prima Mulyasari Agustina

    2004-01-01

    Penelitian ini bertujuan untuk mengetahui keadaan berbagai merek siaran berita stasiun televisi swasta berdasarkan dimensi ekuitas mereknya, dengan memfokuskan pada empat dimensi ekuitas merek, yang meliputi loyalitas merek, kesadaran merek, persepsi kualitas, dan asosiasi merek. Metode yang digunakan metode deskriptif, dengan analisis data menggunakan tabulasi dan teknik skala. Hasil penelitian dari dimensi loyalitas merek tiga besar siaran berita secara berurutan adalah Buser, Patroli dan L...

  20. Analisis Biaya, Volume, Laba sebagai Alat Bantu Perencanaan Laba pada Hotel Sedona Manado

    OpenAIRE

    Samahati, Ricky Budiman

    2013-01-01

    Manado sebagai kota pariwisata menyediakan sarana dan prasarana kepariwisataan termasuk jasa perhotelan. Hotel Sedona merupakan salah satu hotel yang ada di Kota Manado dan merupakan objek yang dipilih penulis dengan menggunakan data operasional penjualan yang terjadi pada tahun 2011 dan 2012. Tujuan penelitian ini yaitu untuk mengetahui titik break even point, jumlah volume penjualan pada tingkat laba yang direncanakan, serta tingkat margin of safety pada Hotel Sedona Manado. Metode analisi...