WorldWideScience

Sample records for type reactors inteligencia

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

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J

    1998-10-01

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

  2. 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.)

  3. LMFBR type reactor

    International Nuclear Information System (INIS)

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

    1988-01-01

    Purpose: To flatten the power distribution while maintaining the flattening in the axial power distribution in LMFBR type reactors. Constitution: Main system control rods are divided into control rods used for the operation and starting rods used for the starting of the reactor, and the starting rods are disposed in the radial periphery of the reactor core, while the control rods are disposed to the inside of the starting rods. With such a constitution, adjusting rods can be disposed in the region where the radial power peaking is generated to facilitate the flattening of the power distribution even in such a design that the ratio of the number of control rods to that of fuel assemblies is relatively large. That is, in this reactor, the radial power peaking is reduced by about 10% as compared with the conventional reactor core. As a result, the maximum linear power density during operation is reduced by about 10% to increase the thermal margin of the reactor core. If the maximum linear power density is set identical, the number of the fuel assemblies can be decreased by about 10%, to thereby reduce the fuel production cost. (K.M.)

  4. LMFBR type reactor

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Kawamura, Yutaka.

    1990-01-01

    A main vessel support skirt is supported by a base mat of reactor buildings and the base mat is supported by means of an earthquake-proof device on concretes of a lower raft disposed on ground rocks. The earthquake-proof device is constituted by alternately stacking, laminating and press-bonding thin steel plates together with thin rubber layers between an upper flange and a lower raft. Thus, for the horizontal seismic vibrations, the period of the swinging in the horizontal direction of the buildings is made greater than the swinging period of earthquakes by the earthquake-proof device to reduce the impact shocks of earthquakes. Further, for the vertical seismic vibrations, the input seismic movements are not amplified during transmission from the base mat of the buildings to the reactor structure by way of the support skirt of the main vessel, due to the shortened load transmission path and the seismic power design to the reactor structure can be moderated sufficiently. A safety LMFBR type reactor with reduced construction cost and improved reliability can be attained. (N.H.)

  5. Inteligencia emocional :

    OpenAIRE

    Barrio Rodríguez, Amós

    2015-01-01

    " El trabajo de fin de grado que voy a desarrollar tiene como tema central la Inteligencia Emocional, que es la capacidad para controlar y valorar las emociones propias y las de los demás, así como usar esa información para guiar nuestro comportamiento. Lo primero que hare será definir todo lo relacionado con la Teoría de las Inteligencias Múltiples y el concepto de Inteligencia Emocional dentro del contexto escolar, para posteriormente, proponer un Plan de Acción Tutorial basado en la Inteli...

  6. BWR type reactor core

    International Nuclear Information System (INIS)

    Tatemichi, Shin-ichiro.

    1981-01-01

    Purpose: To eliminate the variation in the power distribution of a BWR type reactor core in the axial direction even if the flow rate is increased or decreased by providing a difference in the void coefficient between the upper part and the lower parts of the reactor core, and increasing the void coefficient at the lower part of the reactor core. Constitution: The void coefficient of the lower region from the center to the lower part along the axial direction of a nuclear fuel assembly is increased to decrease the dependence on the flow rate of the axial power distribution of the nuclear fuel assembly. That is, a water/fuel ratio is varied, the water in non-boiled region is increased or the neutron spectrum is varied so as to vary the void coefficient. In order to exemplify it, the rate of the internal pellets of the fuel rod of the nuclear fuel assembly or the shape of the channel box is varied. Accordingly, the power does not considerably vary even if the flow rate is altered since the power is varied in the power operation. (Yoshihara, H.)

  7. New reactor type proposed

    CERN Multimedia

    2003-01-01

    "Russian scientists at the Research Institute of Nuclear Power Engineering in Moscow are hoping to develop a new reactor that will use lead and bismuth as fuel instead of uranium and plutonium" (1/2 page).

  8. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1988-01-01

    Purpose: To inhibit the lowering of the neutron moderation effect due to voids in the upper portion of the reactor core, thereby flatten the axial power distribution. Constitution: Although it has been proposed to enlarge the diameter at the upper portion of a water rod thereby increasing the moderator in the upper portion, since the water rod situates within the channel box, the increase in the capacity thereof is has certain limit. In the present invention, it is designed such that the volume of the region at the outside of the channel box for the fuel assembly to which non-boiling water in the non-boiling water region can enter is made greater in the upper portion than in the lower portion of the reactor core. Thus, if the moderator density in the upper portion of the reactor core should be decreased due to the generation of the voids, the neutron moderating effect in the upper portion of the reactor core is not lowered as compared with the lower portion of the reactor core and, accordingly, the axial power distribution can be flattening more as compared with that in the conventional nuclear reactors. (Takahashi, M.)

  9. Reactor scram device for FBR type reactor

    International Nuclear Information System (INIS)

    Kumasaka, Katsuyuki; Arashida, Genji; Itooka, Satoshi.

    1991-01-01

    In a control rod attaching structure in a reactor scram device of an FBR type reactor, an anti-rising mechanism proposed so far against external upward force upon occurrence of earthquakes relies on the engagement of a mechanical structure but temperature condition is not taken into consideration. Then, in the present invention, a material having curie temperature characteristics and which exhibits ferromagnetism only under low temperature condition and a magnet device are disposed to one of a movable control rod and a portion secured to the reactor. Alternatively, a bimetal member or a shape memory alloy which actuates to fix to the mating member only under low temperature condition is secured. The fixing device is adapted to operate so as to secure the control rods when the low temperature state is caused depending on the temperature condition. With such a constitution, when the control rods are separated from a driving device, they are prevented from rising even if they undergo external upward force due to earthquakes and so on, which can improve the reactor safety. (N.H.)

  10. FBR type reactors

    International Nuclear Information System (INIS)

    Maemoto, Junko.

    1985-01-01

    Purpose: To moderate abrupt temperature change near the inner walls of a suspended body thereby prevent thermal shocks and thermal deformations to structural materials. Constitution: High temperature coolants during ordinary operation of the nuclear reactor flow from the reactor core through the flow holes of the suspended body and from the upper plenum into an intermediate heat exchanger. The temperature of the coolants is lowered with heat exchanging effect with secondary coolants in the heat exchange and the coolants are then flow through the lower plenum into the reactor core and heated again. Upon generation of reactor scram, the temperature of the coolants at the exit of the reactor core is reduced abruptly and the flow rate is lowered due to the pump coast down. However, mixing of the coolants in the suspended body is accelerated by the coolants at high temperature flowing out of the flow holes and the coolants at the low temperature flowing from the flow hole group, to reduce the temperature difference and moderate the stratification flow forming an abrupt temperature slope. (Yoshihara, H.)

  11. BWR type reactor system

    International Nuclear Information System (INIS)

    Morooka, Shin-ichi.

    1980-01-01

    Purpose: To reduce the internal structure in a reactor by rapidly and efficiently transferring heat generated in a reactor core out of the reactor and eliminating the danger of radiation exposure. Constitution: Steam generated in a pressure vessel is introduced into heat pipe group by inserting the heat pipe group into the steam dome of the pressure vessel. The introduced steam is condensed in the heat pipes to transfer the heat of the steam to the heat pipe group. The transferred heat is transmitted to a heat exchanger provided out of a containment vessel to generate steam to operate a turbine. Thus, it is not necessary to introduce the steam including radioactive substance externally and can remove only the heat so as to carry out the desired purpose. (Kamimura, M.)

  12. FBR type reactors

    International Nuclear Information System (INIS)

    Kawashima, Katsuyuki; Azekura, Kazuo; Inoue, Kotaro.

    1981-01-01

    Purpose: To decrease power fluctuations due to burning of blanket fuel element clusters by partially replacing the fertile materials in the blanket fuel element clusters with fissile materials. Constitution: Fertile materials in the radial blanket fuel element clusters disposed to the outside or inside of the reactor core are partially replaced with fissile materials. Since the power density of the fissile materials is at the maximum in the initial burning stage and decreases as the burning proceeds, the power density of the materials which is smaller in the initial burning stage and becomes greater with the burning by the neutron-accumulated plutonium is offset. Accordingly, the power fluctuations in the blanket fuel element clusters due to the burning made smaller thereby enable to form a reactor core with less power fluctuations due to burning under the constant coolant flow rate depending on the power in the final burning stage where the blanket power is maximum. (Moriyama, K.)

  13. Molten salt reactor type

    International Nuclear Information System (INIS)

    1977-01-01

    This document is one of the three parts of a first volume devoted to the compilations of American data on the molten salt reactor concept. Emphasize is put essentially on the fuel salt of the primary circuit inside which fission reactions occur. The reasons why the (LiF-BeF 2 -ThF 4 -UF 4 ) salt was chosen for the M.S.B.R. concept are examined; the physical, physicochemical and chemical properties of this salt are discussed with its interactions with the structural materials and its evolution in time. An important part of this volume is devoted to the continuous reprocessing of the active salt, the project designers having deemed advisable to take advantage at best from the availability of a continuous purification, in a thermal breeding. The problem of tritium formation and distribution inside the reactor is also envisaged and the fundamentals of the chemistry of the secondary coolant salt are given. The solutions proposed are: the hydrogen scavenging of the primary circuit, a reduction in metal permeability by an oxyde layer deposition on the side in contact with the vapor, and tritium absorption through an isotope exchange with the hydroxifluoroborate [fr

  14. FBR type reactor

    International Nuclear Information System (INIS)

    Nagai, Fumio.

    1979-01-01

    Purpose: To unify the temperature distribution in a nuclear reactor vessel by the provision of a gas recycle path for pressurizing a cover gas to recycle the cover gas and thus stir the gas in a cover gas chamber. Constitution: A plurality of gas inlet tubes and gas discharge tubes are provided to the wall of a cover gas chamber above the liquid level of coolants in a nuclear reactor vessel and the cover gas is recycled through the tubes. The plurality of gas inlet tubes are each provided at their tops with nozzles opening circumferentially and communicated to the outlet of a compressor. While on the other hand, the plurality of gas discharge tubes are communicated to the inlet of a compressor. Upon operation of the compressor, the pressurized cover gas is jetted out from the nozzles, swirls along the inner circumferential surface of the vessel and interrupts and stirs the vertical thermal convection. The gas, after swirling one-half of the inner circumferential surface of the vessel, automatically flows out of the gas discharging tubes opening behind the nozzles and then flows into the inlet of the compressor. (Seki, T.)

  15. Natural convection type BWR reactor

    International Nuclear Information System (INIS)

    Tobimatsu, Toshimi.

    1990-01-01

    In a natural convection type BWR reactor, a mixed stream of steams and water undergo a great flow resistance. In particular, pressure loss upon passing from an upper plenum to a stand pipe and pressure loss upon passing through rotational blades are great. Then, a steam dryer comprising laminated dome-like perforated plates and a drain pipe for flowing down separated water to a downcomer are disposed above a riser. The coolants heated in the reactor core are boiled, uprise in the riser as a gas-liquid two phase flow containing voids, release steams containing droplets from the surface of the gas-liquid two phase, flow into the steam dryer comprising the perforated plates and are separated into a gas and a liquid. The dried steams flow to a turbine passing through a main steam pipe and the condensated droplets flow down through the drain pipe and the downcomer to the lower portion of the reactor core. In this way, the conventional gas-liquid separator can be saved without lowering the quality of steam drying to reduce the pressure loss and to improve the operation performance. (N.H.)

  16. High conversion burner type reactor

    International Nuclear Information System (INIS)

    Higuchi, Shin-ichi; Kawashima, Masatoshi

    1987-01-01

    Purpose: To simply and easily dismantle and reassemble densified fuel assemblies taken out of a high conversion ratio area thereby improve the neutron and fuel economy. Constitution: The burner portion for the purpose of fuel combustion is divided into a first burner region in adjacent with the high conversion ratio area at the center of the reactor core, and a second burner region formed to the outer circumference thereof and two types of fuels are charged therein. Densified fuel assemblies charged in the high conversion ratio area are separatably formed as fuel assemblies for use in the two types of burners. In this way, dense fuel assembly is separated into two types of fuel assemblies for use in burner of different number and arranging density of fuel elements which can be directly charged to the burner portion and facilitate the dismantling and reassembling of the fuel assemblies. Further, since the two types of fuel assemblies are charged in the burner portion, utilization factor for the neutron fuels can be improved. (Kamimura, M.)

  17. Livermore pool-type reactor

    International Nuclear Information System (INIS)

    Mann, L.G.

    1977-01-01

    The Livermore Pool-Type Reactor (LPTR) has served a dual purpose since 1958--as an instrument for fundamental research and as a tool for measurement and calibration. Our early efforts centered on neutron-diffraction, fission, and capture gamma-ray studies. During the 1960's it was used for extensive calibration work associated with radiochemical and physical measurements on nuclear-explosive tests. Since 1970 the principal applications have been for trace-element measurements and radiation-damage studies. Today's research program is dominated by radiochemical studies of the shorter-lived fission products and by research on the mechanisms of radiation damage. Trace-element measurement for the National Uranium Resource Evaluation (NURE) program is the major measurement application today

  18. PWR type process heat reactor

    International Nuclear Information System (INIS)

    Aubert, Gilles; Petit, Guy.

    1974-01-01

    The nuclear reactor described is of the pressurized water type. It includes a prestressed concrete vessel, the upper part of which is shut by a closure, and a core surrounded by a core ring. The core fuel assemblies are supported by an initial set of vertical tubes integral with the bottom of the vessel, which serve to guide the rods of the control system. Over the core there is a second set of vertical tubes, able to receive the absorbing part of a control rod when this is raised above the core. An annular pressurizer around the core ring keeps the water in a liquid state. A pump is located above the second set of tubes and is integral with the closure. It circulates the water between the core and the intake of at least one primary heat exchanger, the exchanger (s) being placed between the wall of the vessel and the core ring [fr

  19. Power control system in BWR type reactors

    International Nuclear Information System (INIS)

    Nishizawa, Yasuo.

    1980-01-01

    Purpose: To control the reactor power so that the power distribution can satisfy the limiting conditions, by regulating the reactor core flow rate while monitoring the power distribution in the reactor core of a BWR type reactor. Constitution: A power distribution monitor determines the power distribution for the entire reactor core based on the data for neutron flux, reactor core thermal power, reactor core flow rate and control rod pattern from the reactor and calculates the linear power density distribution. A power up ratio computing device computes the current linear power density increase ratio. An aimed power up ratio is determined by converting the electrical power up ratio transferred from a load demand input device into the reactor core thermal power up ratio. The present reactor core thermal power up ratio is subtracted from the limiting power up ratio and the difference is sent to an operation amount indicator and the reactor core flow rate is changed in a reactor core flow rate regulator, by which the reactor power is controlled. (Moriyama, K.)

  20. CALANDRIA TYPE SODIUM GRAPHITE REACTOR

    Science.gov (United States)

    Peterson, R.M.; Mahlmeister, J.E.; Vaughn, N.E.; Sanders, W.J.; Williams, A.C.

    1964-02-11

    A sodium graphite power reactor in which the unclad graphite moderator and fuel elements are contained within a core tank is described. The core tank is submersed in sodium within the reactor vessel. Extending longitudinally through the core thnk are process tubes with fuel elements positioned therein. A bellows sealing means allows axial expansion and construction of the tubes. Within the core tank, a leakage plenum is located below the graphite, and above the graphite is a gas space. A vent line regulates the gas pressure in the space, and another line removes sodium from the plenum. The sodium coolant flows from the lower reactor vessel through the annular space between the fuel elements and process tubes and out into the reactor vessel space above the core tank. From there, the heated coolant is drawn off through an outlet line and sent to the heat exchange. (AEC)

  1. Advanced nuclear reactor types and technologies

    Energy Technology Data Exchange (ETDEWEB)

    Ignatiev, V. [ed.; Feinberg, O.; Morozov, A. [Russian Research Centre `Kurchatov Institute`, Moscow (Russian Federation); Devell, L. [Studsvik Eco and Safety AB, Nykoeping (Sweden)

    1995-07-01

    The document is a comprehensive world-wide catalogue of concepts and designs of advanced fission reactor types and fuel cycle technologies. Two parts have been prepared: Part 1 Reactors for Power Production and Part 2 Heating and Other Reactor Applications. Part 3, which will cover advanced waste management technology, reprocessing and disposal for different nuclear fission options is planned for compilation during 1995. The catalogue was prepared according to a special format which briefly presents the project title, technical approach, development status, application of the technology, reactor type, power output, and organization which developed these designs. Part 1 and 2 cover water cooled reactors, liquid metal fast reactors, gas-cooled reactors and molten salt reactors. Subcritical accelerator-driven systems are also considered. Various reactor applications as power production, heat generation, ship propulsion, space power sources and transmutation of such waste are included. Each project is described within a few pages with the main features of an actual design using a table with main technical data and figure as well as references for additional information. Each chapter starts with an introduction which briefly describes main trends and approaches in this field. Explanations of terms and abbreviations are provided in a glossary.

  2. Advanced nuclear reactor types and technologies

    International Nuclear Information System (INIS)

    Ignatiev, V.; Devell, L.

    1995-01-01

    The document is a comprehensive world-wide catalogue of concepts and designs of advanced fission reactor types and fuel cycle technologies. Two parts have been prepared: Part 1 Reactors for Power Production and Part 2 Heating and Other Reactor Applications. Part 3, which will cover advanced waste management technology, reprocessing and disposal for different nuclear fission options is planned for compilation during 1995. The catalogue was prepared according to a special format which briefly presents the project title, technical approach, development status, application of the technology, reactor type, power output, and organization which developed these designs. Part 1 and 2 cover water cooled reactors, liquid metal fast reactors, gas-cooled reactors and molten salt reactors. Subcritical accelerator-driven systems are also considered. Various reactor applications as power production, heat generation, ship propulsion, space power sources and transmutation of such waste are included. Each project is described within a few pages with the main features of an actual design using a table with main technical data and figure as well as references for additional information. Each chapter starts with an introduction which briefly describes main trends and approaches in this field. Explanations of terms and abbreviations are provided in a glossary

  3. Research Reactors Types and Utilization

    International Nuclear Information System (INIS)

    Nasr, Nahla

    2008-01-01

    A nuclear reactor, in gross terms, is a device in which nuclear chain reactions are initiated, controlled, and sustained at a steady rate. The nuclei of fuel heavy atoms (mostly 235 U or 239 Pu), when struck by a slow neutron, may split into two or more smaller nuclei as fission products,releasing energy and neutrons in a process called nuclear fission. These newly-born fast neutrons then undergo several successive collisions with relatively low atomic mass material, the moderator, to become thermalized or slow. Normal water, heavy water, graphite and beryllium are typical moderators. These neutrons then trigger further fissions, and so on. When this nuclear chain reaction is controlled, the energy released can be used to heat water, produce steam and drive a turbine that generates electricity. The fission process, and hence the energy release, are controlled by the insertion (or extraction) of control rods through the reactor. These rods are strongly neutron absorbents, and thus only enough neutrons to sustain the chain reaction are left in the core. The energy released, mostly in the form of heat, should be continuously removed, to protect the core from damage. The most significant use of nuclear reactors is as an energy source for the generation of electrical power and for power in some military ships. This is usually accomplished by methods that involve using heat from the nuclear reaction to power steam turbines. Research reactors are used for radioisotope production and for beam experiments with free neutrons. Historically, the first use of nuclear reactors was the production of weapons grade plutonium for nuclear weapons. Currently all commercial nuclear reactors are based on nuclear fission. Fusion power is an experimental technology based on nuclear fusion instead of fission.

  4. HTGR type reactors for the heat market

    International Nuclear Information System (INIS)

    Oesterwind, D.

    1981-01-01

    Information about the standard of development of the HTGR type reactor are followed by an assessment of its utilization on the heat market. The utilization of HTGR type reactors is considered suitable for the production of synthesis gas, district heat, and industrial process heat. A comparison with a pit coal power station shows the economy of the HTGR. Finally, some aspects of introducing new technologies into the market, i.e. small plants in particular are investigated. (UA) [de

  5. Fuel exchanger in FBR type reactor

    International Nuclear Information System (INIS)

    Shinden, Kazuhiko; Tanaka, Osamu.

    1990-01-01

    The present invention concerns a fuel exchanger for exchanging fuels in an LMFBR type reactor using liquid metals as coolants. An outer gripper cylinder rotating device for rotating an outer gripper cylinder that holds a gripper is driven, to lower the gripper driving portion and the outer gripper cylinder, fuels are caught by the finger at the top end of the outer gripper cylinder and elevated to extract the fuels from the reactor core. Then, the gripper driving portion casing and the outer gripper cylinder are rotated to rotate the fuels caught by the gripper. Subsequently, the gripper driving portion and the outer gripper cylinder are lowered to charge the fuels in the reactor core. This can directly shuffle the fuels in the reactor core without once transferring the fuels into a reactor storing pot and replacing with other fuels, thereby shortening the shuffling time. (I.N.)

  6. Method of operating FBR type reactors

    International Nuclear Information System (INIS)

    Arie, Kazuo.

    1984-01-01

    Purpose: To secure the controlling performance and the safety of FBR type reactors by decreasing the amount of deformation due to the difference in the heat expansion of a control rod guide tube. Method: The reactor is operated while disposing reactor core fuel assemblies of a same power at point-to-point symmetrical positions relative to the axial center for the control rod assembly. This can eliminate the temperature difference between opposing surfaces of the control rod guide tube and eliminate the difference in the thermal expansion. (Yoshino, Y.)

  7. Different types of power reactors and provenness

    International Nuclear Information System (INIS)

    Goodman, E.I.

    1977-01-01

    The lecture guides the potential buyer in the selection of a reactor type. Recommended criteria regarding provenness, licensability, and contractual arrangements are defined and discussed. Tabular data summarizing operating experience and commercial availability of units are presented and discussed. The status of small and medium power reactors which are of interest to many developing countries is presented. It is stressed that each prospective buyer will have to establish his own criteria based on specific conditions which will be applied to reactor selection. In all cases it will be found that selection, either pre-selection of bidders or final selection of supplier, will be a fairly complex evaluation. (orig.) [de

  8. Vibration-proof FBR type reactor

    International Nuclear Information System (INIS)

    Kawamura, Yutaka.

    1992-01-01

    In a reactor container in an FBR type reactor, an outer building and upper and lower portions of a reactor container are connected by a load transmission device made of a laminated material of rubber and steel plates. Each of the reactor container and the outer building is disposed on a lower raft disposed on a rock by way of a vibration-proof device made of a laminated material of rubber and steel plates. Vibration-proof elements for providing vertical eigen frequency of the vibration-proof system comprising the reactor building and the vibration-proof device within a range of 3Hz to 5Hz are used. That is, the peak of designed acceleration for response spectrum in the horizontal direction of the reactor structural portions is shifted to side of shorter period from the main frequency region of the reactor structure. Alternatively, rigidity of the vibration-proof elements is decreased to shift the peak to the side of long period from the main frequency region. Designed seismic force can be greatly reduced both horizontally and vertically, to reduce the wall thickness of the structural members, improve the plant economy and to ensure the safety against earthquakes. (N.H.)

  9. Inteligencias múltiples

    OpenAIRE

    Howard Gardner

    2005-01-01

    El presente Trabajo Fin de Grado de Educación Infantil está centrado en la Teoría de las Inteligencias Múltiples, la cual, pretende ampliar el alcance del potencial humano más allá de los confines de la cifra del cociente intelectual. Por ello, primeramente se describirán las características más notorias de cada una de las inteligencias múltiples para así, posteriormente, poder acercarnos a una visión más práctica de las mismas en el aula. Con este proyecto se pretende profundizar en las ...

  10. Method of operating BWR type reactors

    International Nuclear Information System (INIS)

    Sekimizu, Koichi

    1980-01-01

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

  11. Hydrogen injection device in BWR type reactor

    International Nuclear Information System (INIS)

    Takagi, Jun-ichi; Kubo, Koji.

    1988-01-01

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

  12. Utilization of thorium in PWR type reactors

    International Nuclear Information System (INIS)

    Correa, F.

    1977-01-01

    Uranium 235 consumption is comparatively evaluated with thorium cycle for a PWR type reactor. Modifications are only made in fuels components. U-235 consumption is pratically unchanged in both cycles. Some good results are promised to the mixed U-238/Th-232 fuel cycle in 1/1 proportion [pt

  13. Control rod for FBR type reactor

    International Nuclear Information System (INIS)

    Nakai, Koichi.

    1993-01-01

    In a control rod for an LMFBR type reactor, a thermal resistor is disposed between a temperature sensitive cylinder and a cam unit support rod. A thermal expansion difference due to the temperature difference is caused between the temperature sensitive cylinder and the cam unit support rod only upon abrupt temperature change of coolants. A control rod shaft extending mechanism of downwardly depressing an absorbent portion by amplifying the thermal expansion difference by an extension link mechanism and the cam unit is provided. The thermal resistor comprises inconel 625 or like other steel of small heat conductivity. If a certain abnormality should cause to the reactor system to elevate the coolant temperature in the reactor elevates abruptly and the reactor shutdown system does not actuate, since the control rod extension shaft extends to urge the absorbent and lower the reactor core reactivity, so that leading to serious accident can be prevented surely. Further, the control rod extension shaft does not extend upon moderate temperature elevation in the usual startup and causes no unnecessary reactivity change. (N.H.)

  14. Water-immersion type ship reactor

    International Nuclear Information System (INIS)

    Okada, Hiroki; Yamamura, Toshio.

    1996-01-01

    In a water immersion-type ship reactor in which a water-tight wall is formed around a pressure vessel by way of an air permeable heat insulation layer and immersing the wall under water in a reactor container, a pressure equalizing means equipped with a back flow check valve and introducing a gas in a gas phase portion above the water level of the container into a water tight wall and a relief valve for releasing the gas in the water tight wall to the reactor container are disposed on the water tight wall. When the pressure in the water tight wall exceeds the pressure in the container, the gas in the water tight wall is released from the relief valve to the reactor container. On the contrary, when the pressure in the container exceeds the pressure in the water tight wall, the gas in the gas phase portion is flown from the pressure equalizing means equipped with a back flow check valve to the inside of the water tight wall. Thus, a differential pressure between both of them is kept around 0kg/cm 2 . A large differential pressure is not exerted on the water tight wall thereby capable of preventing rupture of them to improve reliability, as well as the thickness of the plate can be decreased thereby enabling to moderate the design for the pressure resistance and reduce the weight. (N.H.)

  15. Inteligencia interpersonal: conceptos clave

    Directory of Open Access Journals (Sweden)

    Antoni CASTELLÓ

    2011-01-01

    Full Text Available El propósito de este trabajo es el de delimitar el espacio conceptual de la inteligencia interpersonal, relacionándolo con las situaciones en las cuales se utiliza. Para ello se establecen, en primer lugar, los aspectos relacionados con la naturaleza intelectual y el tipo de objetos representados. Sigue un apartado dedicado a los orígenes de la misma y su función en la adaptación de la especie humana. Un tercer apartado trata del tipo de procedimientos adecuados para su medición, no como una recopilación de instrumentos comúnmente utilizados, sino como una manera de hacer explícitos qué tipo de indicios son buena prueba de este tipo de inteligencia. A continuación se describen algunas de las principales confusiones asociadas a la idea de esta forma de inteligencia, integrando finalmente todos los aspectos tratados en el apartado de conclusiones.

  16. Fueling method in LMFBR type reactors

    International Nuclear Information System (INIS)

    Kawashima, Katsuyuki; Inoue, Kotaro.

    1985-01-01

    Purpose: To extend the burning cycle and decrease the number of fuel exchange batches without increasing the excess reactivity at the initial stage of burning cycles upon fuel loading to an LMFBR type reactor. Method: Each of the burning cycles is divided into a plurality of burning sections. Fuels are charged at the first burning section in each of the cycles such that driver fuel assemblies and blanket assemblies or those assemblies containing neutron absorbers such as boron are distributed in mixture in the reactor core region. At the final stage of the first burning section, the blanket assemblies or neutron absorber-containing assemblies present in mixture are partially or entirely replaced with driver fuel assemblies depending on the number of burning sections such that all of them are replaced with the driver fuel assemblies till the start of the final burning section of the abovementioned cycle. The object of this invention can thus be attained. (Horiuchi, T.)

  17. Agitation device in BWR type reactor

    International Nuclear Information System (INIS)

    Nakamizo, Hiroshi.

    1988-01-01

    Purpose: To secure the integrity of a pressure vessel upon reactor accident by maintaining the water temperature in the pressure suppression pool at a low temperature. Constitution: The pressure vessel and the pressure control pool in a BWR type reactor are connected with a vent pipe by way of a safety valve. Steams generated in the pressure vessel are introduced through the vent pipe into pool water. A turbine is disposed at the midway of the vent pipe and rotated with steams flowing through the vent pipe. A vane is disposed in the pressure suppression pool for agitating water and rotated by the turbine. The temperature distribution for the water in the pool is made uniform by the stirring. In this way, by rotating the vane using steams, since water can automatically be agitated as required without utilizing any power source of other system such as an electric power supply, pool water can be cooled at a high reliability. (Ikeda, J.)

  18. Steam generating system in LMFBR type reactors

    International Nuclear Information System (INIS)

    Kurosawa, Katsutoshi.

    1984-01-01

    Purpose: To suppress the thermal shock loads to the structures of reactor system and secondary coolant system, for instance, upon plant trip accompanying turbine trip in the steam generation system of LMFBR type reactors. Constitution: Additional feedwater heater is disposed to the pipeway at the inlet of a steam generator in a steam generation system equipped with a closed loop extended from a steam generator by way of a gas-liquid separator, a turbine and a condensator to the steam generator. The separated water at high temperature and high pressure from a gas-liquid separator is heat exchanged with coolants flowing through the closed loop of the steam generation system in non-contact manner and, thereafter, introduced to a water reservoir tank. This can avoid the water to be fed at low temperature as it is to the steam generator, whereby the thermal shock loads to the structures of the reactor system and the secondary coolant system can be suppressed. (Moriyama, K.)

  19. 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

  20. Shielding plug for LMFBR type reactors

    International Nuclear Information System (INIS)

    Hashiguchi, Ko.

    1979-01-01

    Purpose: To enable effective removal of liquid metals deposited, if any, in the gaps between a rotary plug and a fixed plug in LMFBR type reactors. Constitution: A plate incorporated with a heater and capable of projecting in a gap between a rotary plug and a fixed plug, and a scraper connected in perpendicular to it are provided to the rotary plug. Solidified liquid metals such as sodium deposited in the gap are effectively removed by the heating with the heater and the scraping action due to the rotation. (Horiuchi, T.)

  1. Design guide for Category III reactors: pool type reactors

    International Nuclear Information System (INIS)

    Brynda, W.J.; Lobner, P.R.; Powell, R.W.; Straker, E.A.

    1978-11-01

    The Department of Energy (DOE) in the ERDA Manual requires that all DOE-owned reactors be sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate consideration to health and safety factors. Specific guidance pertinent to the safety of DOE-owned reactors is found in Chapter 0540 of the ERDA Manual. The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirement of Category III reactor structures, components, and systems

  2. Method of starting up PWR type reactor

    International Nuclear Information System (INIS)

    Kadokami, Akira; Ueno, Ryuji; Tsuge, Ayao; Onimura, Kichiro; Ochi, Tatsuya.

    1988-01-01

    Purpose: To start-up a PWR type reactor so as to effectively impregnate and concentrate corrosion inhibitors in intergranular corrosive faces. Method: Upon reactor start-up, after transferring from the warm zero output state to thermal power loaded state and injecting corrosion inhibitors, thermal power is returned to zero and, subsequently, increased up to a rated power. By selecting the thermal power upon injecting the corrosion inhibitors to a steam generator body, that is, by selecting a thermal power load that starts to boil in heat conduction tubes, feedwater in the clavis portion can be formed into an appropriate boiling convection and, accordingly, the corrosion inhibitors can be penetrated to the clevis portion at a higher rate and in a greater amount as compared with those under zero power condition. Subsequently, when the thermal power is reduced, a sub-cooled state is attained in the clevis portion, in which steams present in the intergranular corrosion faces in the heat conduction tubes are condensated. As a result, the corrosion inhibitors at high concentration are impregnated into the intergranular corrosive faces to provide excellent effects. (Kamimura, M.)

  3. Determining a pool - type reactor fuel policy

    International Nuclear Information System (INIS)

    1964-01-01

    Refuelling the 10 to 15 MW pool type reactor considered here will occur frequently (some 10 elements every 3 to 4 weeks). It is therefore necessary to determine the most economic fuel policy. This study proposes to define a strategy that will make it possible to decide on the number and characteristics of the shipment containers, as well as on the means of storage, so as to reduce the risks as much as possible should the basic parameters of the study vary. Among these parameters, the respective influence of which is investigated, chemical reprocessing costs play a vital part. Two examples of optimum fuel management are given according to whether the reprocessing charges applied are those of the old or of the 1961 U.S. AEC base charges for reprocessing highly enriched irradiated fuel. (authors) [fr

  4. Pressure vessel for a BWR type reactor

    International Nuclear Information System (INIS)

    Shimamoto, Yoshiharu.

    1980-01-01

    Purpose: To prevent the retention of low temperature water and also prevent the thermal fatigue of the pressure vessel by making large the curvature radius of a pressure vessel of a feed water sparger fitting portion and accelerating the mixing of low-temperature water at the feed water sparger base and in-pile hot water. Constitution: The curvature radius of the corner of the feed water sparger fitting portion in a pressure vessel is formed largely. In-pile circulating water infiltrates up to the base portion of the feed water sparger to carry outside low-temperature water at the base part, which is mixed with in-pile hot water. Accordingly, low temperature water does not stay at the base portion of the feed water sparger and generation of thermal fatigue in the pressure vessel can be prevented and the safety of the BWR type reactor can be improved. (Yoshino, Y.)

  5. Reactor core control device for FBR type reactor

    International Nuclear Information System (INIS)

    Iida, Norihiko

    1991-01-01

    The device of the present invention comprises a control line having a control pump and a control tank for injecting liquids for neutron reflectors to an annular tank disposed in a reactor container, a supply line having a supply pump and a supply tank for supplying the liquids for the reflectors to the control tank, a drain line having a control valve, a drain valve and a drain tank disposed to the annular tank and a make-up line for supplying the liquids for the reflectors from the drain tank to the control tank. Liquids such as water or oil for the neutron reflectors are injected in the annular tank disposed at the periphery of the reactor core to raise the level of the liquids in the tank and conduct burning in the reactor core. The liquid level may be controlled by an appropriate ON/OFF operation of a pump with no requirement for a motor or a driving device at a high accuracy and rotational portions. Periodical maintenances are not necessary. Reactor scram can be conducted only by opening the drain valve and the reflectors may be made of inexpensive materials. (N.H.)

  6. Non-electric applications of pool-type nuclear reactors

    International Nuclear Information System (INIS)

    Adamov, E.O.; Cherkashov, Yu.M.; Romenkov, A.A.

    1997-01-01

    This paper recommends the use of pool-type light water reactors for thermal energy production. Safety and reliability of these reactors were already demonstrated to the public by the long-term operation of swimming pool research reactors. The paper presents the design experience of two projects: Apatity Underground Nuclear Heating Plant and Nuclear Sea-Water Desalination Plant. The simplicity of pool-type reactors, the ease of their manufacturing and maintenance make this type of a heat source attractive to the countries without a developed nuclear industry. (author). 6 figs, 1 tab

  7. Reactor core and control rod assembly in FBR type reactor

    International Nuclear Information System (INIS)

    Fujimura, Koji; Kawashima, Katsuyuki; Itooka, Satoshi.

    1993-01-01

    Fuel assemblies and control rod assemblies are attached respectively to reactor core support plates each in a cantilever fashion. Intermediate spacer pads are disposed to the lateral side of a wrapper tube just above the fuel rod region. Intermediate space pads are disposed to the lateral side of a control rod guide tube just above a fuel rod region. The thickness of the intermediate spacer pad for the control rod assembly is made smaller than the thickness of the intermediate spacer pad for the fuel assembly. This can prevent contact between intermediate spacer pads of the control guide tube and the fuel assembly even if the temperature of coolants is elevated to thermally expand the intermediate spacer pad, by which the radial displacement amount of the reactor core region along the direction of the height of the control guide tube is reduced substantially to zero. Accordingly, contribution of the control rod assembly to the radial expansion reactivity can be reduced to zero or negative level, by which the effect of the negative radial expansion reactivity of the reactor is increased to improve the safety upon thermal transient stage, for example, loss of coolant flow rate accident. (I.N.)

  8. Steam generator of FBR type reactor

    International Nuclear Information System (INIS)

    Hashiguchi, Ko.

    1992-01-01

    Liquid metal (for example, mercury) which is scarcely reactive with metal sodium is contained and cover gases which are scarcely reactive with the liquid metal are filled in a steam generator of an FBR type reactor and it is closed. The heat of primary sodium is transferred to the liquid metal, which is not reactive with sodium, in a primary thermal conduction portion. Since the temperature of the primary thermal conduction portion is high, the density is extremely low. On the other hand, since a second thermal conduction portion is kept at a single phase and the temperature is lower compared with that of the first thermal conduction portion, the density is kept high. since the density difference and gas jetting speed generate a great circulating force to liquid metal passing the opening of a partition plate, heat can be conducted on the side of water without disposing pumps. The steam concentration in the liquid metal is low being in a single phase of steams, corrosion caused from the outside of pipes of the primary thermal conduction pipe is scarcely promoted. Even if sodium leaks should be caused, since the sodium concentration in the liquid metal is extremely low and the reactivity is low, the temperature of the liquid metal is not elevated. (N.H.)

  9. Steam generator for FBR type reactor

    International Nuclear Information System (INIS)

    Watabe, Ichiro

    1998-01-01

    In a steam generator for an FBR type reactor, a heating fluid is introduced from outer circumferential one end of a cylindrical main body by way of a heating fluid distribution structure main body, put to heat exchange with helical coils disposed inside of the main body and then discharged from the other end of the main body, the distribution structure comprises a heating fluid entrance connected to and passed through the outer one circumferential end of the main body and an inner distribution duct comprising a cylindrical body having a large number of small distribution apertures on the circumference and having ring-like flanges protruded outwardly on both ends, with the end of one flange being secured to the inner surface of the main body so that an entrance for heating fluid is opened between both of the flanges. Since the other flange is left free, there is no restriction between the main body and the inner distribution duct, and the heating fluid distribution structure can be free from thermal stresses. (N.H.)

  10. Steam generator for FBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Watabe, Ichiro

    1998-11-24

    In a steam generator for an FBR type reactor, a heating fluid is introduced from outer circumferential one end of a cylindrical main body by way of a heating fluid distribution structure main body, put to heat exchange with helical coils disposed inside of the main body and then discharged from the other end of the main body, the distribution structure comprises a heating fluid entrance connected to and passed through the outer one circumferential end of the main body and an inner distribution duct comprising a cylindrical body having a large number of small distribution apertures on the circumference and having ring-like flanges protruded outwardly on both ends, with the end of one flange being secured to the inner surface of the main body so that an entrance for heating fluid is opened between both of the flanges. Since the other flange is left free, there is no restriction between the main body and the inner distribution duct, and the heating fluid distribution structure can be free from thermal stresses. (N.H.)

  11. Dynamic behaviour of a CAREM type reactor

    International Nuclear Information System (INIS)

    Abbate, P.; Doval, A.

    1990-01-01

    As complement to CAREM reactor design studies, behaviour analysis were made in a non-stationary regime, with the aim of developing plant systems and determining process variables variation ranges, characteristic of normal operating conditions, specifying alarm values for different variables, as well as for operating policies. Transient accidental scenes analysis were made, concluding that reactor characteristics provide security, maintaining the core integrity. (Author) [es

  12. Fuel exchange device for FBR type reactor

    International Nuclear Information System (INIS)

    Onuki, Koji.

    1993-01-01

    The device of the present invention can provide fresh fuels with a rotational angle aligned with the direction in the reactor core, so that the fresh fuels can be inserted being aligned with apertures of the reactor core even if a self orientation mechanism should fail to operate. That is, a rotational angle detection means (1) detects the rotational angle of fresh fuels before insertion to the reactor core. A fuel rotational angle control means (2) controls the rotational angle of the fresh fuels by comparing the detection result of the means (1) and the data for the insertion position of the reactor core. A fuel rotation means (3) compensates the rotational angel of the fresh fuels based on the control signal from the means (2). In this way, when the fresh fuels are inserted to the reactor core, the fresh fuels set at the same angle as that for the aperture of the reactor core. Accordingly, even if the self orientation mechanism should not operate, the fresh fuels can be inserted smoothly. As a result, it is possible to save loss time upon fuel exchange and mitigate operator's burden during operation. (I.S.)

  13. LAS MÚLTIPLES INTELIGENCIAS

    Directory of Open Access Journals (Sweden)

    María Amarís Macías

    2002-01-01

    Full Text Available Este trabajo tiene como objetivo plantear un análisis reflexivo acerca de «Las múltiples inteligencias», expuesta por el psicólogo y neurólogo Howard Gardner. Esta propuesta rompe el paradigma tradicional de inteligencia como única y general y señala su condición de pluralidad. Esta nueva visión de la inteligencia permite reivindicar la condición humana con relación a sus múltiples capacidades de cognición y genera en la educación nuevas prácticas pedagógicas e institucionales. Finalmente, se señala también el valor del entorno cultural para el desarrollo del intelecto humano.

  14. Strategies of operation cycles in BWR type reactors

    International Nuclear Information System (INIS)

    Molina, D.; Sendino, F.

    1996-01-01

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

  15. Self-operation type power control device for nuclear reactor

    International Nuclear Information System (INIS)

    Kanbe, Mitsuru.

    1993-01-01

    The device of the present invention operates by sensing the temperature change of a reactor core in all of LMFBR type reactors irrespective of the scale of the reactor core power. That is, a region where liquid poison is filled is disposed at the upper portion and a region where sealed gases are filled is disposed at the lower portion of a pipe having both ends thereof being closed. When the pipe is inserted into the reactor core, the inner diameter of the pipe is determined smaller than a predetermined value so that the boundary between the liquid poison and the sealed gases in the pipe is maintained relative to an assumed maximum acceleration. The sealed gas region is disposed at the reactor core region. If the liquid poison is expanded by the elevation of the reactor core exit temperature, it is moved to the lower gas region, to control the reactor power. Since high reliability can be maintained over a long period of time by this method, it is suitable to FBR reactors disposed in such environments that maintenance can not easily be conducted, such as desserts, isolated islands and undeveloped countries. Further, it is also suitable to ultra small sized nuclear reactors disposed at environments that the direction and the magnitude of gravity are different from those on the ground. (I.S.)

  16. Operation control equipment for BWR type reactor

    International Nuclear Information System (INIS)

    Izumi, Masayuki; Takeda, Renzo.

    1981-01-01

    Purpose: To improve the temperature balance in a feedwater heater by obtaining the objective value of a feedwater enthalpy upon calculation of respective measured values and controlling the opening or closing of an extraction valve so that the objective value may coincide with the measured value, thereby averaging the axial power distribution. Constitution: A plurality of stages of extraction lines are connected to a turbine, and extraction valves are respectively provided at the lines. By calculating the measured values of ractor pressure, reactor core flow rate, vapor flow rate and reactor core inlet enthalpy determined to predetermined value using heat balance the objective feedwater enthalpy is obtained, is fed as an extraction valve opening or closing signal from a control equipment, the extraction stages of the turbine extraction are altered in accordance with this signal, and the feedwater enthalpy is controlled. (Sekiya, K.)

  17. Primary cooling system for BWR type reactor

    International Nuclear Information System (INIS)

    Ibe, Eishi; Takahashi, Masanori; Aoki, Yasuko

    1993-01-01

    The present invention effectively uses information from a plurality of sensors in order to suppress corrosion circumstance of a nuclear reactor. That is, a predetermined general water quality factor at a predetermined position is determined as a standard index. A concentration of a water quality improver is controlled such that the index is within an aimed range. For this purpose, the entire sensor groups disposed in a primary coolant system of a nuclear reactor are divided into a plural systems of sensor groups each disposed on every different positions. Then, a predetermined sensor group (standard sensor group) is connected to a computing device and a data base so that it is always monitored for calculating and estimating the standard index. Only oxidative ingredient in water at the measuring point is noted, and a concentration distribution which agrees with an actually measured value of oxidative ingredients is extracted from data base and used as a correct concentration distribution. With such procedures, reactor water quality can be estimated accurately while compensating erroneous factors of individual sensors. Even when a new sensor is used, it is not necessary to greatly change control logic. (I.S.)

  18. Core arrangement in BWR type reactors

    International Nuclear Information System (INIS)

    Asano, Masayuki.

    1981-01-01

    Purpose: To decrease the number of fuel assemblies whose locations are to be changed upon fuel exchange, as well as unify the power distribution in the core by arranging, in a chess board configuration, a plurality pattern of unit reactor lattices each containing fuel assemblies of different burnup degrees in orthogonal positions to each other. Constitution: A first pattern of unit reactor lattice is formed by disposing fuel assemblies of burnup degree 1 and fuel assemblies of burnup degree 3 at orthogonal positions to each other. A second pattern of unit reactor lattice is formed by disposing fuel assemblies of burnup degree 2 and fuel assemblies of burnup degree 1 at orthogonal positions to each other. The unit lattices each in such a dispositions are arranged in a chess board arrangement. Since, the fuel assemblies of the burnup degree 1 in the first pattern unit lattices proceed to the burnup degree 2 and the fuel assemblies of the burnup degree 2 in the second pattern unit lattices proceed to the burnup degree 3 up to the fuel exchange stage, fuel exchange and movement have only to be made, not for those fuel assemblies, but for another half of the fuel assemblies. (Kawakami, Y.)

  19. Three-dimensional reactor dynamics code for VVER type nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kyrki-Rajamaeki, R. [VTT Energy, Espoo (Finland)

    1995-10-01

    A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.).

  20. Three-dimensional reactor dynamics code for VVER type nuclear reactors

    International Nuclear Information System (INIS)

    Kyrki-Rajamaeki, R.

    1995-10-01

    A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.)

  1. Pin-Type Gas Cooled Reactor for Nuclear Electric Propulsion

    Science.gov (United States)

    Wright, Steven A.; Lipinski, Ronald J.

    2003-01-01

    This paper describes a point design for a pin-type Gas-Cooled Reactor concept that uses a fuel pin design similar to the SP100 fuel pin. The Gas-Cooled Reactor is designed to operate at 100 kWe for 7 years plus have a reduced power mode of 20% power for a duration of 5 years. The power system uses a gas-cooled, UN-fueled, pin-type reactor to heat He/Xe gas that flows directly into a recuperated Brayton system to produce electricity. Heat is rejected to space via a thermal radiator that unfolds in space. The reactor contains approximately 154 kg of 93.15 % enriched UN in 313 fuel pins. The fuel is clad with rhenium-lined Nb-1Zr. The pressures vessel and ducting are cooled by the 900 K He/Xe gas inlet flow or by thermal radiation. This permits all pressure boundaries to be made of superalloy metals rather than refractory metals, which greatly reduces the cost and development schedule required by the project. The reactor contains sufficient rhenium (a neutron poison) to make the reactor subcritical under water immersion accidents without the use of internal shutdown rods. The mass of the reactor and reflectors is about 750 kg.

  2. Fuel assembly for PWR type reactor

    International Nuclear Information System (INIS)

    Yokoyama, Takashi.

    1991-01-01

    In a fuel assembly in a reactor-loaded state, pellets to be loaded in a region higher than a predetermined height are made hollow. That is, the volume of the gap in the hollow portion of the pellet comprising fissible materials to be filled at a position higher by 1/2 to 1/3 height from the upper region (downstream of coolant flow) of at least a portion of fuel rods in a fuel assembly is reduced stepwise than that in the lower region (upstream of coolant flow). Alternatively, the volume of the gap is gradually reduced from the lower portion to the upper portion. The diameter of the hollow hole portion is thus varied and the volume of the gap of the fissible materials per pellet is controlled, to reduce the amount of the fissile materials per unit volume. With such a constitution, the power of fission energy in the reactor core upper portion can be lowered. Accordingly, the corrosion of a cladding tube upon high burnup degree can be suppressed, thereby enabling to ensure integrity. (T.M.)

  3. Self operation type reactor scram device

    International Nuclear Information System (INIS)

    Saito, Makoto; Gunji, Minoru.

    1992-01-01

    A control rod having neutron absorbers therein is held by a curie point electromagnet by way of a control rod extension shaft. The electromagnet is suspended from a vertically movable driving shaft in an upper guide tube. Then, a heater is disposed at the lower portion in the inner side of the upper guide tube. Upon a function confirmation test, the electromagnet is at first pulled up to the inside of the upper guide tube. Subsequently, the electromagnet is heated by the heater by a temperature higher than the curie point of the temperature sensing magnetic material. If the function is normal, armature connected to the control rod extension tube is separated. With such a constitution, the electromagnetic portion is isolated from a coolant main stream, thereby enabling to avoid the cooling effect by the stream of coolants. Accordingly, the operation test for confirming the integrity of the function of the curie point electromagnet can be conducted while placing the electromagnet in the reactor core as it is during actual reactor operation. (I.N.)

  4. Coolant cleanup system for BWR type reactor

    International Nuclear Information System (INIS)

    Kinoshita, Shoichiro; Araki, Hidefumi.

    1993-01-01

    The cleanup system of the present invention removes impurity ions and floating materials accumulated in a reactor during evaporation of coolants in the nuclear reactor. That is, coolants pass pipelines from a pressure vessel using pressure difference between a high pressure in the pressure vessel and a low pressure at the upstream of a condensate filtration/desalting device of a condensate/feed water system as a driving source, during which cations and floating materials are removed in a high temperature filtration/desalting device and coolants flow into the condensate/feedwater system. Impurities containing anions are removed here by the condensates filtration/desalting device. Then, they return to the pressure vessel while pressurized and heated by a condensate pump, a feed water pump and a feed water heater. At least pumps, a heat exchanger for heating, a filtration/desalting device for removing anions and pipelines connecting them used exclusively for the coolant cleanup system are no more necessary. (I.S.)

  5. Station Blackout Analysis of HTGR-Type Experimental Power Reactor

    Science.gov (United States)

    Syarip; Zuhdi, Aliq; Falah, Sabilul

    2018-01-01

    The National Nuclear Energy Agency of Indonesia has decided to build an experimental power reactor of high-temperature gas-cooled reactor (HTGR) type located at Puspiptek Complex. The purpose of this project is to demonstrate a small modular nuclear power plant that can be operated safely. One of the reactor safety characteristics is the reliability of the reactor to the station blackout (SBO) event. The event was observed due to relatively high disturbance frequency of electricity network in Indonesia. The PCTRAN-HTR functional simulator code was used to observe fuel and coolant temperature, and coolant pressure during the SBO event. The reactor simulated at 10 MW for 7200 s then the SBO occurred for 1-3 minutes. The analysis result shows that the reactor power decreases automatically as the temperature increase during SBO accident without operator’s active action. The fuel temperature increased by 36.57 °C every minute during SBO and the power decreased by 0.069 MW every °C fuel temperature rise at the condition of anticipated transient without reactor scram. Whilst, the maximum coolant (helium) temperature and pressure are 1004 °C and 9.2 MPa respectively. The maximum fuel temperature is 1282 °C, this value still far below the fuel temperature limiting condition i.e. 1600 °C, its mean that the HTGR has a very good inherent safety system.

  6. 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.)

  7. Description of the advanced gas cooled type of reactor (AGR)

    International Nuclear Information System (INIS)

    Nonboel, E.

    1996-11-01

    The present report comprises a technical description of the Advanced Gas cooled Reactor (AGR), a reactor type which has only been built in Great Britain. 14 AGR reactors have been built, located at 6 different sites and each station is supplied with twin-reactors. The Torness AGR plant on the Lothian coastline of Scotland, 60 km east of Edinburgh, has been chosen as the reference plant and is described in some detail. Data on the other 6 stations, Dungeness B, Hinkely Point B, Hunterston G, Hartlepool, Heysham I and Heysham II, are given only in tables with a summary of design data. Where specific data for Torness AGR has not been available, corresponding data from other AGR plans has been used, primarily from Heysham II, which belongs to the same generation of AGR reactors. The information presented is based on the open literature. The report is written as a part of the NKS/RAK-2 subproject 3: 'Reactors in Nordic Surroundings', which comprises a description of nuclear power plants neighbouring the Nordic countries. (au) 11 refs

  8. Evaluation of plate type fuel options for small power reactors

    International Nuclear Information System (INIS)

    Andrzejewski, Claudio de Sa

    2005-01-01

    Plate type fuels are generally used in research reactor. The utilization of this kind of configuration improves significantly the overall performance fuel. The conception of new fuels for small power reactors based in plate-type configuration needs a complete review of the safety criteria originally used to conduce power and research reactor projects. In this work, a group of safety criteria is established for the utilization of plate-type fuels in small power reactors taking into consideration the characteristics of power and research reactors. The performance characteristics of fuel elements are strongly supported by its materials properties and the adopted configuration for its fissile particles. The present work makes an orientated bibliographic investigation searching the best material properties (structural materials and fuel compounds) related to the performance fuel. Looking for good parafermionic characteristics and manufacturing exequibility associated to existing facilities in national research centres, this work proposes several alternatives of plate type fuels, considering its utilization in small power reactors: dispersions of UO 2 in stainless steel, of UO 2 in zircaloy, and of U-Mo alloy in zircaloy, and monolithic plates of U-Mo cladded with zircaloy. Given the strong dependency of radiation damage with temperature increase, the safety criteria related to heat transfer were verified for all the alternatives, namely the DNBR; coolant temperature lower than saturation temperature; peak meat temperature to avoid swelling; peak fuel temperature to avoid meat-matrix reaction. It was found that all alternatives meet the safety criteria including the 0.5 mm monolithic U-Mo plate cladded with zircaloy. (author)

  9. Method of controlling power distribution in FBR type reactors

    International Nuclear Information System (INIS)

    Sawada, Shusaku; Kaneto, Kunikazu.

    1982-01-01

    Purpose: To attain the power distribution flattening with ease by obtaining a radial power distribution substantially in a constant configuration not depending on the burn-up cycle. Method: As the fuel burning proceeds, the radial power distribution is effected by the accumulation of fission products in the inner blancket fuel assemblies which varies the effect thereof as the neutron absorbing substances. Taking notice of the above fact, the power distribution is controlled in a heterogeneous FBR type reactor by varying the core residence period of the inner blancket assemblies in accordance with the charging density of the inner blancket assemblies in the reactor core. (Kawakami, Y.)

  10. Core construction in a pressure tube type heavy water reactor

    International Nuclear Information System (INIS)

    Ueda, Makoto; Aoki, Katsutada.

    1975-01-01

    Object: To replace a centrally positioned fuel assembly of a fuel assembly unit with a reactor controlling machinery to decrease a distance between the fuel assemblies thereby saving use of heavy water and enhancing economy. Structure: A centrally positioned fuel assembly of a fuel assembly unit, which is composed of a plurality of fuel assemblies orderly arranged in lattice fashion, is replaced with a reactor controlling members such as control rods, poison tubes and the like to provide an arrangement of lattice-free type fuel assembly, thus reducing the pitch as small as possible. (Kamimura, M.)

  11. Description of the magnox type of gas cooled reactor (MAGNOX)

    International Nuclear Information System (INIS)

    Jensen, S.E.; Nonboel, E.

    1999-05-01

    The present report comprises a technical description of the MAGNOX type of reactor as it has been build in Great Britain. The Magnox reactor is gas cooled (CO 2 ) with graphite moderators. The fuels is natural uranium in metallic form, canned with a magnesium alloy called 'Magnox'. The Calder Hall Magnox plant on the Lothian coastline of Scotland, 60 km east of Edinburgh, has been chosen as the reference plant and is described in some detail. Data on the other stations are given in tables with a summary of design data. Special design features are also shortly described. Where specific data for Calder Hall Magnox has not been available, corresponding data from other Magnox plants has been used. The information presented is based on the open literature. The report is written as a part of the NKS/RAK-2 sub-project 3: 'Reactors in Nordic Surroundings', which comprises a description of nuclear power plants neighbouring the Nordic countries. (au)

  12. After-heat removing system in FBR type reactor

    International Nuclear Information System (INIS)

    Ohashi, Yukio.

    1990-01-01

    The after-heat removing system of the present invention removes the after heat generated in a reactor core without using dynamic equipments such as pumps or blowers. There are disposed a first heat exchanger for heating a heat medium by the heat in a reactor container and a second heat exchanger situated above the first heat exchanger for spontaneously air-cooling the heat medium. Recycling pipeways connect the first and the second heat exchangers to form a recycling path for the heat medium. Then, since the second heat exchanger for spontaneously air-cooling the heat medium is disposed above the first heat exchanger and they are connected by the recycling pipeways, the heat medium can be circulated spontaneously. Accordingly, dynamic equipments such as pumps or blowers are no more necessary. As a result, the after-heat removing system of the FBR type reactor of excellent safety and reliability can be obtained. (I.S.)

  13. Perspective channel-type reactor with enhanced safety

    International Nuclear Information System (INIS)

    Adamov, E.O.; Grozdov, I.I.; Kuznetsov, S.P.; Petrov, A.A.; Rozhdestvensky, M.I.; Cherkashov, Yu.M.

    1994-01-01

    Following the search for new design solutions to develop within the framework of channel trends the reactor with enhanced safety the Research and Development Institute of Power Engineering has developed the design of the multiloop boiling water reactor (MKER). The MKER enhanced safety is attained when involving the inherent safety features, passive safety systems as well as the accident consequences confinement devices. The design realizes several advantages which are typical of the channel-type reactors, namely: The design desintegration simplifying the manufacture, control, equipment delivery and decreasing, versus the pressure vessel reactors, the accident effect if it proceeds in an explosive manner; small operating reactivity margin and fuel burnup increased due to continuous refuelling; fuel cycle flexibility allowing comparatively easily to adopt the reactor to the conjuncture of the country fuel balance; multiloop circuit of the main coolant which reduces the degree and effect of the accidents connected with the equipment and pipings rupture; monitoring of the channels and fuel assemblies leak-tightness. (orig.)

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

    International Nuclear Information System (INIS)

    Ortiz S, J.J.

    1998-01-01

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

  15. INTELIGENCIA Y RENDIMIENTO DEPORTIVO: UN ESTUDIO SOBRE LA INTELIGENCIA EMOCIONAL

    Directory of Open Access Journals (Sweden)

    Gerardo Araya Vargas

    2001-06-01

    Full Text Available Este estudio tuvo el propósito de determinar la correlación entre los índices de inteligencia tradicional (razonamiento analógico, C. I. e inteligencia emocional (C.E. con el rendimiento deportivo. Participaron 10 basketbolistas, entre los 17 y 25 años (media = 20.1 años, todas mujeres. Se les aplicó pruebas de C. I. (Raven y de C. E. (Goleman y luego se sometió a los sujetos a dos pruebas de precisión (tiro libre y tiro de tres puntos y posteriormente el entrenador evaluó mediante la Escala de Rendimiento Emocional Percibido por el Técnico, la capacidad de manejo emocional de las basketbolistas en situación de juego. El puntaje de C. E. se correlacionó significativamente (r=0.71; p < 0.05 con la precisión en el tiro de tres puntos. En los otros casos las correlaciones fueron bajas y no significativas. La evaluación del entrenador mostró (rbis = -0.87; p < 0.05 correlación significativa y negativa entre el índice C. E. y la percepción del efecto negativo de las emociones sobre el rendimiento, por tanto existe evidencia preliminar de que este índice podría ser valioso como predictor del rendimiento en circunstancias de alta exigencia.

  16. La inteligencia emocional y liderazgo escolar

    OpenAIRE

    João RUIVO; Sérgio PAES

    2015-01-01

    El fenómeno del liderazgo escolar, así como el de la inteligencia emocional, han despertado el interés de la comunidad científica y se ha traducido en una necesidad premiosa de comprender el impacto que puedan lograr en la vida de las escuelas. A partir de las características de la inteligencia emocional de los líderes de una organización escolar, este estudio de caso pretende describir las relaciones existentes entre la inteligencia emocional del liderazgo y la eficacia de ese mismo liderazg...

  17. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages

    International Nuclear Information System (INIS)

    Jurado P, M.; Martin del Campo M, C.

    2005-01-01

    In this work the main advantages and disadvantages of the installation of a new type of nuclear reactor different to the BWR type reactor in Mexico are presented. A revision of the advanced reactors is made that are at the moment in operation and of the advanced reactors that are in construction or one has already planned its construction in the short term. Specifically the A BWR and EPR reactors are analyzed. (Author)

  18. Primary system thermal-hydraulic simulation of a experimental pool type research fast reactor

    International Nuclear Information System (INIS)

    Borges, E.M.; Braz Filho, F.A.

    1993-01-01

    The first step of the Fast Reactor Program (REARA) is the design of an experimental reactor. To this end a 5 MW t pool type reactor was adapted. The objective of this work is to evaluate the reactor behaviour at the on set protected accidents. The program NALAP was used in this study and the results showed the outstanding safety margins that this reactor type presents inherently. (author)

  19. Calculation device for fuel power history in BWR type reactors

    International Nuclear Information System (INIS)

    Sakagami, Masaharu.

    1980-01-01

    Purpose: To enable calculations for power history and various variants of power change in the power history of fuels in a BWR type reactor or the like. Constitution: The outputs of the process computation for the nuclear reactor by a process computer are stored and the reactor core power distribution is judged from the calculated values for the reactor core power distribution based on the stored data. Data such as for thermal power, core flow rate, control rod position and power distribution are recorded where the changes in the power distribution exceed a predetermined amount, and data such as for thermal power and core flow rate are recorded where the changes are within the level of the predetermined amount, as effective data excluding unnecessary data. Accordingly, the recorded data are taken out as required and the fuel power history and the various variants in the fuel power are calculated and determined in a calculation device for fuel power history and variants for fuel power fluctuation. (Furukawa, Y.)

  20. Device for monitoring thermal operation margin in BWR type reactors

    International Nuclear Information System (INIS)

    Purpose: To extend the freedom of operation relative to the thermal limit for the fuel rods without imparing the reactor safety. Constitution: The monitoring system comprises a computing device for the plant operation conditions that computes the plant conditions based on the data signals obtained from each of various types of detectors for detecting the position of control rods inserted into the reactor core, neutron fluxes in the reactor core and the process amounts in the inner and the outer sides of the reactor cores, a thermal limit computing device that computes the thermal limit value in the operation based on the data outputted from the plant operation condition computer device, a transient condition thermal limit computing device that computes the thermal limit value in the transient changes of the conditions based on the data outputted from the plant operation condition computing device, and a thermal comparison device that compares the outputs of the thermal limit computing device and the transient thermal limit computing device. (Ikeda, J.)

  1. Temperature fluctuation reducing device for FBR type reactor

    International Nuclear Information System (INIS)

    Ootsuka, Fumio; Shiratori, Fumihiro.

    1991-01-01

    In existent FBR type reactors, since temperature fluctuation in the reactor upper portion has been inevitable, thermal fatigue may be caused possibly in reactor core upper mechanisms. Then, a valve is disposed to a control rod lower guide tube contained in a reactor container for automatically controlling the amount of passing coolants in accordance with the temperature of the passing coolants, to mix and control coolants passing through a fuel assembly in adjacent with the guide tube and coolants passing through the guide tube. Further, a rectification cylinder is disposed, in which a portion of coolants passing through the fuel assembly is caused to flow. An orifice is disposed to the cylinder with an exit being disposed to the upstream thereof such that the coolants not flown into the rectification cylinder and the coolants passing through the guide tube are mixed to moderate the temperature fluctuation. That is, a portion of the coolants flown into the rectification cylinder can not pass through the orifice, but flow backwardly to the upstream and is discharged out of the rectification cylinder from the coolants exit and mixed sufficiently with coolants passing through the guide tube. In this way, temperature fluctuation can be moderated. (N.H.)

  2. Determining reactor fuel type from continuous antineutrino monitoring

    OpenAIRE

    Jaffke, Patrick; Huber, Patrick

    2016-01-01

    We investigate the ability of an antineutrino detector to determine the fuel type of a reactor. A hypothetical 5t antineutrino detector is placed 25m from the core and measures the spectral shape and rate of antineutrinos emitted by fission fragments in the core for a number of 90 day periods. Our results indicate that four major fuel types can be differentiated from the variation of fission fractions over the irradiation time with a true positive probability of detection at 95%. In addition,...

  3. Determining Reactor Fuel Type from Continuous Antineutrino Monitoring

    Science.gov (United States)

    Jaffke, Patrick; Huber, Patrick

    2017-09-01

    We investigate the ability of an antineutrino detector to determine the fuel type of a reactor. A hypothetical 5-ton antineutrino detector is placed 25 m from the core and measures the spectral shape and rate of antineutrinos emitted by fission fragments in the core for a number of 90-d periods. Our results indicate that four major fuel types can be differentiated from the variation of fission fractions over the irradiation time with a true positive probability of detection at approximately 95%. In addition, we demonstrate that antineutrinos can identify the burnup at which weapons-grade mixed-oxide (MOX) fuel would be reduced to reactor-grade MOX, on average, providing assurance that plutonium-disposition goals are met. We also investigate removal scenarios where plutonium is purposefully diverted from a mixture of MOX and low-enriched uranium fuel. Finally, we discuss how our analysis is impacted by a spectral distortion around 6 MeV observed in the antineutrino spectrum measured from commercial power reactors.

  4. Reactor building seismic analysis of a PWR type - NPP

    International Nuclear Information System (INIS)

    Kakubo, Masao

    1983-01-01

    Earthquake engineering studies raised up in Brazil during design licensing and construction phases of Almirante Alvaro Alberto NPP, units 1 and 2. State of art of soil - structure interaction analysis with particular reference to the impedance function calculation analysis with particular reference to the impedance function calculation of a group of pile is presented in this M.Sc. Dissertation, as an example the reactor building dynamic response of a 1325 MWe NPP PWR type is calculated. The reactor building is supported by a pile foundation with 2002 end bearing piles. Upper and lower bound soil parameters are considered in order to observe their influence on dynamic response of structure. Dynamic response distribution on pile heads show pile-soil-pile interaction effects. (author)

  5. Method of planning fuel exchanges in FBR type reactors

    International Nuclear Information System (INIS)

    Urushihara, Hiroshi.

    1979-01-01

    Purpose: To simplify fuel exchange planning and ensure satisfactory fuel burning by simulating nuclear properties required for the fuel exchange in FBR type reactors with multi-variable algebraic expressions in integer linear planning method and conducting the decision for the optimum replacing positions capable of satisfying the aimed functions. Constitution: Number of new fuels to be loaded in each of the regions in the reactor core is determined previously for each of the fuel cycles based on a long term planning, positions for loading succeeding new fuel assemblies are forecast, nuclear properties and number of fuels to be exchanged required for the fuel exchange are respectively simulated with relevant algebraic expressions based on respective nuclear property data such as for neutron flux distribution, burning reactivity and uniform exchange for each of the forecast arrangement and present arrangement, and the loading positions for the new fuels are determined by the use of the integer linear planning method. (Horiuchi, T.)

  6. Apartes desde la inteligencia artificial

    Directory of Open Access Journals (Sweden)

    Luis Carlos Torres Soler

    1998-05-01

    Full Text Available El estudio y desarrollo de la inteligencia artificial no debe centrarse sólo en la creación de software o hardware que permita realizar procesos algorítmicos o heurísticos en el computador, de tal forma que produzcan soluciones óptimas y eficientes al resolver un problema complejo, ya sea de manejo de información o de toma de decisiones, o crear máquinas que tengan buena apariencia del ser humano; se debe, sobre todo, analizar la parte neurológica y sicológica que presenta el individuo al solucionar problemas. Además, es importante conocer la capacidad intelectual de la persona, de ahí la variedad de carreras profesionales que existen; no puede quedar por fuera de los sistemas inteligentes la concepción del amor o admiración.

  7. Solid-Core Heat-Pipe Nuclear Batterly Type Reactor

    International Nuclear Information System (INIS)

    Ehud Greenspan

    2008-01-01

    This project was devoted to a preliminary assessment of the feasibility of designing an Encapsulated Nuclear Heat Source (ENHS) reactor to have a solid core from which heat is removed by liquid-metal heat pipes (HP). Like the SAFE 400 space nuclear reactor core, the HPENHS core is comprised of fuel rods and HPs embedded in a solid structure arranged in a hexagonal lattice in a 3:1 ratio. The core is oriented horizontally and has a square rather cylindrical cross section for effective heat transfer. The HPs extend from the two axial reflectors in which the fission gas plena are embedded and transfer heat to an intermediate coolant that flows by natural-circulation. The HP-ENHS is designed to preserve many features of the ENHS including 20-year operation without refueling, very small excess reactivity throughout life, natural circulation cooling, walkaway passive safety, and robust proliferation resistance. The target power level and specific power of the HP-ENHS reactor are those of the reference ENHS reactor. Compared to previous ENHS reactor designs utilizing a lead or lead-bismuth alloy natural circulation cooling system, the HP-ENHS reactor offers a number of advantageous features including: (1) significantly enhanced passive decay heat removal capability; (2) no positive void reactivity coefficients; (3) relatively lower corrosion of the cladding (4) a core that is more robust for transportation; (5) higher temperature potentially offering higher efficiency and hydrogen production capability. This preliminary study focuses on five areas: material compatibility analysis, HP performance analysis, neutronic analysis, thermal-hydraulic analysis and safety analysis. Of the four high-temperature structural materials evaluated, Mo TZM alloy is the preferred choice; its upper estimated feasible operating temperature is 1350 K. HP performance is evaluated as a function of working fluid type, operating temperature, wick design and HP diameter and length. Sodium is the

  8. The utility of different reactor types for the research

    International Nuclear Information System (INIS)

    Stiennon, G.

    1983-01-01

    The report presents a general view of the use of the different belgian research reactor i.e. venus reactor, BR-1 reactor, BR-2 reactor and BR-3 reactor. Particular attention is given to the programmes which is in the interest of international collaboration. In order to reach an efficient utilization of such reactors they require a specialized personnel groups to deal with the irradiation devices and radioactive materials and post irradiation examinations, creating a complete material testing station. (A.J.)

  9. Fuel loading method to exchangeable reactor core of BWR type reactor and its core

    International Nuclear Information System (INIS)

    Koguchi, Kazushige.

    1995-01-01

    In a fuel loading method for an exchangeable reactor core of a BWR type reactor, at least two kinds of fresh fuel assemblies having different reactivities between axial upper and lower portions are preliminarily prepared, and upon taking out fuel assemblies of advanced combustion and loading the fresh fuel assemblies dispersingly, they are disposed so as to attain a predetermined axial power distribution in the reactor. At least two kinds of fresh fuel assemblies have a content of burnable poisons different between the axial upper portion and lower portions. In addition, reactivity characteristics are made different at a region higher than the central boundary and a region lower than the central boundary which is set within a range of about 6/24 to 16/24 from the lower portion of the fuel effective length. There can be attained axial power distribution as desired such as easy optimization of the axial power distribution, high flexibility, and flexible flattening of the power distribution, and it requires no special change in view of the design and has a good economical property. (N.H.)

  10. Radiation protection optimization in the PWR type reactor dismantling

    International Nuclear Information System (INIS)

    Hilmoine, R.

    1998-01-01

    The studies made at the international level for the PWR type reactors, give dosimetric evaluations about 10 to 15 h.Sv for an immediate dismantling and around three to four times lower for a delayed dismantling according to the storage time. The technical hypothesis, the ambient dosimetry, the time of occupational exposure and the radioactive wastes management are not clearly specified so, Electricite de France has undertaken a more exhaustive study that takes into account, the radiation protection dimension in its universality from a complete radiological characterization in a standard installation. (N.C.)

  11. The water desalination complex based on ABV-type reactor plant

    International Nuclear Information System (INIS)

    Panov, Yu.K.; Fadeev, Yu.P.; Vorobiev, V.M.; Baranaev, Yu.D.

    1997-01-01

    A floating nuclear desalination complex with two barges, one for ABV type reactor plant, with twin reactor 2 x 6 MW(e), and one for reverse osmosis desalination plant, was described. The principal specifications of the ABV type reactor plant and desalination barge were given. The ABV type reactor has a traditional two-circuit layout using an integral type reactor vessel with all mode natural convection of primary coolant. The desalted water cost was estimated to be around US $0.86 per cubic meter. R and D work has been performed and preparations for commercial production are under way. (author)

  12. Liquid-metal-gas heat exchanger for HTGR type reactors

    International Nuclear Information System (INIS)

    Werth, G.

    1980-01-01

    The aim of this study is to investigate the heat transfer characteristics of a liquid metal heat exchanger (HE) for a helium-cooled high temperature reactor. A tube-type heat exchanger is considered as well as two direct exchangers: a bubble-type heat exchanger and a heat exchanger according to the spray principle. Experiments are made in order to determine the gas content of bubble-type heat exchangers, the dependence of the droplet diameter on the nozzle diameter, the falling speed of the droplets, the velocity of the liquid jet, and the temperature variation of liquid jets. The computer codes developed for HE calculation are structured so that they may be used for gas/liquid HE, too. Each type of HE that is dealt with is designed by accousting for a technical and an economic assessment. The liquid-lead jet spray is preferred to all other types because of its small space occupied and its simple design. It shall be used in near future in the HTR by the name of lead/helium HE. (GL) [de

  13. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  14. Consideration of BORAX-type reactivity accidents applied to research reactors

    International Nuclear Information System (INIS)

    Couturier, Jean; Meignen, Renaud; Bourgois, Thierry; Biaut, Guillaume; Mireau, Jean-Pierre; Natta, Marc

    2011-01-01

    Most of the research reactors discussed in this document are pool-type reactors in which the reactor vessel and some of the reactor coolant systems are located in a pool of water. These reactors generally use fuel in plate assemblies formed by a compact layer of uranium (or U 3 Si 2 ) and aluminium particles, sandwiched between two thin layers of aluminium serving as cladding. The fuel melting process begins at 660 deg. C when the aluminium melts, while the uranium (or U 3 Si 2 ) particles may remain solid. The accident that occurred in the American SL-1 reactor in 1961, together with tests carried out in the United States as of 1954 in the BORAX-1 reactor and then, in 1962, in the SPERT-1 reactor, showed that a sudden substantial addition of reactivity in this type of reactor could lead to explosive mechanisms caused by degradation, or even fast meltdown, of part of the reactor core. This is what is known as a 'BORAX-type' accident. The aim of this document is first to briefly recall the circumstances of the SL-1 reactor accident, the lessons learned, how this operational feedback has been factored into the design of various research reactors around the world and, second, to describe the approach taken by France with regard to this type of accident and how, led by IRSN, this approach has evolved in the last decade. (authors)

  15. Installation of a new type of nuclear reactor in Mexico: advantages and disadvantages; Instalacion de un nuevo tipo de reactor nuclear en Mexico: ventajas y desventajas

    Energy Technology Data Exchange (ETDEWEB)

    Jurado P, M.; Martin del Campo M, C. [FI-UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: mjp_green@hotmail.com

    2005-07-01

    In this work the main advantages and disadvantages of the installation of a new type of nuclear reactor different to the BWR type reactor in Mexico are presented. A revision of the advanced reactors is made that are at the moment in operation and of the advanced reactors that are in construction or one has already planned its construction in the short term. Specifically the A BWR and EPR reactors are analyzed. (Author)

  16. Leak detector for a steam generator in FBR type reactors

    International Nuclear Information System (INIS)

    Miyaji, Nobuyoshi.

    1979-01-01

    Purpose: To facilitate maintenance for liquid leak detectors such as exchange of nickel membrane sensors during operation in a sodium-cooled fbr type reactor. Constitution: A pipeway capable of supplying a cover gas such as argon into the cylinder of a hydrogen detector containing a nickel membrane sensor is provided in a liquid leak detector constituting a part of a by-pass loop. The pipeway is also adapted to be evacuated. A pipeway and a small sodium tank for drain use are provided on the side of the by-pass loop near valves. Then, after closing the inlet and outlet valves to disconnect the by-pass loop from the sodium main pipeway, the cover gas is supplied to drive liquid sodium to the drain tank. After the drain of the liquid sodium, the sensor can be replaced. (Ikeda, J.)

  17. Inteligent control system for a CANDU 600 type reactor process

    International Nuclear Information System (INIS)

    Venescu, B.; Zevedei, D.; Jurian, M.; Venescu, R.

    2013-01-01

    The present paper is set on presenting a highly intelligent configuration, capable of controlling, without the need of the human factor, a complete nuclear power plant type of system, giving it the status of an autonomous system. The urge for such a controlling system is justified by the amount of drawbacks that appear in real life as disadvantages, loses and sometimes even inefficiency in the current controlling and comanding systems of the nuclear reactors. The application stands in the comand sent from the auxiliary feedwater flow control valves to the steam generators. As an environment fit for development I chose Matlab Simulink to simulate the behaviour of the process and the adjusted system. Comparing the results obtained after the fuzzy regulation with those obtained after the classical regulation, we can demonstrate the necessity of implementing artificial intelligence techniques in nuclear power plants and we can agree to the advantages of being able to control everything automatically. (authors)

  18. Liquid-poison type power controlling device for nuclear reactor

    International Nuclear Information System (INIS)

    Horiuchi, Tetsuo; Yamanari, Shozo; Sugisaki, Toshihiko; Goto, Hiroshi.

    1981-01-01

    Purpose: To improve the safety and the operability of a nuclear reactor by adjusting the density of liquid poison. Constitution: The thermal expansion follow-up failure between cladding and a pellet upon abrupt and local variations of the power is avoided by adjusting the density of liquid poison during ordinary operation in combination with a high density liquid poison tank and a filter and smoothly controlling the reactor power through a pipe installed in the reactor core. The high density liquid poison is abruptly charged in to the reactor core under relatively low pressure through the tube installed in the reactor core at the time of control rod insertion failure in an accident, thereby effectively shutting down the reactor and improving the safety and the operability of the reactor. (Yoshihara, H.)

  19. Development and study of a control and reactor shutdown device for FBR-type reactors with a modified open core

    International Nuclear Information System (INIS)

    Goswami, S.

    1983-01-01

    The doctoral thesis at hand presents a newly designed control and shutdown device to be used for output control and fast shutdown of modified open core FBR-type reactors. The task was the design of a new control and shutdown device having economic and operation advantages, using reactor components time-tested under reactor conditions. This control and shutdown device was adapted to the specific needs concerning dimensions and design. The actuation is based on the magnetic-jack principle, which has been upgraded for the purpose. The principle is now combined with pneumatic acceleration. The improvements mainly concern a smaller number of piece parts and system simplification. (orig./RW) [de

  20. La inteligencia emocional y liderazgo escolar

    Directory of Open Access Journals (Sweden)

    João RUIVO

    2015-10-01

    Full Text Available El fenómeno del liderazgo escolar, así como el de la inteligencia emocional, han despertado el interés de la comunidad científica y se ha traducido en una necesidad premiosa de comprender el impacto que puedan lograr en la vida de las escuelas. A partir de las características de la inteligencia emocional de los líderes de una organización escolar, este estudio de caso pretende describir las relaciones existentes entre la inteligencia emocional del liderazgo y la eficacia de ese mismo liderazgo escolar, según los parámetros y dominios definidos por la Inspección General de Educación en Portugal. Para alcanzar ese objetivo se recurrió a dos tipos de técnicas de recogida de datos, la pregunta por cuestionario y el análisis documental. Por un lado, la aplicación de cuestionarios de autodescripción posibilitó la caracterización de la inteligencia emocional de los sujetos encuestados. Por otro, el análisis documental nos permitió la exploración y descripción de relaciones entre aquellas características y la eficacia del liderazgo. Los resultados expresan la existencia de relaciones entre las diferentes dimensiones de la inteligencia emocional, la calidad de las relaciones interpersonales y la eficacia del liderazgo de los grupos escolares. 

  1. Effects of Thermal Aging on Type 316H Stainless Steel for Reactor Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Ji Hyun; Hong, Seok Min; Lee, Bong Sang; Koo, Gyeong Hoi [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    Type 316H stainless steel is a prime candidate for reactor vessel material of sodium-cooled fast reactor (SFR) which has been developed as one of the Gen IV nuclear reactors in Korea. The reactor vessel steel will be exposed to higher temperature for an extended design life time. It is known that austenitic stainless steel such as Type 316H stainless steel shows excellent toughness and adequate strength at a moderate temperature. However, the previous researches reported the mechanical properties of Type 316H stainless weld would be deteriorated by the aging at the elevated temperature range.

  2. Seismic responses of a pool-type fast reactor with different core support designs

    International Nuclear Information System (INIS)

    Wu, Ting-shu; Seidensticker, R.W.

    1989-01-01

    In designing the core support system for a pool-type fast reactor, there are many issues which must be considered in order to achieve an optimum and balanced design. These issues include safety, reliability, as well as costs. Several design options are possible to support the reactor core. Different core support options yield different frequency ranges and responses. Seismic responses of a large pool-type fast reactor incorporated with different core support designs have been investigated. 4 refs., 3 figs

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

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  4. High yields of hydrogen production from methanol steam reforming with a cross-U type reactor.

    Science.gov (United States)

    Zhang, Shubin; Zhang, Yufeng; Chen, Junyu; Zhang, Xuelin; Liu, Xiaowei

    2017-01-01

    This paper presents a numerical and experimental study on the performance of a methanol steam reformer integrated with a hydrogen/air combustion reactor for hydrogen production. A CFD-based 3D model with mass and momentum transport and temperature characteristics is established. The simulation results show that better performance is achieved in the cross-U type reactor compared to either a tubular reactor or a parallel-U type reactor because of more effective heat transfer characteristics. Furthermore, Cu-based micro reformers of both cross-U and parallel-U type reactors are designed, fabricated and tested for experimental validation. Under the same condition for reforming and combustion, the results demonstrate that higher methanol conversion is achievable in cross-U type reactor. However, it is also found in cross-U type reactor that methanol reforming selectivity is the lowest due to the decreased water gas shift reaction under high temperature, thereby carbon monoxide concentration is increased. Furthermore, the reformed gas generated from the reactors is fed into a high temperature proton exchange membrane fuel cell (PEMFC). In the test of discharging for 4 h, the fuel cell fed by cross-U type reactor exhibits the most stable performance.

  5. High yields of hydrogen production from methanol steam reforming with a cross-U type reactor

    Science.gov (United States)

    Zhang, Shubin; Chen, Junyu; Zhang, Xuelin; Liu, Xiaowei

    2017-01-01

    This paper presents a numerical and experimental study on the performance of a methanol steam reformer integrated with a hydrogen/air combustion reactor for hydrogen production. A CFD-based 3D model with mass and momentum transport and temperature characteristics is established. The simulation results show that better performance is achieved in the cross-U type reactor compared to either a tubular reactor or a parallel-U type reactor because of more effective heat transfer characteristics. Furthermore, Cu-based micro reformers of both cross-U and parallel-U type reactors are designed, fabricated and tested for experimental validation. Under the same condition for reforming and combustion, the results demonstrate that higher methanol conversion is achievable in cross-U type reactor. However, it is also found in cross-U type reactor that methanol reforming selectivity is the lowest due to the decreased water gas shift reaction under high temperature, thereby carbon monoxide concentration is increased. Furthermore, the reformed gas generated from the reactors is fed into a high temperature proton exchange membrane fuel cell (PEMFC). In the test of discharging for 4 h, the fuel cell fed by cross-U type reactor exhibits the most stable performance. PMID:29121067

  6. El impacto de la Inteligencia Emocional en el bienestar personal

    OpenAIRE

    Fernández-Berrocal, Pablo

    2013-01-01

    La inteligencia emocional es concebida como una inteligencia genuina basada en el uso adaptativo de las emociones de manera que el individuo pueda solucionar problemas y adaptarse de forma eficaz al medio que le rodea (Mayer y Salovey, 1997). Mayer y Salovey, los padres del concepto, definen la inteligencia emocional como “la capacidad para percibir, valorar y expresar las emociones con exactitud; la capacidad para acceder y generar sentimientos que faciliten el pensamiento; la capacidad ...

  7. Coolant distribution device on reactor core side of HTGR type reactor

    International Nuclear Information System (INIS)

    Masuba, Yoshitaka.

    1993-01-01

    The coolant distribution device comprises an annular main body and a pressure loss source member having a plurality of blow ports perforated at positions equally dividing the circumference of the main body. The coolant distribution device is disposed to the outer circumference of a plurality of support columns disposed between the reactor core support plate and a rectification plate at a reactor floor portion. Coolants uprising in the reactor core and flowing under heating to a reactor floor portion are blown out from main cooling system pipelines and auxiliary cooling system pipelines, passed through the gap of the reactor core support plate and the rectification plate and sealed by the pressure loss source member. Since the difference of a speed head caused by geometrical shape in the circumferential direction of a flow channel is reduced as a pressure loss, the pressure in the pressure loss source member is kept uniform. Accordingly, a uniform amount of coolants is distributed from the blow ports of the pressure loss source member to the side of the reactor core of the reactor floor portion, to cool the outer circumference of the reactor core uniformly. (I.N.)

  8. Thorium Fuel Utilization Analysis on Small Long Life Reactor for Different Coolant Types

    Science.gov (United States)

    Permana, Sidik

    2017-07-01

    A small power reactor and long operation which can be deployed for less population and remote area has been proposed by the IAEA as a small and medium reactor (SMR) program. Beside uranium utilization, it can be used also thorium fuel resources for SMR as a part of optimalization of nuclear fuel as a “partner” fuel with uranium fuel. A small long-life reactor based on thorium fuel cycle for several reactor coolant types and several power output has been evaluated in the present study for 10 years period of reactor operation. Several key parameters are used to evaluate its effect to the reactor performances such as reactor criticality, excess reactivity, reactor burnup achievement and power density profile. Water-cooled types give higher criticality than liquid metal coolants. Liquid metal coolant for fast reactor system gives less criticality especially at beginning of cycle (BOC), which shows liquid metal coolant system obtains almost stable criticality condition. Liquid metal coolants are relatively less excess reactivity to maintain longer reactor operation than water coolants. In addition, liquid metal coolant gives higher achievable burnup than water coolant types as well as higher power density for liquid metal coolants.

  9. Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ehud Greenspan

    2008-09-30

    This project was devoted to a preliminary assessment of the feasibility of designing an Encapsulated Nuclear Heat Source (ENHS) reactor to have a solid core from which heat is removed by liquid-metal heat pipes (HP).

  10. Startup method for natural convection type nuclear reactor

    International Nuclear Information System (INIS)

    Utsuno, Hideaki.

    1993-01-01

    In a nuclear reactor started by natural convection, no sufficient stability margin can be ensured upon start up. Then, in the present invention, a deaerating operation is conducted before start-up of the reactor, then control rods are withdrawn after conducting the deaerating operation and temperature and pressure are raised by nuclear heating, to obtain a rated power. As a result, reactor power and subcooling at the inlet of the reactor core are within a range of lower than a geysering forming region, thereby enabling to prevent occurence of geysering inherent to the start-up of operation in a natural convection state, shorten the start-up time, as well as remove oxygen dissolved in coolants. (N.H.)

  11. Nonlinear punctual dynamic applied to simulation of PWR type reactors

    International Nuclear Information System (INIS)

    Cysne, F.S.

    1978-01-01

    In order to study some kinds of nuclear reactor accidents, a simulation is made using the punctual kinetics model to the reactor core. The following integration methods are used: Hansen's method in which a linearization is made and C S M P using a variable interval fourth-order Runge Kutta method. The results were good and were compared with those obtained by the code Dinamica I which uses a finite difference integration method of backward kind. (author)

  12. Introducci??n a la Inteligencia en el ??mbito de Seguridad y Defensa

    OpenAIRE

    Jord??n Enamorado, Javier

    2015-01-01

    Este an??lisis, con finalidad eminentemente did??ctica, ofrece una introducci??n conceptual a la Inteligencia en materia de seguridad y defensa. Al mismo tiempo, desarrolla dos temas relacionados. La relaci??n entre Inteligencia y toma de decisiones pol??tica, e Inteligencia y secreto. Finaliza con una breve taxonom??a de los principales tipos de Inteligencia.

  13. Inteligencia Emocional para tiempos de crisis

    OpenAIRE

    Fernández-Berrocal, Pablo

    2014-01-01

    La Inteligencia Emocional se concibe como un conjunto de habilidades, tanto básicas como complejas, dirigidas a “unificar las emociones y el razonamiento”, esto es, usar las emociones para facilitar el razonamiento y los procesos de pensamiento, y usar nuestro razonamiento para pensar de forma inteligente acerca de nuestras emociones (Mayer y Salovey, 1997). En concreto, la IE se define como una habilidad mental que incluye “la capacidad para percibir, valorar y expresar las emociones con...

  14. Inteligencia social en el sector laboral colombiano

    OpenAIRE

    2012-01-01

    La inteligencia social en el trabajo es la competencia que desarrollan las personas para lograr acceder y realizarse laborando, está investigación busca determinar cuáles son los recursos que emplea el trabajador para ingresar y permanecer en el mercado laboral tanto formal como informal. Las condiciones del mercado laboral colombiano, hacen que subsistan y complementen el empleo y desempleo. La incapacidad del sector productivo y de servicios de generar empleo genera un deterioro de la ca...

  15. Servicios de inteligencia y lucha antiterrorista

    Directory of Open Access Journals (Sweden)

    Jordán Enamorado, Javier

    2005-01-01

    Full Text Available El terrorismo, y más concretamente el yihadismo global, se ha convertido en una de las principales amenazas violentas contra la seguridad de Estados Unidos y de Europa. Como consecuencia ha pasado a ocupar un lugar prioritario entre los temas de interés de los servicios de inteligencia. Este artículo describe en un primer epígrafe las características esenciales del terrorismo yihadista, con objeto de subrayar las similitudes y diferencias que plantea en comparación con otros tipos de terrorismo. Seguidamente, analiza de qué manera la naturaleza particular de este terrorismo afecta al desarrollo de las tareas de propias de los servicios, repasando cada una de las fases del ciclo de inteligencia. Por último, termina con una serie de consideraciones sobre la adaptación del Centro Nacional de Inteligencia español a la lucha contra el yihadismo global.…

  16. Fuel assemblies for PWR type reactors: fuel rods, fuel plates. CEA work presentation

    International Nuclear Information System (INIS)

    Delafosse, Jacques.

    1976-01-01

    French work on PWR type reactors is reported: basic knowledge on Zr and its alloys and on uranium oxide; experience gained on other programs (fast neutron and heavy water reactors); zircaloy-2 or zircaloy-4 clad UO 2 fuel rods; fuel plates consisting of zircaloy-2 clad UO 2 squares of thickness varying between 2 and 4mm [fr

  17. The development of the physical conceptions of the FBR type reactors control methods

    International Nuclear Information System (INIS)

    Matveev, V.I.; Ivanov, A.P.

    1984-01-01

    The physical concepts and specific problems of the control elements for LMFBR type reactors are discussed in this paper. Typical temperature coefficient of reactivity, its dependency on reactor power and burnup level are given. The authors give us the most advisable methods of the reactivity coefficient compensation

  18. Reactor power automatically controlling method and device for BWR type reactor

    International Nuclear Information System (INIS)

    Murata, Akira; Miyamoto, Yoshiyuki; Tanigawa, Naoshi.

    1997-01-01

    For an automatic control for a reactor power, when a deviation exceeds a predetermined value, the aimed value is kept at a predetermined value, and when the deviation is decreased to less than the predetermined value, the aimed value is increased from the predetermined value again. Alternatively, when a reactor power variation coefficient is decreased to less than a predetermine value, an aimed value is maintained at a predetermined value, and when the variation coefficient exceeds the predetermined value, the aimed value is increased. When the reactor power variation coefficient exceeds a first determined value, an aimed value is increased to a predetermined variation coefficient, and when the variation coefficient is decreased to less than the first determined value and also when the deviation between the aimed value and an actual reactor power exceeds a second determined value, the aimed value is maintained at a constant value. When the deviation is increased or when the reactor power variation coefficient is decreased, since the aimed value is maintained at predetermined value without increasing the aimed value, the deviation is not increased excessively thereby enabling to avoid excessive overshoot. (N.H.)

  19. 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.)

  20. EDF's (Electricite de France) in service control for GCR type reactor vessels

    International Nuclear Information System (INIS)

    Douillet, M.G.

    1979-01-01

    This paper presents the performance of the data acquisition and processing systems developed by the French EDF for controlling and testing the mechanical properties (thermal stress, deformations, cracks,...) of prestressed concrete vessels for GCR type reactors

  1. 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.)

  2. Simulation test of PIUS-type reactor with large scale experimental apparatus

    International Nuclear Information System (INIS)

    Tamaki, M.; Tsuji, Y.; Ito, T.; Tasaka, K.; Kukita, Yutaka

    1995-01-01

    A large scale experimental apparatus for simulating the PIUS-type reactor has been constructed keeping the volumetric scaling ratio to the realistic reactor model. Fundamental experiments such as a steady state operation and a pump trip simulation were performed. Experimental results were compared with those obtained by the small scale apparatus in JAERI. We have already reported the effectiveness of the feedback control for the primary loop pump speed (PI control) for the stable operation. In this paper this feedback system is modified and the PID control is introduced. This new system worked well for the operation of the PIUS-type reactor even in a rapid transient condition. (author)

  3. Neutronics comparative analysis of plate-type research reactor using deterministic and stochastic methods

    International Nuclear Information System (INIS)

    Liu, Shichang; Wang, Guanbo; Wu, Gaochen; Wang, Kan

    2015-01-01

    Highlights: • DRAGON and DONJON are applied and verified in calculations of research reactors. • Continuous-energy Monte Carlo calculations by RMC are chosen as the references. • “ECCO” option of DRAGON is suitable for the calculations of research reactors. • Manual modifications of cross-sections are not necessary with DRAGON and DONJON. • DRAGON and DONJON agree well with RMC if appropriate treatments are applied. - Abstract: Simulation of the behavior of the plate-type research reactors such as JRR-3M and CARR poses a challenge for traditional neutronics calculation tools and schemes for power reactors, due to the characteristics of complex geometry, highly heterogeneity and large leakage of the research reactors. Two different theoretical approaches, the deterministic and the stochastic methods, are used for the neutronics analysis of the JRR-3M plate-type research reactor in this paper. For the deterministic method the neutronics codes DRAGON and DONJON are used, while the continuous-energy Monte Carlo code RMC (Reactor Monte Carlo code) is employed for the stochastic approach. The goal of this research is to examine the capability of the deterministic code system DRAGON and DONJON to reliably simulate the research reactors. The results indicate that the DRAGON and DONJON code system agrees well with the continuous-energy Monte Carlo simulation on both k eff and flux distributions if the appropriate treatments (such as the ECCO option) are applied

  4. Stellarator-type magnetic system for a research fusion reactor

    International Nuclear Information System (INIS)

    Kotenko, V.G.; Romanov, S.S.; Bjesjedyin, M.T.

    2001-01-01

    To create the plasma confinement region in a research fusion reactor (RFR),the possibility of using a toroidal magnetic field formed in the l=2,m=1 torsatron along with a reversed additional longitudinal magnetic field is shown.The principal difference of RFR from existing designs is greater distance between the plasma confinement region and the 1st wall, r p1 /r w <<1

  5. Dynamic power behavior of a PWR type nuclear reactor

    International Nuclear Information System (INIS)

    Moreira, F.J.

    1984-01-01

    A methodology for the power level evaluation (dynamic behavior) in a Pressurized Water Reactor, during a transient is developed, by solving the point kinetic equation related to the control rod insertion effects and fuel or moderator temperature 'feed-back'. A new version of the thermal-hydraulic code COBRA III P/MIT, is used. In this new version was included, as an option, the methodology developed. (E.G.) [pt

  6. Comparison of performance indicators of different types of reactors based on ISOE database

    International Nuclear Information System (INIS)

    Janzekovic, H.; Krizman, M.

    2005-01-01

    The optimisation of the operation of a nuclear power plant (NPP) is a challenging issue due to the fact that besides general management issues, a risk associated to nuclear facilities should be included. In order to optimise the radiation protection programmes in around 440 reactors in operation with more than 500 000 monitored workers each year, the international exchange of performance indicators (PI) related to radiation protection issues seems to be essential. Those indicators are a function of a type of a reactor as well as the age and the quality of the management of the reactor. in general three main types of radiation protection PI could be recognised. These are: occupational exposure of workers, public exposure and management of PI related to radioactive waste. The occupational exposure could be efficiently studied using ISOC database. The dependence of occupational exposure on different types of reactors, e.g. PWR, BWR, are given, analysed and compared. (authors)

  7. Coolant make-up device for BWR type reactor

    International Nuclear Information System (INIS)

    Sasagawa, Hiroshi.

    1994-01-01

    In a coolant make-up device, an opening of a pressure equalizing pipeline in a pressure vessel is disposed in coolants above a reactor core and below a usual fluctuation range of a reactor vessel water level. Further, a float check valve is disposed to the pressure equalizing pipeline for preventing coolants in the pressure vessel flowing into the pipeline. If the water level in the pressure vessel is lowered than the setting position for the float check valve, the float drops by its own weight to open the opening of the pressure equalizing pipeline. Then, steams in the pressure vessel are flown into the pipeline, to equalize the pressure between a coolant storage tank and the pressure vessel of the reactor. Coolants in the coolant storage tank is injected to the pressure vessel by way of the water injection pipeline due to the difference of the pressure head between the water level in the coolants storage tank and the water level in the pressure vessel. If the coolants are lowered than the setting position for the float check value, the float check valve does not close unless the water level is recovered to the setting position for the float valve and, accordingly, the coolant make-up is continued. (N.H.)

  8. Servicios de inteligencia y lucha antiterrorista

    OpenAIRE

    Jordán Enamorado, Javier

    2005-01-01

    El terrorismo, y más concretamente el yihadismo global, se ha convertido en una de las principales amenazas violentas contra la seguridad de Estados Unidos y de Europa. Como consecuencia ha pasado a ocupar un lugar prioritario entre los temas de interés de los servicios de inteligencia. Este artículo describe en un primer epígrafe las características esenciales del terrorismo yihadista, con objeto de subrayar las similitudes y diferencias que plantea en comparación con otros tipos d...

  9. La inteligencia emocional en las instituciones educativas

    Directory of Open Access Journals (Sweden)

    Ileana Vargas-Jiménez

    2004-12-01

    Full Text Available Se pretende con el siguiente artículo reflexionar acerca de la importancia de la inteligencia emocional y cómo esta puede ser un instrumento útil para la labor del maestro (a qué es y cuáles son los componentes, así como algunas estrategias útiles para implementar dentro del salón de clases. Finalmente en el artículo se señala cómo impactan en las organizaciones especialmente en lo que tiene que ver con cambio organizacional, resolución de conflictos y liderazgo.

  10. Accident analysis for new reactor concepts and VVER type reactor design with advanced fuel. STC with Russia. Final report

    International Nuclear Information System (INIS)

    Grundmann, U.; Kliem, S.; Mittag, S.; Rohde, U.; Seidel, A.

    2000-10-01

    In the frame of a project on scientific-technical cooperation funded by BMBF/BMWi, the 3D reactor dynamics code DYN3D developed at Forschungszentrum Rossendorf (FZR), has been transferred to the Institute of Physics and Power Engineering (IPPE) Obninsk in Russia and integrated into the software package of IPPE. DYN3D has been coupled to a thermohydraulic system code used in IPPE making available 3D neutron kinetics within this software package. A new macroscopic cross section library has been created using a modified version of the WIMS/D4 code. This library includes data for modernized fuel design containing burnable absorbers in different concentrations, which is tested in VVER-1000 type reactors. The cross section library has been connected to DYN3D. Calculations were performed to check the library in comparison with other data libraries and codes. The code DYN3D and the coupled 3D neutron kinetics/thermal hydraulics code system were used to perform analyses of Anticipated Transients Without Scram (ATWS) for the reactor design ABV-67, an integral reactor concept with small power developed under participation of IPPE. The fluid dynamics code DINCOR developed at IPPE was transferred to FZR. It was used in validation calculations on test problems for the short-term core melt behaviour (CORVIS experiments). (orig.) [de

  11. Fast spectrum space reactor sizing code for calandria-type cores (CORSCO Code)

    Science.gov (United States)

    Specht, Eugene R.; Villalobos, Antonio

    1991-01-01

    The CORSCO code rapidly sizes reactor cores that have calandria-type geometry. The fuel configuration modeled is a large ceramic zone that contains numerous small cylindrical coolant channels spaced apart with a triangular pitch. A minimum reactor weight is obtained for a fixed set of constraints (peak fuel temperature, peak coolant velocity, etc.) by obtaining a unique solution to a set of five thermal/hydraulic equations, as well as a required excess reactivity which is specified by a core size dependent one-group criticality expression. Typical results are shown for a W-Re/UN cermet-fueled, lithium-cooled space reactor over a power range of 25 to 100 MWt. Reactor sensitivity coefficients are also shown for changes in reactor weight and number of coolant channels due to changes in core thermal/hydraulic constraints.

  12. Behavior of Type 316 stainless steel under simulated fusion reactor irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Wiffen, F.W.; Maziasz, P.J.; Bloom, E.E.; Stiegler, J.O.; Grossbeck, M.L.

    1978-05-01

    Fusion reactor irradiation response in alloys containing nickel can be simulated in thermal-spectrum fission reactors, where displacement damage is produced by the high-energy neutrons and helium is produced by the capture of two thermal neutrons in the reactions: /sup 58/Ni + n ..-->.. /sup 59/Ni + ..gamma..; /sup 59/Ni + n ..-->.. /sup 56/Fe + ..cap alpha... Examination of type 316 stainless steel specimens irradiated in HFIR has shown that swelling due to cavity formation and degradation of mechanical properties are more severe than can be predicted from fast reactor irradiations, where the helium contents produced are far too low to simulate fusion reactor service. Swelling values are greater and the temperature dependence of swelling is different than in the fast reactor case.

  13. Sloshing and fluid-structure interaction in a 400-MWe pool-type advanced fast reactor

    International Nuclear Information System (INIS)

    Ma, D.C.; Gvildys, J.; Chang, Y.W.

    1987-01-01

    This paper describes the seismic analysis of a 400-MWe advanced fast reactor under 0.3 g SSE ground excitation. Two types of analyses are performed - the sloshing analysis and the fluid-structure interaction analysis. In the sloshing analysis, the sloshing frequency and wave patterns are calculated. The maximum wave height and the sloshing forces exerted on the submerged components and the primary tank are evaluated. In the fluid-structure interaction analysis, the maximum horizontal acceleration for the reactor core and the relative displacement between the reactor core and UIS are examined. The fluid-coupling phenomena between various components are investigated. Seismic stresses at critical areas are examined. The results obtained from this study are very useful to the design of the advanced reactors. Meanwhile, the computer code FLUSTR-ANL has proved to be a useful analytical tool for assessing the complicated seismic fluid-structure interactions and sloshing in the fast reactor systems. 10 refs., 25 figs

  14. Inteligencia emocional y afrontamiento del estrés

    OpenAIRE

    Gutierrez Villarreal, Jorge Ivan; Sanabria Cuervo, Diego Felipe

    2014-01-01

    El objetivo principal de este trabajo es realizar una revisión teórica de los estudios que han elaborado un análisis acerca de la Inteligencia Emocional con la capacidad para afrontar situaciones generadoras de estrés. Los diferentes estudios muestran que niveles altos en Inteligencia Emocional se relacionan con estrategias de afrontamiento basadas en el análisis y resolución de conflictos, mientras que niveles bajos de inteligencia emocional se relacionan con estrategias de afrontamiento ba...

  15. Desarrollo de la inteligencia interpersonal desde la psicomotricidad

    OpenAIRE

    Bordas Aja, Natalia

    2015-01-01

    RESUMEN El presente Trabajo Fin de Grado pretende mostrar la relación entre la inteligencia interpersonal y la actividad motriz en la etapa de educación infantil. Para ello, en primer lugar, se recuperan algunas de las teorías de grandes autores sobre la psicomotricidad. En segundo lugar, se presenta un apartado sobre el concepto inteligencia, su evolución y la teoría de las Inteligencias Múltiples. Y en tercer lugar, se parte de todo lo expuesto previamente para plantear una propuesta prácti...

  16. La inteligencia emocional y el rendimiento académico

    OpenAIRE

    Sandoval, M.; Castro, R.

    2016-01-01

    A partir de que Goleman la da a conocer en los años 90´s, se ha explorado, y realizado investigación sobre la inteligencia emocional (I.E.); en el ámbito académico hay múltiples trabajos que afirman que existe una correlación entre dicha inteligencia y el rendimiento académico. Para Salovey et al. Inteligencia emocional es un conjunto de competencias que abarca la evaluación, expresión y uso de emociones, para facilitar las actividades cognitivas, el conocimiento acerca de las emociones y la ...

  17. El compromiso organizacional como predictor de la inteligencia emocional

    Directory of Open Access Journals (Sweden)

    Carmen M. Salvador-Ferrer

    2012-01-01

    Full Text Available El propósito de este estudio consiste en analisar minuciosamente la relación entre el compromiso de los trabajadores y la inteligencia emocional. Para ello, se expone una investigación que incluye sendas variables. Se obtuvieron datos de 165 trabajadores de una empresa. Además, se plantea un modelo predictivo de la inteligencia emocional, para ponerlo a prueba se aplica un análisis de ecuaciones estructurales. En este sentido, los datos vienen a reflejar el gran poder predictivo que tiene el compromiso normativo sobre la inteligencia emocional.

  18. Personalidad, inteligencia emocional y estilos de afrontamiento en los conciliadores de la ciudad de Arequipa

    Directory of Open Access Journals (Sweden)

    Walter Lizandro Arias Gallegos

    2016-06-01

    Full Text Available RESUMEN: El presente estudio analiza las características psicológicas de un grupo de 26 conciliadores de la ciudad de Arequipa. Para ello se ha evaluado la personalidad con el Inventario de Personalidad de Eysenck, los estilos de afrontamiento con el Cuestionario de Modos de Afrontamiento de Lazarus y Folkman, la inteligencia emocional con el Cuestionario de Inteligencia Emocional y para valorar algunas manifestaciones clínicas de la personalidad se utilizó el MINI-MULT. Los resultados indican que los conciliadores de Arequipa tienen un tipo de personalidad sanguíneo de manera predominante, inteligencia emocional es superior, y usan la Confrontación, la Aceptación de la responsabilidad y el Distanciamiento como estilos de afrontamiento preferentes. No se hallaron manifestaciones clínicas significativas. Se encontraron también diversas relaciones entre las variables, como entre Neuroticismo y algunos estilos de afrontamiento, entre Extroversión e Inteligencia Emocional, Inteligencia Emocional y Autocontrol, entre Autocontrol y Aceptación de la propia responsabilidad, entre Distanciamiento y Evitación, entre la Planificación y la Revaluación positiva. ABSTRACT: The present survey analyses the psychological characters of 26 conciliators of an Arequipa city´s group. For this, the personality has been evaluated by the Eysenck Personality Questionnaire, the coping types with the Coping Types Questionnaire by Lazarus and Folkman, the emotional intelligence with the Emotional Intelligence Questionnaire and to value some clinics manifestations of personality we used the MINI-MULT. The results refers that the Arequipa conciliators have sanguine personality in predominant wise, emotional intelligence is higher, and they use the coping, the acceptation of responsibility and the distancing as preferential brave types. We didn’t found significant clinics manifestations. We also found differents relationships between the variables, like

  19. Improvement on fabrication process of CANDU type reactor fuels

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chang Bum; Chung, Sang Tae; Kim, Hyung Soo; Park, Choon Ho

    1993-05-01

    The study on fabrication of the nuclear fuel for heavy water cooled reactor is performed. Among the fabrication processes of nuclear fuel, welding thickness between fuel rod and end cap can occur a serious error in total fuel length. Therefore, for nuclear fuel design, the thickness of end cap and changed weight of zircaloy-4 tube must be measured accurately. For welding performance, microstructure of welding point is investigated successfully. The result of the study shows the possibility of cost reduction and quality improvement by simplification of fabrication process of nuclear fuel. (Author).

  20. Surveillance extension experience at WWER-440 type reactors

    International Nuclear Information System (INIS)

    Gillemot, F.; Uri, G.; Oszwald, F.; Trampus, P.

    1993-01-01

    In WWER-440 reactors, the surveillance specimens are located in accelerated irradiation positions. After 5 years, all specimens are withdrawn and the operational changes are not monitored. At Paks NPP a new surveillance program extension has been settled in order to avoid these original program disadvantages and generate further data for plant lifetime management. This paper includes: research performed to prepare the surveillance extension programme, the evaluation method for the surveillance extension, and first results (Charpy and tensile tests). (authors). 6 refs., 12 figs., 3 tabs

  1. Automatic accounting of nuclear materials at WWER type reactor NPPs

    International Nuclear Information System (INIS)

    Babaev, N.S.; Poznyakov, N.L.; Strelkov, D.F.

    1978-01-01

    The possibilities of automatic accounting of nuclear materials at NPPs based on WWER reactors are considered. Organizational and technical principles of an automated system of accounting that takes into consideration IAEA requirements in conducting accounting documentation are proposed. A program is described for accounting materials using a BESM-6 computer. Operation of the program requires that all accounting data be recorded on conventional carriers of computer information (magnetic tapes, discs, perforated cards), which constitute the basic NPP accounting documents and may be directly used as initial data for a corresponding information program

  2. Completely integrated prestressed-concrete reactor pressure vessel, type 'Star'

    International Nuclear Information System (INIS)

    Neunert, B.; Jueptner, G.; Kumpf, H.

    1975-01-01

    The star support vessel is suitable for the connection to all primary circuit systems consisting of a main vessel and a number of satellite vessels around and connected to it, i.e. for LWR, HTR and process reactor. It must be made clear, however, that the PWR in particular with its components does not appear to be suited for the optimum incorporation in a prestressed-concrete pressure vessel system, no matter what kind. There are clear concepts about modifications which, however, require considerable development expenditure. (orig./LH) [de

  3. Transient performance of flow in circuits of PWR type reactors

    International Nuclear Information System (INIS)

    Hirdes, V.R.; Carajilescov, P.

    1988-09-01

    Generally, PWR's are designed with several primary loops, each one provided with a pump to circulate the coolant through the core. If one or more of these pumps fail, there would be a decrease in reactor flow rate which could cause coolant phase change in the core and components overheating. The present work establishes a simulation model for pump failure in PWR's and the SARDAN-FLOW computes code was developed, considering any combination of such failures. Based on the data of Angra I, several accident and operational transient conditions were simulated. (author) [pt

  4. Theoretical study for ICRF sustained LHD type p-11B reactor

    International Nuclear Information System (INIS)

    Watanabe, Tsuguhiro

    2003-04-01

    This is a summary of the workshop on 'Theoretical Study for ICRF Sustained LHD Type p- 11 B Reactor' held in National Institute for Fusion Science (NIFS) on July 25, 2002. In the workshop, study of LHD type D- 3 He reactor is also reported. A review concerning the advanced nuclear fusion fuels is also attached. This review was reported at the workshop of last year. The development of the p- 11 B reactor research which uses the LHD magnetic field configuration has been briefly summarized in section 1. In section 2, an integrated report on advanced nuclear fusion fuels is given. Ignition conditions in a D- 3 He helical reactor are summarized in section 3. 0-dimensional particle and power balance equations are solved numerically assuming the ISS95 confinement law including a confinement factor (γ HH ). It is shown that high average beta plasma confinement, a large confinement factor (γ HH > 3) and the hot ion mode (T i /T e > 1.4) are necessary to achieve the ignition of the D- 3 He helical reactor. Characteristics of ICRF sustained p- 11 B reactor are analyzed in section 4. The nuclear fusion reaction rate is derived assuming a quasilinear plateau distribution function (QPDF) for protons, and an ignition condition of p- 11 B reactor is shown to be possible. The 3 of the presented papers are indexed individually. (J.P.N.)

  5. Three-dimension thermal hydraulic studies for the pool-type fast reactor of CEFR

    International Nuclear Information System (INIS)

    Xu Yijun; Liu Yizhe; Xue Xiuli; Feng Yuheng; Qiao Xuedong; Hou Zhifeng; Yu Hong; Yang Hongyi; Yang Fuchang

    2009-01-01

    With the development of the computer software and hardware, 3-dimension numerical analysis technology has become an important part of the reactor core and plenums design and research of the fast reactor, sometimes even plays an un-replacable role in the design. In this paper, the typical thermal-hydraulic phenomena in the pool-type fast reactor are analysed by using 3-dimension numerical analysis codes and programs. It can be said that it will play an important role in the thermal hydraulic design and research by using these tools. And at the same time, it will also set good examples and speed up the application of these technologies by summing up these experiences and methods in order that it can be used in the future design and analyses for the large-scaled pool-type fast reactor. (authors)

  6. Modelling the WWER-type reactor dynamics using a hybrid computer. Part 1

    International Nuclear Information System (INIS)

    Karpeta, C.

    Results of simulation studies into reactor and steam generator dynamics of a WWER type power plant are presented. Spatial kinetics of the reactor core is described by a nodal approximation to diffusion equations, xenon poisoning equations and heat transfer equations. The simulation of the reactor model dynamics was performed on a hybrid computer. Models of both a horizontal and a vertical steam generator were developed. The dynamics was investigated over a large range of power by computing the transients on a digital computer. (author)

  7. Investigating The Neutron Flux Distribution Of The Miniature Neutron Source Reactor MNSR Type

    International Nuclear Information System (INIS)

    Nguyen Hoang Hai; Do Quang Binh

    2011-01-01

    Neutron flux distribution is the important characteristic of nuclear reactor. In this article, four energy group neutron flux distributions of the miniature neutron source reactor MNSR type versus radial and axial directions are investigated in case the control rod is fully withdrawn. In addition, the effect of control rod positions on the thermal neutron flux distribution is also studied. The group constants for all reactor components are generated by the WIMSD code, and the neutron flux distributions are calculated by the CITATION code. The results show that the control rod positions only affect in the planning area for distribution in the region around the control rod. (author)

  8. Modification of Neutron Kinetic Code for Plate Type Fuel Nuclear Reactor

    Directory of Open Access Journals (Sweden)

    Salah Ud-Din Khan

    2013-01-01

    Full Text Available The research is conducted on the modification of neutron kinetic code for the plate type fuel nuclear reactor. REMARK is a neutron kinetic code that works only for the cylindrical type fuel nuclear reactor. In this research, our main emphasis is on the modification of this code in order to be applicable for the plate type fuel nuclear reactor. For this purpose, detailed mathematical studies have been performed and are subjected to write the program in Fortran language. Since REMARK code is written in Fortran language, so we have developed the program in Fortran and then inserted it into the source library of the code. The main emphasis is on the modification of subroutine in the source library of the code for hexagonal fuel assemblies with plate type fuel elements in it. The number of steps involved in the modification of the code has been included in the paper. The verification studies were performed by considering the small modular reactor with hexagonal assemblies and plate type fuel in it to find out the power distribution of the reactor core. The purpose of the research is to make the code work for the hexagonal fuel assemblies with plate type fuel element.

  9. Aplicación didáctica de las inteligencias múltiples

    OpenAIRE

    Delgado Henríquez, María del Pino

    2013-01-01

    Hacia una escuela inclusiva que potencie el desarrollo de las distintas inteligencias. Según Howard Gardner, serían ocho, por tanto, el ser humano poseería ocho puntos diferentes de su cerebro donde se albergarían diferentes inteligencias. Aunque este Psicólogo afirme que número ocho es relativamente subjetivo, son ésas las inteligencias que se caracterizan por lo que él denomina inteligencias múltiples, las cuales son: Inteligencia Lingüística o verbal. Inteligencia Lógico – Matemática. Inte...

  10. Method of fuel exchange in BWR type reactors

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1986-01-01

    Purpose: To shorten the time required for the exchange of fuel assemblies, increase the burnup and improve the fuel economy. Method: Control rods in the reactor core are divided into two groups, in which the first group is constituted with four adjacent fuel assemblies, that is, the unburnt, and the second cycle burning, the fourth cycle burning and the sixth cycle burning while the second group is constituted with four adjacent fuel assemblies, that is, the first cycle burning, the third burning, the fifth cycle burning and the seventh cycle burning. Then, after completion of one cycle operation, fuel assemblies burnt for 8 cycles are taken out and replaced with the unburnt fuel assemblies. Further, a third group constituted with four adjacent fuel assemblies, i.e., the eighth cycle burning, the nineth cycle burning, the tenth cycle burning and the eleventh cycle burning are arranged at the outer circumferential range of the reactor core. After the completion for the one cycle operation, the fuel assemblies for the eighth cycle burning may be charged therein instead of the fuel assemblies for the twelveth cycle burning. (Sekiya, K.)

  11. Inteligencias múltiples y deporte

    Directory of Open Access Journals (Sweden)

    José Mª del Pino Medina

    2009-03-01

    Full Text Available El propósito del presente estudio, basándonos en la Teoría de las Inteligencias Múltiples de Gardner, consiste en averiguar si existe un perfil de inteligencia típico para deportistas, y si a su vez se pueden identificar subperfiles en función de la modalidad deportiva practicada. Definido el perfil para personas deportistas y el perfil para cada modalidad, se comparan, al objeto de poder contrastarlas. Contamos con la colaboración de futbolistas, baloncestistas, nadadores y atletas, además de personas no deportistas, que cumplimentaron el cuestionario para delimitar el perfil de IM. Se intenta determinar si existen diferencias por el hecho de ser hombre o mujer deportista en las modalidades en las que contamos con sujetos de ambos sexos. Del análisis se desprende la existencia de un perfil de IM para deportistas, que a su vez presenta diferencias en función de la modalidad deportiva practicada.

  12. Continuous fill intermittent decant type sequencing batch reactor application to upgrade the UASB treated sewage.

    Science.gov (United States)

    Khan, Abid Ali; Gaur, Rubia Zahid; Diamantis, Vasileios; Lew, Beni; Mehrotra, Indu; Kazmi, A A

    2013-05-01

    The performance of continuous flow intermittent decant type sequencing batch (CFID) reactor treating the effluent of an UASB reactor treating domestic wastewater and operated at 8 h hydraulic retention time (HRT) was investigated. The CFID was operated at three different HRTs (22, 8 and 6 h) and three different dissolved oxygen (DO) patterns (UASB systems, with a final effluent quality that comply with receiving water and effluent reuse criteria.

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

    International Nuclear Information System (INIS)

    Itjeu Karliana; Sumijanto; Dhandhang Purwadi, M.

    2008-01-01

    The needs of fresh water increased by rapid population growth and industrials expansion, but these demands can not be prepared naturally. Following this case, seawater desalination becomes the primer option which can fulfill the need through the nuclear desalination technology. The coupled nuclear power reactor enables to supply thermal energy for auxiliary equipment and pumps operation. The utilization study of power reactor type BWR coupled with desalination process has been performed. The goal of study is to obtain characteristic data of desalted water specification which desalination system coupling with nuclear power plant produced energy for desalination process. The study is carried out by browsing data and information, and comprehensive review of thermal energy correlation between NPP with desalination process installation. According to reviewing are found that the thermal energy and electric power utilization from the nuclear power reactor are enable to remove the seawater to produce desalted water and also to operate auxiliary equipments. The assessment results is VK-300 reactor prototype, BWR type 250 MW(e) power are cogeneration unit can supplied hot steam temperature 285 °C to the extraction turbine to empower 150 MW electric power, and a part of hot steam 130 °C is use to operate desalination process and remind heat is distribute to the municipal and offices at that region. The coupled of VK-300 reactor power type BWR with desalination installation of MED type enable to produce desalted water with high quality distillate. Based on the economic calculation that the VK-300 reactor power of BWR type produced water distillate capacity is 300.000 m 3 /hour with cost US$ 0.58/m 3 . The coupling VK-300 reactor power type BWR with MED desalination plant is competitive economically. (author)

  14. Status of development - An integral type small reactor MRX in JAERI

    International Nuclear Information System (INIS)

    Hoschi, T.; Ochiai, M.; Shimazaki, J.

    1998-01-01

    JAERI is conducting a design study on an integral type small reactor MRX for the use of nuclear ships. The basic concept of the reactor system is the integral type reactor with in-vessel steam generators and control rod drive systems, however, such new technologies as the water-filled containment, the passive decay heat removal system, the advanced automatic system, etc., are adopted to satisfy the essential requirements for the next generation ship reactors, i.e. compact, light, highly safe and easy operation. Research and development (R and D) works have being progressed on the peculiar components, the advanced automatic operation systems and the safety systems. Feasibility study and the economical evaluation of nuclear merchant ships have also being performed. The experiments and analysis of the safety carried out so far are proving that the passive safety features applied into the MRX are sufficient functions in the safety point of view. The MRX is a typical small type reactor realizing the easy operation by simplifying the reactor systems adopting the passive safety systems, therefore, it has wide variety of use as energy supply systems. This paper summarizes the present status on the design study of the MRX and the research and development activities as well as the some results of feasibility study. (author)

  15. Special features of embrittlement of welded joints in shells of VVER-type reactors

    International Nuclear Information System (INIS)

    Kasatkin, O.G.

    1999-01-01

    At present, the atomic power engineering of Russia and Ukraine is based on water-water energy reactors of the VVER-440 and VVER-1000 type, with the electric power of 440 and 1000 MW, respectively. The majority of the VVER-440 reactors are installed in Russia, and VVER-1000 reactors operate in Ukraine. The reactors' shell (RS) is produced from cylindrical shells and a dished end welded together by circular joints under a flux. The RS of the VVER-440 reactor is produced from 15Kh3MFA steel, and the VVER-1000 reactors are produced from 15Kh2NMFA steel. The shell of the VVER-1000 reactor has an internal austenite coating. The condition of the RS metal is determined mainly by the critical brittleness temperature T b at which the impact toughness of specimens with a sharp notch reaches 60 J/cm 2 . The energy reactors, working in western countries, are characterised by a service life of 40 years and discussion is being carried out to extend this lifetime to 60 years. The design service life of the domestic reactors varies from 30 (RS VVER-440) to 40 (RS VVER-1000) years. According to investigations, the service life of the shells of these reactors is restricted by the properties of welded joints which are characterised by higher susceptibility to embrittlement than that of the parent metal, especially due to a higher content in the weld of phosphorus (RS VVER-440) or nickel (RS VVER-1000). Therefore, some experts believe that the actual service life of the RS is shorter than the design life. The accurate evaluation of the service life of welded joints in the RS is very important for the safety of service and also in the economic aspects, because the unjustified decrease of the permissible service life and premature shutdown of units of the nuclear power station result in huge losses

  16. Experience with safety assessment of digital upgrading of IandC in VVER type reactors

    International Nuclear Information System (INIS)

    Wach, D.; Mulka, B.; Schnuerer, G.

    1997-01-01

    The digital upgrading of IandC systems important to safety in WWER type reactors requires a broad expertise in various knowledge fields. The approach of the Institute for safety Technology to the qualification and categorization of safety-critical software systems is highlighted. The role of the Institute in the qualification of the Teleperm XS and the type testing of its components is described. The aspects of the safety assessment of digital IandC systems in WWER type reactors is discussed in some detail. (A.K.)

  17. Reactor coolant pump type RUV for Westinghouse Electric Company LLC reactor AP1000 TM

    International Nuclear Information System (INIS)

    Baumgarten, S.; Brecht, B.; Bruhns, U.; Fehring, P.

    2010-01-01

    The RUV is a reactor coolant pump, specially designed for the Westinghouse Electric Company LLC AP1000 TM reactor. It is a hermetically sealed, wet winding motor pump. The RUV is a very compact, vertical pump/motor unit, designed to fit into the compartment next to the reactor pressure vessel. Each of the two steam generators has two pump casings welded to the channel head by the suction nozzle. The pump/motor unit consists of a pump part, where a semi-axial impeller/diffuser combination is mounted in a one-piece pump casing. Computational Fluid Dynamics methods combined with various hydraulic tests in a 1:2 scale hydraulic test assure full compliance with the specific customer requirements. A short and rigid shaft, supported by a radial bearing, connects the impeller with the high inertia flywheel. This flywheel consists of a one-piece forged stainless steel cylinder, with an option for several smaller heavy metal cylinders inside. The flywheel is located inside the thermal barrier, which forms part of the pressure boundary. A specific arrangement of cooling water circuits guarantees a homogeneous temperature distribution in and around the flywheel, minimizes the friction losses of the flywheel and protects the motor from hot coolant. The driving torque is transmitted by the motor shaft, which itself is supported by two radial bearings. A three-phase, high-voltage squirrel-cage induction motor generates the driving torque. Due to the wet winding concept it is possible to achieve positive effects regarding motor lifetime. The cooling water is forced through the stator windings and the gap between rotor and stator by an auxiliary impeller. Furthermore, this wet winding motor concept has higher efficiency as compared to a canned motor since there are no eddy current losses. As part of the design process and in addition to the hydraulic scale model, a complete half scale model pump was built. It was used to verify the calculations performed like coast

  18. Conducta agresiva e inteligencia emocional en la adolescencia

    OpenAIRE

    Cándido J. Inglés; María S. Torregrosa; José M. García-Fernández; María C. Martínez-Monteagudo; Estefanía Estévez; Beatriz Delgado

    2014-01-01

    Son escasos los estudios que analizan la relación entre conducta agresiva e inteligencia emocional. Este estudio examina la relación entre inteligencia emocional rasgo y los componentes motor (agresividad física y agresividad verbal), cognitivo (hostilidad) y afectivo/emocional (ira) de la conducta agresiva. El Trait Emotional Intelligence Questionnaire-Adolescents Short Form (TEIQue-ASF) y el Aggression Questionnaire Short version (AQ-S) fueron administrados a una muestra de 314 adolescentes...

  19. La Inteligencia Emocional y el estudio de la felicidad

    Directory of Open Access Journals (Sweden)

    Pablo Fernández-Berrocal

    2009-01-01

    Full Text Available Desde que Salovey y Mayer (1990 introdujera el constructo de inteligencia emocional en la literatura científica, varios investigadores han analizado el vínculo potencial de las habilidades emocionales sobre el bienestar individual y la felicidad subjetiva. La inteligencia emocional, definida como la habilidad para percibir, comprender, asimilar y regular las emociones propias y la de los demás, aparece como una destreza crítica que ayudaría a los adolescentes a guiar sus pensamientos y a reflexionar sobre sus emociones ayudándoles a mejorar sus niveles de bienestar. Por otro lado, se discuten las similitudes y diferencias conceptuales entre el campo de la psicología positiva y el de la inteligencia emocional. Se presentan datos recientes, utilizando las medidas de habilidad de inteligencia emocional (MSCEIT, en los que se ponen de manifiesto los correlatos y consecuencias de la inteligencia emocional para un desarrollo positivo durante la adolescencia. En general, los resultados demuestran que las habilidades emocionales se relacionan con la felicidad, el funcionamiento social y el bienestar de los niños y adolescentes. Asimismo, se discuten las implicaciones educativas y se presentan pautas específicas desde la Psicología Positiva y la Inteligencia Emocional para crear escuelas positivas y emocionalmente inteligentes. Finalmente, los autores subrayan la importancia de desarrollar fortalezas positivas y habilidades socio-emocionales en el contexto educativo.

  20. Structural assessments of plate type support system for APR1400 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, Anh Tung; Namgung, Ihn, E-mail: inamgung@kings.ac.kr

    2017-04-01

    Highlights: • This paper investigates plate-type support structure for the reactor vessel of the APR 1400. • The tall column supports of APR1400 reactor challenges in seismic and severe accident events. • A plate-type support of reactor vessel was proposed and evaluated based on ASME code. • The plate-type support was assessed to show its higher rigidity than column-type. - Abstract: This paper investigates an alternative form of support structure for the reactor vessel of the APR 1400. The current reactor vessel adopts a four-column support arrangement locating on the cold legs of the vessel. Although having been successfully designed, the tall column structure challenges in seismic events. In addition, for the mitigation of severe accident consequences, the columns inhibit ex-vessel coolant flow, hence the elimination of the support columns proposes extra safety advantages. A plate-type support was proposed and evaluated for the adequacy of meeting the structural stiffness by Finite Element Analysis (FEA) approach. ASME Boiler and Pressure Vessel Code was used to verify the design. The results, which cover thermal and static structural analysis, show stresses are within allowable limits in accordance with the design code. Even the heat conduction area is increased for the plate-type of support system, the results showed that the thermal stresses are within allowable limits. A comparison of natural frequencies and mode shapes for column support and plate-type support were presented as well which showed higher fundamental frequencies for the plate-type support system resulting in greater rigidity of the support system. From the outcome of this research, the plate-type support is proven to be an alternative to current APR column type support design.

  1. Development of a Monolithic Research Reactor Fuel Type at Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Clark, C.R.; Briggs, R.J.

    2004-10-06

    The Reduced Enrichment for Research and Test Reactors (RERTR) program has been tasked with the conversion of research reactors from highly enriched to low-enriched uranium (LEU). To convert several high power reactors, monolithic fuel, a new fuel type, is being developed. This fuel type replaces the standard fuel dispersion with a fuel alloy foil, which allows for fuel densities far in excess of that found in dispersion fuel. The single-piece fuel foil also contains a significantly lower interface area between the fuel and the aluminum in the plate than the standard fuel type, limiting the amount of detrimental fuel-aluminum interaction that can occur. Implementation of monolithic fuel is dependant on the development of a suitable fabrication method as traditional roll-bonding techniques are inadequate.

  2. Vibration stopper for main recycling pump in FBR type reactor

    International Nuclear Information System (INIS)

    Ooka, Yuji.

    1991-01-01

    Since a main recycling pump suspended in a cantilever form from an upper support structure in a reactor container or a pump-containing vessel has low eigenfrequency, there is a worry of causing resonance vibrations. Then, sodium discharge ports are disposed in the circumferential direction of a pump body each at an equiangular distance. A ball is disposed at the exit. A cap is secured to the pump body so as to sandwich the ball. A dash pot disposed at the outside of the cap is made movable. Then dash pot is usually forwarded by the thrusting force of highly pressurized sodium, to attain vibration damping. When it undergoes impact shocks such as earthquakes, the dash pot is backwarded and the highly pressurized sodium is partially returned to the cap, by which the ball closes the sodium discharge port of the pump body. As a result, the impact shocks are absorbed to the highly pressurized sodium. If the pump is stopped and the pressure is removed, since the dash pot is returned to the original position to prevent scorching, drawing and reinsertion of the pump are facilitated upon maintenances. (N.H.)

  3. Neutronic design of a 22 MW MTR type nuclear research reactor

    International Nuclear Information System (INIS)

    Khamis, I.; Khattab, K.; Soleman, I.; Ghazi, N.

    2006-12-01

    The neutronic design calculations of a 22 MW MTR type nuclear research reactor are conducted in this project. This reactor type is selected by the Arab Atomic Energy Commission in a cooperated project. The design calculations are conducted in two methods: The deterministic method, solving the neutron transport and diffusion equations using the WIMSD4 and the CITATION codes, and the probabilistic method using the MCNP code. Good agreements are noticed between the results of the multiplication factor and the neutron flux distribution which prove the accuracy of our models using the two methods. (author)

  4. A nuclear desalination complex with a VK-300 boiling type reactor facility

    International Nuclear Information System (INIS)

    Kuznetzov, Y.N.; Mishanina, Y.A.; Romenkov, A.A.

    2004-01-01

    RDIPE has developed a detailed design of an enhanced safety nuclear steam supply system (NSSS) with a VK-300 boiling water reactor for combined heat and power generation. The thermal power of the reactor is 750 MW. The maximum electrical power in the condensation mode is 250 MWe. The maximum heat generation capacity of 400 Gcal/h is reached at 150 MWe. This report describes, in brief, the basic technical concepts for the VK-300 NSSS and the power unit, with an emphasis on enhanced safety and good economic performance. With relatively small power, good technical and economic performance of the VK-300 reactor that is a base for the desalination complex is attained through: reduced capital costs of the nuclear plant construction thanks to technical approaches ensuring maximum simplicity of the reactor design and the NSSS layout; a single-circuit power unit configuration (reactor-turbine) excluding expensive equipment with a lot of metal, less pipelines and valves; reduced construction costs of the basic buildings thanks to reduced construction volumes due to rational arrangement concepts; higher reliability of equipment and reduced maintenance and repair costs; longer reactor design service life of up to 60 years; selection of the best reactor and desalination equipment interface pattern. The report considers the potential application of the VK-300 reactor as a source of energy for distillation desalination units. The heat from the reactor is transferred to the desalination unit via an intermediate circuit. Comparison is made between variants of the reactor integration with desalination units of the following types: multi-stage flash (MSF technology); multi-effect distillation horizontal-tube film units of the DOU GTPA type (MED technology). The NDC capacity with the VK-300 reactor, in terms of distillate, will be more than 200,000 m 3 /day, with the simultaneous output of electric power from the turbine generator buses of around 150 MWe. The variants of the

  5. Theoretical study for ICRF sustained LHD type p-{sup 11}B reactor

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Tsuguhiro (ed.)

    2003-04-01

    This is a summary of the workshop on 'Theoretical Study for ICRF Sustained LHD Type p-{sup 11}B Reactor' held in National Institute for Fusion Science (NIFS) on July 25, 2002. In the workshop, study of LHD type D-{sup 3}He reactor is also reported. A review concerning the advanced nuclear fusion fuels is also attached. This review was reported at the workshop of last year. The development of the p-{sup 11}B reactor research which uses the LHD magnetic field configuration has been briefly summarized in section 1. In section 2, an integrated report on advanced nuclear fusion fuels is given. Ignition conditions in a D-{sup 3}He helical reactor are summarized in section 3. 0-dimensional particle and power balance equations are solved numerically assuming the ISS95 confinement law including a confinement factor ({gamma}{sub HH}). It is shown that high average beta plasma confinement, a large confinement factor ({gamma}{sub HH} > 3) and the hot ion mode (T{sub i}/T{sub e} > 1.4) are necessary to achieve the ignition of the D-{sup 3}He helical reactor. Characteristics of ICRF sustained p-{sup 11}B reactor are analyzed in section 4. The nuclear fusion reaction rate < {sigma}{upsilon} > is derived assuming a quasilinear plateau distribution function (QPDF) for protons, and an ignition condition of p-{sup 11}B reactor is shown to be possible. The 3 of the presented papers are indexed individually. (J.P.N.)

  6. Control console conceptual design for sheet type fuels of Triga Mark-II reactor

    International Nuclear Information System (INIS)

    Eko Priyono; Kurnia Wibowo; Anang Susanto

    2016-01-01

    The control console conceptual design for sheet type fuel of TRIGA Mark-II reactor has been made. The control console conceptual design was made with refer study result of instrument and control system which is used in BATAN'S reactor i.e TRIGA-2000 Bandung, TRIGA Yogyakarta and MPR-30 Serpong. The control console conceptual design was made by using AutoCad software. The control console conceptual design reactor for sheet type fuel of TRIGA Mark-II reactor consist of 5 segments that is 3 segments for placing the computer monitors, 1 segment for placing bargraph displays and recorders and 1 segment for placing panel meters. There are the door on front and back position at each segment for enter and out devices in the console. The control console conceptual design is also equipped by the table along in front of console for placing reactor panel control and for writing, 3 drawers for 3 keyboards. The dimension of console will refer control room size and the components will be placed on console which will be detailed in detail design if this conceptual design has been approved. (author)

  7. Monte Carlo Analysis of the Battery-Type High Temperature Gas Cooled Reactor

    Science.gov (United States)

    Grodzki, Marcin; Darnowski, Piotr; Niewiński, Grzegorz

    2017-12-01

    The paper presents a neutronic analysis of the battery-type 20 MWth high-temperature gas cooled reactor. The developed reactor model is based on the publicly available data being an `early design' variant of the U-battery. The investigated core is a battery type small modular reactor, graphite moderated, uranium fueled, prismatic, helium cooled high-temperature gas cooled reactor with graphite reflector. The two core alternative designs were investigated. The first has a central reflector and 30×4 prismatic fuel blocks and the second has no central reflector and 37×4 blocks. The SERPENT Monte Carlo reactor physics computer code, with ENDF and JEFF nuclear data libraries, was applied. Several nuclear design static criticality calculations were performed and compared with available reference results. The analysis covered the single assembly models and full core simulations for two geometry models: homogenous and heterogenous (explicit). A sensitivity analysis of the reflector graphite density was performed. An acceptable agreement between calculations and reference design was obtained. All calculations were performed for the fresh core state.

  8. Monte Carlo Analysis of the Battery-Type High Temperature Gas Cooled Reactor

    Directory of Open Access Journals (Sweden)

    Grodzki Marcin

    2017-12-01

    Full Text Available The paper presents a neutronic analysis of the battery-type 20 MWth high-temperature gas cooled reactor. The developed reactor model is based on the publicly available data being an ‘early design’ variant of the U-battery. The investigated core is a battery type small modular reactor, graphite moderated, uranium fueled, prismatic, helium cooled high-temperature gas cooled reactor with graphite reflector. The two core alternative designs were investigated. The first has a central reflector and 30×4 prismatic fuel blocks and the second has no central reflector and 37×4 blocks. The SERPENT Monte Carlo reactor physics computer code, with ENDF and JEFF nuclear data libraries, was applied. Several nuclear design static criticality calculations were performed and compared with available reference results. The analysis covered the single assembly models and full core simulations for two geometry models: homogenous and heterogenous (explicit. A sensitivity analysis of the reflector graphite density was performed. An acceptable agreement between calculations and reference design was obtained. All calculations were performed for the fresh core state.

  9. Optimized core design and fuel management of a pebble-bed type nuclear reactor

    NARCIS (Netherlands)

    Boer, B.

    2009-01-01

    The core design of a pebble-bed type Very High Temperature Reactor (VHTR) is optimized, aiming for an increase of the coolant outlet temperature to 1000 C, while retaining its inherent safety features. The VHTR has been selected by the international Generation IV research initiative as one of the

  10. Experimental study on earthquake resistant components for BWR type reactor building

    International Nuclear Information System (INIS)

    Miyazaki, Y.; Hayama, S.; Makita, T.; Tomii, Y.; Kubo, T.

    1987-01-01

    Seismic loading experiments were carried out for three types of seismic shear wall components. A set of fundamental data were obtained through the experimental studies. A maximium use of these data can be made in next stages to evaluate stiffnesses, strength, and so on of the complicated structural systems of a reactor building as well as its load-deflection characteristics. (orig./HP)

  11. Programme of hot points eradication (Co-60) led on French PWR type reactors

    International Nuclear Information System (INIS)

    Rocher, A.; Ridoux, P.; Anthoni, S.; Brun, C.

    1998-01-01

    The question of hot points (pellets rich in cobalt 59 or in cobalt 60 in a PWR type reactor), is studied from the radiation protection point of view. The purpose is to see how to optimize the radiation protection, the elimination of these hot points can bring an improvement. (N.C.)

  12. Modernization for safety purposes of Russian nuclear power plants with channel-type reactors

    International Nuclear Information System (INIS)

    Riakhin, V.M.

    1999-01-01

    The nineties have crucially changed the Russian policy towards channel-type reactors known as RBMK. After the period of intensive commissioning the new Units (Kursk NPP: 1976, 1979, 1983,1985; Smolensk NPP 1982, 1985, 1990), the main financial flow was directed into reconstruction of these units. Safety upgrade of the units of Kursk NPP is presented in more details

  13. Model for calculating the boron concentration in PWR type reactors

    International Nuclear Information System (INIS)

    Reis Martins Junior, L.L. dos; Vanni, E.A.

    1986-01-01

    A PWR boron concentration model has been developed for use with RETRAN code. The concentration model calculates the boron mass balance in the primary circuit as the injected boron mixes and is transported through the same circuit. RETRAN control blocks are used to calculate the boron concentration in fluid volumes during steady-state and transient conditions. The boron reactivity worth is obtained from the core concentration and used in RETRAN point kinetics model. A FSAR type analysis of a Steam Line Break Accident in Angra I plant was selected to test the model and the results obtained indicate a sucessfull performance. (Author) [pt

  14. 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

  15. CORRELACION ENTRE INTELIGENCIA EMOCIONAL Y RENDIMIENTO ACADEMICO EN LOS ALUMNOS DEL QUINTO GRADO DE EDUCACION SECUNDARIA DEL CONSORCIO DE COLEGIOS CATOLICOS DEL CUSCO - 2012

    OpenAIRE

    PÉREZ SÁNCHEZ, ELMER FREDY

    2007-01-01

    NIVELES DEL TEST DE INTELIGENCIA EMOCIONAL RENDIMIENTO ACADÉMICO EN LAS ÁREAS DE MATEMÁTICA Y COMUNICACIÓN CORRELACIÓN ENTRE LA INTELIGENCIA EMOCIONAL Y EL RENDIMIENTO ACADÉMICO EN LAS +REAS DE MATEMÁTICA Y COMUNICACIÓN DISCUSIÓN DE RESULTADOS INTELIGENCIA EMOCIONAL DEFINICIONES DE INTELIGENCIA TEORÍAS PSICOLÓGICAS DE LA INTELIGENCIA INTELIGENCIA EMOCIONAL LA INTELIGENCIA EMOCIONAL SEGÚN BARÓN DEFINICIÓN DE LOS FACTORES DE LA INTELIGENCIA EMOCIONAL LA INTELIGENCIA EMOCIONAL EN LA EDUCACIÓN IN...

  16. Inteligencia emocional y educación. Beneficios de la inteligencia emocional en la escuela

    OpenAIRE

    Palomera Martín, Raquel

    2016-01-01

    La conferencia reivindica la inclusión de las competencias emocionales como competencias básicas en la escolaridad obligatoria y en los objetivos de la formación inicial del profesorado que se está diseñando actualmente dentro del marco del Espacio Europeo de Educación Superior (EEES). Para ello, realizamos una revisión de las investigaciones más actuales en torno al papel fundamental que tienen las competencias emocionales y más concretamente la inteligencia emocional (IE; Mayer y Salovey, 1...

  17. Problemas bioéticos emergentes de la inteligencia artificial

    Directory of Open Access Journals (Sweden)

    Jairo Andrés Villalba Gómez

    2016-01-01

    Full Text Available El presente artículo de revisión, relaciona de forma analítica los conceptos entre bioética e inteligencia artificial, identificando los elementos técnicofilosóficos tales como: transhumanismo, inteligencia artificial y bioética de la tecnología; cuyo orden transdisciplinar, evoluciona en cuestionamientos científicos basados en la evolución de la tecnociencia del siglo XXI. Se identificarán los referentes conceptuales de la relación entre transhumanismo (H+ e inteligencia artificial (IA, su génesis, enfoques, fundamentos disciplinares, así como los elementos básicos que hacen posible la arquitectura en un sistema de inteligencia artificial, precisando así el ambiente prospectivo en el que se consolida una “era” basada en la “singularidad tecnológica”, para finalmente concluir en una descripción de algunos problemas ético-filosóficos que emergen en la evolución de la inteligencia artificial.

  18. Analysis of gamma heating at TRIGA mark reactor core Bandung using plate type fuel

    International Nuclear Information System (INIS)

    Setiyanto; Tukiran Surbakti

    2016-01-01

    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. (author)

  19. Dominant seismic sloshing mode in a pool-type reactor tank

    International Nuclear Information System (INIS)

    Ma, D.C.; Gvildys, J.; Chang, Y.W.

    1987-01-01

    Large-diameter LMR (Liquid Metal Reactor) tanks contain a large volume of sodium coolant and many in-tank components. A reactor tank of 70 ft. in diameter contains 5,000,000 of sodium coolant. Under seismic events, the sloshing wave may easily reach several feet. If sufficient free board is not provided to accommodate the wave height, several safety problems may occur such as damage to tank cover due to sloshing impact and thermal shocks due to hot sodium, etc. Therefore, the sloshing response should be properly considered in the reactor design. This paper presents the results of the sloshing analysis of a pool-type reactor tank with a diameter of 39 ft. The results of the fluid-structure interaction analysis are presented in a companion paper. Five sections are contained in this paper. The reactor system and mathematical model are described. The dominant sloshing mode and the calculated maximum wave heights are presented. The sloshing pressures and sloshing forces acting on the submerged components are described. The conclusions are given

  20. SVBR-100 module-type fast reactor of the IV generation for regional power industry

    Science.gov (United States)

    Zrodnikov, A. V.; Toshinsky, G. I.; Komlev, O. G.; Stepanov, V. S.; Klimov, N. N.

    2011-08-01

    In the report the following is presented: basic conceptual provisions of the innovative nuclear power technology (NPT) based on modular fast reactors (FR) SVBR-100, summarized results of calculations of the reactor, analysis of the opportunities of multi-purpose application of such reactor facilities (RF) including export potentials with due account of nonproliferation requirements. The most important features of the proposed NPT analyzed in the report are as follows: (1) integral (monoblock) arrangement of the primary circuit equipment with entire elimination of the primary circuit pipelines and valves that considerably reduces the construction and assembly works period and coupling with high boiling point of lead-bismuth coolant (LBC) deterministically eliminates accidents of the LOCA type, (2) option for 100 MWe power and dimensions of the reactor provide: on the one hand, an opportunity to transport the reactor monoblock in factory-readiness by railway as well as other kinds of transport, on the other hand, core breeding ratio (CBR) exceeds 1 while MOX-fuel is used. The preferable area of application of RF SVBR-100 is regional and small power requiring power-units of electric power in a range of (100-600) MW, which could be used for cogeneration-based district heating while locating them nearby cities as well as for generation of electric power in a mode of load tracking in the regions with low network systems.

  1. SVBR-100 module-type fast reactor of the IV generation for regional power industry

    Energy Technology Data Exchange (ETDEWEB)

    Zrodnikov, A.V. [FSUE State Scientific Center of Russian Federation Institute for Physics and Power Engineering 1, Bondarenko sq., Obninsk, Kaluga rg. 249033 (Russian Federation); Toshinsky, G.I., E-mail: toshinsky@ippe.ru [FSUE State Scientific Center of Russian Federation Institute for Physics and Power Engineering 1, Bondarenko sq., Obninsk, Kaluga rg. 249033 (Russian Federation); Komlev, O.G. [FSUE State Scientific Center of Russian Federation Institute for Physics and Power Engineering 1, Bondarenko sq., Obninsk, Kaluga rg. 249033 (Russian Federation); Stepanov, V.S.; Klimov, N.N. [JSC Experimental Design Bureau ' Gidropress' 21, Ordzhonikidze st., Podolsk, Moscow rg. 142103 (Russian Federation)

    2011-08-31

    In the report the following is presented: basic conceptual provisions of the innovative nuclear power technology (NPT) based on modular fast reactors (FR) SVBR-100, summarized results of calculations of the reactor, analysis of the opportunities of multi-purpose application of such reactor facilities (RF) including export potentials with due account of nonproliferation requirements. The most important features of the proposed NPT analyzed in the report are as follows: (1) integral (monoblock) arrangement of the primary circuit equipment with entire elimination of the primary circuit pipelines and valves that considerably reduces the construction and assembly works period and coupling with high boiling point of lead-bismuth coolant (LBC) deterministically eliminates accidents of the LOCA type, (2) option for 100 MWe power and dimensions of the reactor provide: on the one hand, an opportunity to transport the reactor monoblock in factory-readiness by railway as well as other kinds of transport, on the other hand, core breeding ratio (CBR) exceeds 1 while MOX-fuel is used. The preferable area of application of RF SVBR-100 is regional and small power requiring power-units of electric power in a range of (100-600) MW, which could be used for cogeneration-based district heating while locating them nearby cities as well as for generation of electric power in a mode of load tracking in the regions with low network systems.

  2. Evaluation on Safety of Stainless Steels in Chemical Decontamination Process with Immersion Type of Reactor Coolant Pump for Nuclear Reactor

    International Nuclear Information System (INIS)

    Kim, Seong Jong; Han, Min Su; Jang, Seok Ki; Kim, Ki Joon

    2011-01-01

    Due to commercialization of nuclear power, most countries have taken interest in decontamination process of nuclear power plant and tried to develop a optimum process. Because open literature of the decontamination process are rare, it is hard to obtain skills on decontamination of foreign country and it is necessarily to develop proper chemical decontamination process system in Korea. In this study, applicable possibility in chemical decontamination for reactor coolant pump (RCP) was investigated for the various stainless steels. The stainless steel (STS) 304 showed the best electrochemical properties for corrosion resistance and the lowest weight loss ratio in chemical decontamination process with immersion type than other materials. However, the pitting corrosion was generated in both STS 415 and STS 431 with the increasing numbers of cycle. The intergranular corrosion in STS 431 was sporadically observed. The sizes of their pitting corrosion also increased with increasing cycle numbers

  3. Study on vertical seismic response model of BWR-type reactor building

    International Nuclear Information System (INIS)

    Konno, T.; Motohashi, S.; Izumi, M.; Iizuka, S.

    1993-01-01

    A study on advanced seismic design for LWR has been carried out by the Nuclear Power Engineering Corporation (NUPEC), under the sponsorship of the Ministry of International Trade and Industry (MITI) of Japan. As a part of the study, it has been investigated to construct an accurate analytical model of reactor buildings for a seismic response analysis, which can reasonably represent dynamic characteristics of the building. In Japan, vibration models of reactor buildings for horizontal ground motion have been studied and examined through many simulation analyses for forced vibration tests and earthquake observations of actual buildings. And now it is possible to establish a reliable horizontal vibration model on the basis of multi-lumped mass and spring model. However, vertical vibration models have not been so much studied as horizontal models, due to less observed data for vertical motions. In this paper, the vertical seismic response models of a BWR-type reactor building including soil-structure interaction effect are numerically studied, by comparing the dynamic characteristics of (1) three dimensional finite element model, (2) multi-stick lumped mass model with a flexible base-mat, (3) multi-stick lumped mass model with a rigid base-mat and (4) single-stick lumped mass model. In particular, the BWR-type reactor building has the long span truss roof which is considered to be one of the critical members to vertical excitation. The modelings of the roof trusses are also studied

  4. 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.)

  5. Reactor

    International Nuclear Information System (INIS)

    Evans, R.M.

    1976-01-01

    Disclosed is a neutronic reactor having a moderator, coolant tubes traversing the moderator from an inlet end to an outlet end, bodies of material fissionable by neutrons of thermal energy disposed within the coolant tubes, and means for circulating water through said coolant tubes characterized by the improved construction wherein the coolant tubes are constructed of aluminum having an outer diameter of 1.729 inches and a wall thickness of 0.059 inch, and the means for circulating a liquid coolant through the tubes includes a source of water at a pressure of approximately 350 pounds per square inch connected to the inlet end of the tubes, and said construction including a pressure reducing orifice disposed at the inlet ends of the tubes reducing the pressure of the water by approximately 150 pounds per square inch. 1 claim, 16 figures

  6. The use of experimental data in an MTR-type nuclear reactor safety analysis

    Science.gov (United States)

    Day, Simon E.

    Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type ( i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up to some reactivity insertion limit beyond which fuel damage occurs. This characteristic was studied in the Borax and Spert reactor tests of the 1950s and 1960s in the USA. This thesis considers the use of this experimental data in generic MTR-type reactor safety analysis. The approach presented herein is based on fundamental phenomenological understanding and uses correlations in the reactor test data with suitable account taken for differences in important system parameters. Specifically, a semi-empirical approach is used to quantify the relationship between the power, energy and temperature rise response of the system as well as parametric dependencies on void coefficient and the degree of subcooling. Secondary effects including the dependence on coolant flow are also examined. A rigorous curve fitting approach and error assessment is used to quantify the trends in the experimental data. In addition to the initial power burst stage of an unprotected transient, the longer term stability of the system is considered with a stylized treatment of characteristic power/temperature oscillations (chugging). A bridge from the HEU-based experimental data to the LEU fuel cycle is assessed and outlined based on existing simulation results presented in the literature. A cell-model based parametric study is included. The results are used to construct a practical safety analysis methodology for determining reactivity insertion safety limits for a light-water moderated and cooled MTR-type core.

  7. SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control

    OpenAIRE

    Lindström, Tobias

    2015-01-01

    In this master thesis a small modular sodium-cooled metal-fuelled pool-type fast reactor design, called SPARC - Safe and Passive with Autonomous Reactivity control, has been designed. The long term reactivity changes in the SPARC are managed by implementation of the the Autonomous Reactivity Control (ARC) system, which is the novelty of the design. The overall design is mainly based on the Integral Fast Reactor project (IFR), which experimentally demonstrated the passive safety characteristic...

  8. De la Neurociencia a la Inteligencia Artificial y Vuelta

    OpenAIRE

    Varona, Pablo

    2015-01-01

    Resumen—En este artículo se enfatiza la necesidad de  una mayor transferencia de conocimiento de la Neurociencia a la Inteligencia Artificial y de la Inteligencia Artificial a la Neurociencia. Para ello se describen algunos ejemplos de la transferencia bidireccional entre la Neurociencia y la tecnología, enfatizando el trabajo del Grupo de Neurocomputación Biológica de la Universidad Autónoma de Madrid y de sus colaboradores internacionales en este contexto interdisciplinar. Se discuten tambi...

  9. Problemas bioéticos emergentes de la inteligencia artificial

    OpenAIRE

    Jairo Andrés Villalba Gómez

    2016-01-01

    El presente artículo de revisión, relaciona de forma analítica los conceptos entre bioética e inteligencia artificial, identificando los elementos técnicofilosóficos tales como: transhumanismo, inteligencia artificial y bioética de la tecnología; cuyo orden transdisciplinar, evoluciona en cuestionamientos científicos basados en la evolución de la tecnociencia del siglo XXI. Se identificarán los referentes conceptuales de la relación entre transhumanismo ...

  10. La inteligencia emocional y el sector financiero colombiano

    OpenAIRE

    Rodrigo Zárate Torres; Sergio Matviuk

    2010-01-01

    Existe un consenso general que dice que la inteligencia emocional es la habilidad de los individuos de lidiar con las emociones (Salovey y Mayer, 1990; Law, Wong y Song, 2004; Mayer, Caruso y Salovey, 2000; Wong, Law y Wong, 2004a; Wong, Wong y Law, 2007) y que es tan o más importante que el coeficiente intelectual en la vida de negocios y en la carrera profesional (Erkus, 2008; Goleman, 1995). Poco se ha estudiado acerca de la inteligencia emocional y la mayoría de estudios existentes se han...

  11. Inteligencia emocional y motivación del estudiante universitario

    OpenAIRE

    Pérez Rojas, Araceli

    2012-01-01

    Programa de doctorado: Formación del Profesorado [ES] La presente tesis doctoral tiene como objetivo principal analizar la relación que existe entre los tres factores de inteligencia emocional del modelo Salovey y Mayer en el esquema de la Teoría de la Autodeterminación, en concreto con el clima motivacional de orientación hacia la tarea, por lo que estudiaremos la relación que existe entre la inteligencia emocional percibida y la motivación autodeterminada en el contexto de la educación u...

  12. La inteligencia emocional en la toma de decisiones

    OpenAIRE

    Uribe Chinkovsky, Sebastián; Henao Cadavid, Natalia

    2015-01-01

    El objetivo del presente artículo es revisar en un principio el concepto de toma de decisiones a partir de los estudios realizados por Antonio Damasio (1994/2010), los cuales nos permiten comprender que este es un proceso que está altamente influenciado por las emociones y los sentimientos -- Más adelante, y siguiendo esta línea de argumentación, se realiza una revisión del concepto de inteligencia emocional a partir de Daniel Goleman (1996) -- La inteligencia emocional nos permite comprender...

  13. Las inteligencias múltiples en los manuales de ELE

    OpenAIRE

    Pons Dasí, Victoria

    2013-01-01

    Suplemento del número 16 de marcoELE (enero - junio de 2013) Este trabajo tiene como objetivo conocer en qué medida aparecen las inteligencias múltiples en el aula de ELE y cuál es el enfoque que mayor variedad de ellas incluye en sus propuestas de trabajo. Con este fin se ha revisado la Teoría de las Inteligencias Múltiples de Gardner, así como las aportaciones de otros autores, y sobre esa base, se ha analizado en profundidad una muestra de actividades de cuatro manuales de ELE represen...

  14. La Inteligencia Emocional y el estudio de la felicidad

    OpenAIRE

    Pablo Fernández-Berrocal; Natalio Extremera Pacheco

    2009-01-01

    Desde que Salovey y Mayer (1990) introdujera el constructo de inteligencia emocional en la literatura científica, varios investigadores han analizado el vínculo potencial de las habilidades emocionales sobre el bienestar individual y la felicidad subjetiva. La inteligencia emocional, definida como la habilidad para percibir, comprender, asimilar y regular las emociones propias y la de los demás, aparece como una destreza crítica que ayudaría a los adolescentes a guiar sus pensamientos y a ref...

  15. La inteligencia emocional en Educación Infantil

    OpenAIRE

    Manzaneque Díaz-Oliver, Laura

    2013-01-01

    Conocemos la etapa de Educación Infantil, como aquella en la que se trabajan todos los aspectos de la educación, se trata de una educación integral en la cual tiene que haber un sitio para el desarrollo y la expresión de las emociones de todos los alumnos. Por ello, una vez investigada y estudiada toda la teoría sobre la inteligencia emocional, definiendo las distintas inteligencias múltiples, además de destacar la importancia de las emociones en la edad escolar, se realizará una programación...

  16. INTELIGENCIA EMOCIONAL Y "BURNOUT" EN PROFESORES DE SECUNDARIA

    OpenAIRE

    Grande-Prohens, María Magdalena

    2013-01-01

    El estudio de la influencia de la inteligencia emocional en la salud laboral de los docentes es un tema de creciente interés en la actualidad, dado que afecta a la calidad de la educación que reciben los alumnos. El objetivo del presente trabajo es analizar la relación que existe entre los componentes de la inteligencia emocional (atención, claridad y reparación emocional) y el síndrome "burnout" (agotamiento, despersonalización y realización personal) en docentes de Educación Secundaria. Se ...

  17. Propuesta educativa sobre inteligencia emocional para maestros parvularios

    OpenAIRE

    Ramírez Maldonado, Kyra Victoria

    2008-01-01

    Desde los últimos veinte años del siglo pasado han sido muy prolíficas las producciones con dirección cognitiva, a tal punto que se viene hablando del desarrollo de la ciencia cognitiva, que rebasa la visión epistemológica de corte Piagetiano. La teoría de las inteligencias múltiples de Gardner, la teoría tríarquica de Sthember, revoluciona la vieja concepción de inteligencia en los términos de Binet, con fuerte presencia positiva, reconceptúandola en su real dimensión cualitativa. Estos ap...

  18. El compromiso organizacional como predictor de la inteligencia emocional

    OpenAIRE

    Carmen M. Salvador-Ferrer

    2012-01-01

    El propósito de este estudio consiste en analisar minuciosamente la relación entre el compromiso de los trabajadores y la inteligencia emocional. Para ello, se expone una investigación que incluye sendas variables. Se obtuvieron datos de 165 trabajadores de una empresa. Además, se plantea un modelo predictivo de la inteligencia emocional, para ponerlo a prueba se aplica un análisis de ecuaciones estructurales. En este sentido, los datos vienen a reflejar el gran poder predictivo que tiene el ...

  19. Mejora del ambiente laboral con la inteligencia emocional

    OpenAIRE

    Sanz de Galdeano Arocena, Xabier

    2011-01-01

    En este proyecto fin de carrera se van a tratar tres grandes conceptos: el capital intelectual, la gestión de conocimientos y la inteligencia emocional. La idea es aumentar el capital intelectual de una empresa, mediante la mejora de la gestión de conocimientos de la misma y para ello utilizar la inteligencia emocional. Se desarrollará un poco cada uno de esos conceptos para conocer exactamente de lo que estamos hablando y así, poder entender la relación existente entre cada uno de los tres c...

  20. Inteligencia emocional y enfermedad oncológica

    OpenAIRE

    Teques, Andreia Patricia de Sousa Pereira

    2016-01-01

    [ES]La Inteligencia Emocional (IE) se ha revelado como una pronosticadora de éxito y realización en múltiples contextos de la vida. En la presente investigación, se enfocará su relación con variables psicológicas con la finalidad de analizar su pertinencia para la adaptación en el proceso de enfermedad oncológica. En este sentido, el estudio empírico está compuesto por cuatro estudios. El premier pretende construir y validar un cuestionario sobre Inteligencia Emocional. Un total de 401 partic...

  1. Sistemas de Inteligencia Web basados en redes sociales

    OpenAIRE

    Rosa Troyano, Fco. Fernando de la; Martínez Gasca, Rafael

    2007-01-01

    El Análisis de las Redes Sociales (ARS) es un área que está emergiendo como imprescindible en los procesos de toma de decisiones. Su capacidad para analizar e intervenir una red social puede ser aprovechada para implantar tareas de vigilancia en los sistemas de inteligencia de un centro de investigación o una empresa de base tecnológica. El objetivo de este trabajo es realizar una propuesta para diseñar sistemas de inteligencia web basados en redes sociales. El primer obstáculo para implantar...

  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. Atmospheric-pressure small-scale thermal-hydraulic experiment of a PIUS-type reactor

    International Nuclear Information System (INIS)

    Tasaka, Kanji; Tamaki, Masayoshi; Imai, Satoshi; Kohketsu, Hideto; Anoda, Yoshinari; Murata, Hideo; Kukita, Yutaka.

    1992-01-01

    An experimental small-scale low-pressure setup of a PIUS (Process Inherent Ultimate Safety)-type reactor was used for the examination of the stability during normal operation such as startup and load following operation and of the safety during accidents such as loss-of-feedwater and pump runaway. Automatic feedback pump control system based on differential pressure at lower honeycomb density lock was quite effective to maintain the stratified interface between primary and pool water in the honeycomb density lock during normal operation. The process inherent ultimate safety characteristics of the PIUS-type reactor was confirmed with pump-trip scram at the pump speed limit for the various simulated accidents such as a loss-of-feedwater and pump runaway. (author)

  4. Heat resistant/radiation resistant cable and incore structure test device for FBR type reactor

    International Nuclear Information System (INIS)

    Tanimoto, Hajime; Shiono, Takeo; Sato, Yoshimi; Ito, Kazumi; Sudo, Shigeaki; Saito, Shin-ichi; Mitsui, Hisayasu.

    1995-01-01

    A heat resistant/radiation resistant coaxial cable of the present invention comprises an insulation layer, an outer conductor and a protection cover in this order on an inner conductor, in which the insulation layer comprises thermoplastic polyimide. In the same manner, a heat resistant/radiation resistant power cable has an insulation layer comprising thermoplastic polyimide on a conductor, and is provided with a protection cover comprising braid of alamide fibers at the outer circumference of the insulation layer. An incore structure test device for an FBR type reactor comprises the heat resistant/radiation resistant coaxial cable and/or the power cable. The thermoplastic polyimide can be extrusion molded, and has excellent radiation resistant by the extrusion, as well as has high dielectric withstand voltage, good flexibility and electric characteristics at high temperature. The incore structure test device for the FBR type reactor of the present invention comprising such a cable has excellent reliability and durability. (T.M.)

  5. Safety and Environment aspects of Tokamak- type Fusion Power Reactor- An Overview

    Science.gov (United States)

    Doshi, Bharat; Reddy, D. Chenna

    2017-04-01

    Power Reactor). This paper describes an overview of safety and environmental merits of fusion power reactor, issues and design considerations and need for R&D on safety and environmental aspects of Tokamak type fusion reactor.

  6. Trace element analysis at the Livermore pool-type reactor using neutron activation techniques

    International Nuclear Information System (INIS)

    Ragaini, R.C.; Ralston, R.; Garvis, D.

    1975-01-01

    The capabilities of trace element analysis at the Livermore Pool-Type Reactor (LPTR) using instrumental neutron activation analysis (INAA) are discussed. A description is given of the technology and the methods employed, including sample preparation, irradiation, and analysis. Applications of the INAA technique in past and current projects are described. A computer program, GAMANAL, has been used for nuclide identification and quantification. (U.S.)

  7. Regulatory use the classification security systems of I and C in VVER type reactors

    International Nuclear Information System (INIS)

    Ilizastegui Perez, F.

    1998-01-01

    Presently work the author proposes a classification to the system I and C to the VVER 440 type reactor in categories the regulatory control with a view to establishing the degree to the attention that the regulator should pay to these systems, leaving the importance that have the same ones for the security the installation, during the execution the works that are carried out with this equipment in the stages construction, setting in service and exploitation

  8. Propagation of cracks by stress corrosion in conditions of BWR type reactor

    International Nuclear Information System (INIS)

    Merino C, F.J.; Fuentes C, P.

    2004-01-01

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

  9. Natural vibrations of a core banel of a PWR type reactor by elements of revolution shell

    International Nuclear Information System (INIS)

    Barcellos, C.S. de.

    1980-01-01

    Aim to estimate the behavior of the cove barrel of PWR type reactors, submitted to several load conditions, their dynamic characteristic, were determined. In order to obtain the natural modes and frequencies of the core barrel, the CYLDYFE comprete code based in the finite element method, was developed. The obtained results are compared with results obtained by other programs such as SAP, ASKA and STRUDL/DYNAL and by other analytical methods. (M.C.K.) [pt

  10. Performance of static var compensator control type thyristor controlled reactor and thyristor switched capacitor

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Josias M. de; Yung, Chou Shaw; Rose, Eber H.; Pantoja, Antonio L.A. [ELETRONORTE, Belem, PA (Brazil); Fouesnant, Thomas; Boissier, Luc

    1994-12-31

    This paper has the objective of presenting the philosophy of Static Var Compensator (SVC) Control as well the necessary adjustments in the project of control system to guarantee suitable performance under different operating conditions. The verification on the performance of the SVC control has been done by Transient Network Analyzer (TNA/CEPEL) studies, commissioning tests and a factory tests. The SVC is the type of Thyristor Controlled Reactor (TCR) and Thyristor Switched Capacitor (TSC). (author) 3 refs., 12 figs.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-01-15

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

  12. Progress of design studies on an LHD-type steady-state reactor

    Energy Technology Data Exchange (ETDEWEB)

    Motojima, O.; Komori, A.; Sagara, A. [National Institute for Fusion Science, Toki (Japan)

    2007-07-01

    Helical Heliotrons such as the Large Helical Device (LHD) and Stellarators (H and S systems) have a high potential to realize a current-less steady-state and stable magnetic fusion energy reactor as an alternative to the tokamak DEMO-reactor. H and S systems ideally have an intrinsic property of Q=infinite. Here it is very important to remember that the understanding of the physics of 3-D toroidal magnetic confinement system is naturally extended to tokamak systems. The physics is universal among these two types of systems and the technology is common. We present our recent results from LHD experiments and reactor studies of a next generation LHD-type DEMO Reactor called FFHR. (1) Development of 3-D superconducting (SC) coil technology Due to the successful results of the LHD construction from 1990 to 2007, and steady operation over 8 years from 1998 to 2007, more than 2,000 hrs/year at a high field of around 3 Tesla, we have a large enough data base to demonstrate that 3D coil technology has become the standard technology for a fusion energy reactor. LHD is the largest SC fusion device in the world, contributing to the development of the SC technology necessary for fusion research. The poloidal coils of LHD adopted a super critical forced flow cooling system and their dimensions are almost the same as the ITER toroidal coils. (2) Extended physics understanding of high beta, high T, high n{sub {tau}}{sub T}, and steady state operation Recent LHD experiments have demonstrated the broad and advanced capabilities of LHD as a toroidal magnetic confinement device, which are highlighted by the achievements of 5% volume averaged beta, electron and ion temperatures of 10 keV, super high density of 10E15/cc and 1 hr discharges. We plan to increase the heating power up to 35 MW, and to use deuterium gas for confinement improvement. The n{sub {tau}}{sub T} will be improved to the design nominal value of Q=0.3 within several years and ultimately would approach unity. The key

  13. Thermal-Hydraulic Experiment To Test The Stable Operation Of A PIUS Type Reactor

    International Nuclear Information System (INIS)

    Irianto, Djoko; Kanji, T.; Kukita, Y.

    1996-01-01

    An advanced type of reaktor concept as the Process Inherent Ultimate Safety (PIUS) reactor was based on intrinsically passive safety considerations. The stable operation of a PIUS type reactor is based on the automation of circulation pump speed. An automatic circulation pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed the PIUS-type reactor. In principle this control system maintains the fluid temperature at the axial center of the lower density lock at average of the fluid temperatures below and above the lower density lock. This control system will prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments using atmospheric pressure thermal-hydraulic test loop which simulated the PIUS principle. The experiments such as: start-up and power ramping tests for normal operation simulation and loss of feedwater test for an accident condition simulation, carried out in JAERI

  14. Study of behaviour of radioactive iodine inorganic compounds in PWR type reactor loops

    International Nuclear Information System (INIS)

    Alm, M.; Johannsen, K.-H.; Dreyer, R.

    1980-01-01

    Compounds of radioactive iodine and its distribution between water and vapour depending on temperature, pressure and water regime of reactor coolant with water under pressure are investigated. The field of variation of parameters indicated is widened as compared with operating reactor parameters (pressure 2-14 MPa, temperature 210-335 deg C). Distribution of iodine compounds has been studied by a statistical method. For WWER-type reactors the following conclusions have been drawn: radioactive iodine in water and vapor in the first and second loops exists in the form of iodide, radioactive iodine concentration in water vapour at constant temperature and pressure mainly is depended on water pH value, radioactive iodine solubility in water vapor at normal parameters of the reactor first loop can be approximately calculated by the equation: Ksub(d)=Csub(g)/Csub(l)=(rhosub(g)/rhosub(l))sup(2), where Ksub(d) is a coefficient of solid distribution between water and vapour, rho is density c is concentration [ru

  15. Progress of design studies on an LHD-type steady state reactor

    Energy Technology Data Exchange (ETDEWEB)

    Motojima, O. [National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292 (Japan)], E-mail: motojima@LHD.nifs.ac.jp; Komori, A.; Sagara, A.; Yamada, H. [National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292 (Japan); Mitarai, O. [Kyushu Tokai University, 9-1-1 Toroku, Kumamoto 862-8652 (Japan); Sakamoto, R.; Miyazawa, J.; Kobayashi, M.; Morisaki, T.; Masuzaki, S.; Imagawa, S.; Kozaki, Y.; Tanaka, T. [National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292 (Japan)

    2008-12-15

    Progress of design studies on a heliotron reactor is reported. Recent experimental achievements in large helical device (LHD) are building up the physical basement. Integrated designs on LHD-type energy reactors have improved the base design of force free helical reactor and revealed economical feasibility. Large helical device is exploring a new horizon of net current free helical plasmas. Inherent characteristics demonstrate reactor relevant performances individually; steady state (1 h), high beta (5%), high density (1 x 10{sup 21} m{sup -3}), etc. In particular, discovery of internal diffusion barrier provides a novel attractive scenario of super high density operation. It greatly facilitates physical requirements as well as mitigates engineering demands. New methods have been proposed to access and operate ignited plasmas; a long rise-up over 300 s to reduce the heating power to 30 MW and a new proportional-integration-derivative (PID) control of the fueling to handle the thermally unstable plasma at high-density operations.

  16. Development of Regulatory Technical Requirements for the Advanced Integral Type Research Reactor

    International Nuclear Information System (INIS)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik; Kim, Hho Jung

    2004-01-01

    This paper presents the current status of the study on the development of regulatory technical requirements for the licensing review of an advanced integral type research reactor of which the license application is expected in a few years. According to the Atomic Energy Act of Korea, both research and education reactors are subject to the technical requirements for power reactors in the licensing review. But, some of the requirements may not be applicable or insufficient for the licensing reviews of reactors with unique design features. Thus it is necessary to identify which review topics or areas can not be addressed by the existing requirements and to develop the required ones newly or supplement appropriately. Through the study performed so far, it has been identified that the following requirements need to be developed newly for the licensing review of SMART-P: the use of proven technology, the interfacial facility, the non-safety systems, and the metallic fuels. The approach and basis for the development of each of the requirements are discussed. (authors)

  17. The working lifetime of nuclear power plants and new types of power reactors

    International Nuclear Information System (INIS)

    Bataille, Ch.; Birraux, C.

    2003-01-01

    The report on the working lifetime of nuclear power plants and new reactor types, by Mr Christian Bataille, deputy for the Nord, and Mr Claude Birraux, deputy for Haute-Savoie as well as President of the Office, supplements the studies carried out by the Parliamentary Office on the Safety of Nuclear Installations and Radioactive Wastes: it examines the remaining working life of the EDF nuclear power plants and the current status of projects that might, if circumstances were right, replace the reactors at present in service. The report investigates the different physical and other factors that influence the ageing of nuclear power plants and tackles the question of whether the design life of 40 years could be exceeded in practice. The whole issue of French nuclear power plant is put in perspective and compared with the situation of nuclear plants in Finland, Sweden, Germany and the United States, from the technical and regulatory standpoints. Believing that any attempt to optimise the working lifetime of the power plants currently in service must be accompanied by simultaneous moves aimed at their replacement, Messrs. Christian Bataille and Claude Birraux go on to review in detail the various light water reactor projects being proposed around the world for completion by 2015, as developments of existing models, in particular the EPR reactor of Framatome ANP, characterised by its competitiveness. They suggest that a first such reactor should be built as quickly as possible. Describing the other nuclear systems being investigated by research organisations not only in France but also in the United States and Sweden, Mrs. Christian Bataille and Claude Birraux review the objectives of these and the circumstances in which they might be developed, which would be unlikely to be before 2035 in view of the technological problems to be overcome and the industrial demonstration plants that would be needed

  18. Evaluation of Advanced Thermohydraulic System Codes for Design and Safety Analysis of Integral Type Reactors

    International Nuclear Information System (INIS)

    2014-02-01

    The integral pressurized water reactor (PWR) concept, which incorporates the nuclear steam supply systems within the reactor vessel, is one of the innovative reactor types with high potential for near term deployment. An International Collaborative Standard Problem (ICSP) on Integral PWR Design, Natural Circulation Flow Stability and Thermohydraulic Coupling of Primary System and Containment during Accidents was established in 2010. Oregon State University, which made available the use of its experimental facility built to demonstrate the feasibility of the Multi-application Small Light Water Reactor (MASLWR) design, and sixteen institutes from seven Member States participated in this ICSP. The objective of the ICSP is to assess computer codes for reactor system design and safety analysis. This objective is achieved through the production of experimental data and computer code simulation of experiments. A loss of feedwater transient with subsequent automatic depressurization system blowdown and long term cooling was selected as the reference event since many different modes of natural circulation phenomena, including the coupling of primary system, high pressure containment and cooling pool are expected to occur during this transient. The power maneuvering transient is also tested to examine the stability of natural circulation during the single and two phase conditions. The ICSP was conducted in three phases: pre-test (with designed initial and boundary conditions established before the experiment was conducted), blind (with real initial and boundary conditions after the experiment was conducted) and open simulation (after the observation of real experimental data). Most advanced thermohydraulic system analysis codes such as TRACE, RELAPS and MARS have been assessed against experiments conducted at the MASLWR test facility. The ICSP has provided all participants with the opportunity to evaluate the strengths and weaknesses of their system codes in the transient

  19. Inteligencias múltiples y rendimiento en fútbol

    Directory of Open Access Journals (Sweden)

    José Mª del Pino Medina

    2015-08-01

    Full Text Available El propósito de este estudio ha sido intentar determinar la existencia de un perfil de inteligencia típico para futbolistas en general, y específico por demarcaciones, desde los postulados que ofrece la teoría de las inteligencias múltiples de Howard Gardner. Para ello, 37 futbolistas y cuerpo técnico de dos clubes, cumplimentaron una serie de cuestionarios para fijar los términos referidos: a perfil de inteligencias múltiples, y b percepción de competencia deportiva. Se sometieron al test de campo de Course Navette para delimitar su Potencia aeróbica máxima y el VO2 máx. Se codifican los estadísticos de competición para cada uno de los deportistas, al objeto de delimitar el perfil de IM asociado al rendimiento deportivo para futbolistas, y analizar la incidencia de cada tipo de inteligencia con los factores de eficacia coligados a la competencia deportiva en esta disciplina. Se identifica un perfil típico de IM para futbolistas con escasa incidencia en el rendimiento en fútbol.

  20. Optimized Core Design and Fuel Management of a Pebble-Bed Type Nuclear Reactor

    International Nuclear Information System (INIS)

    Boer, Brian

    2007-01-01

    The Very High Temperature Reactor (VHTR) has been selected by the international Generation IV research initiative as one of the six most promising nuclear reactor concepts that are expected to enter service in the second half of the 21st century. The VHTR is characterized by a high plant efficiency and a high fuel discharge burnup level. More specifically, the (pebble-bed type) High Temperature Reactor (HTR) is known for its inherently safe characteristics, coming from a negative temperature reactivity feedback, a low power density and a large thermal inertia of the core. The core of a pebble-bed reactor consists of graphite spheres (pebbles) that form a randomly packed porous bed, which is cooled by high pressure helium. The pebbles contain thousands of fuel particles, which are coated with several pyrocarbon and silicon carbon layers that are designed to contain the fission products that are formed during operation of the reactor. The inherent safety concept has been demonstrated in small pebble-bed reactors in practice, but an increase in the reactor size and power is required for cost-effective power production. An increase of the power density in order to increase the helium coolant outlet temperature is attractive with regard to the efficiency and possible process heat applications. However, this increase leads in general to higher fuel temperatures, which could lead to a consequent increase of the fuel coating failure probability. This thesis deals with the pebble-bed type VHTR that aims at an increased coolant outlet temperature of 1000 degrees C and beyond. For the simulation of the neutronic and thermal-hydraulic behavior of the reactor the DALTON-THERMIX coupled code system has been developed and has been validated against experiments performed in the AVR and HTR-10 reactors. An analysis of the 400 MWth Pebble Bed Modular Reactor (PBMR) design shows that the inherent safety concept that has been demonstrated in practice in the smaller AVR and HTR-10

  1. Importance of helical pitch parameter in LHD-type heliotron reactor designs

    International Nuclear Information System (INIS)

    Goto, T.; Suzuki, Y.; Yanagi, N.; Watanabe, K.Y.; Imagawa, S.; Sagara, A.

    2010-11-01

    In the design studies of the LHD-type heliotron reactors, one of the key issues is to secure sufficient blanket spaces. In this respect, helical pitch parameter γ is quite important because it significantly affects both the coil and plasma shapes. In order to understand the effect of helical pitch parameter on the design window quantitatively, a system design code for the LHD-type heliotron reactors has been developed and parametric scans were carried out with 3 cases of γ=1.15, 1.20 and 1.25. It becomes clear that the possible design window of heliotron reactors strongly depends on the engineering constraints: stored magnetic energy of coil system, blanket space, and neutron wall load. γ=1.20 is optimum from the viewpoint of moderating the physics requirements, but γ=1.15 has a robustness to the change in the physics and engineering conditions. Since the design windows are quite sensitive to the engineering constraints and physics conditions, the further detailed study on design feasibility of advanced engineering components and the effect of γ on the physics conditions is expected to optimize the value of γ. (author)

  2. Deployable nuclear fleet based on available quantities of uranium and reactor types – the case of fast reactors started up with enriched uranium

    Directory of Open Access Journals (Sweden)

    Baschwitz Anne

    2016-01-01

    Full Text Available International organizations regularly produce global energy demand scenarios. To account for the increasing population and GDP trends, as well as to encompass evolving energy uses while satisfying constraints on greenhouse gas emissions, long-term installed nuclear power capacity scenarios tend to be more ambitious, even after the Fukushima accident. Thus, the amounts of uranium or plutonium needed to deploy such capacities could be limiting factors. This study first considers light-water reactors (LWR, GEN III using enriched uranium, like most of the current reactor technologies. It then examines the contribution of future fast reactors (FR, GEN IV operating with an initial fissile load and then using depleted uranium and recycling their own plutonium. However, as plutonium is only available in limited quantity since it is only produced in nuclear reactors, the possibility of starting up these Generation IV reactors with a fissile load of enriched uranium is also explored. In one of our previous studies, the uranium consumption of a third-generation reactor like an EPR™ was compared with that of a fast reactor started up with enriched uranium (U5-FR. For a reactor lifespan of 60 years, the U5-FR consumes three times less uranium than the EPR and represents a 60% reduction in terms of separative work units (SWU, though its requirements are concentrated over the first few years of operation. The purpose of this study is to investigate the relevance of U5-FRs in a nuclear fleet deployment configuration. Considering several power demand scenarios and assuming different finite quantities of available natural uranium, this paper examines what types of reactors must be deployed to meet the demand. The deployment of light-water reactors only is not sustainable in the long run. Generation IV reactors are therefore essential. Yet when started up with plutonium, the number of reactors that can be deployed is also limited. In a fleet deployment

  3. Optimal conditions in direct dimethyl ether synthesis from syngas utilizing a dual-type fluidized bed reactor

    International Nuclear Information System (INIS)

    Yousefi, Ahmad; Eslamloueyan, Reza; Kazerooni, Nooshin Moradi

    2017-01-01

    Concerns over environmental pollution and ever-increasing energy demand have urged the global community to tap clean-burning fuels among which dimethyl ether is a promising candidate for contribution in the transportation sector. Direct dimethyl ether synthesis from syngas, in which methanol production and dehydration take place simultaneously, is arguably the preferred route for large scale production. In this study, direct dimethyl ether synthesis is proposed in an industrial dual-type fluidized bed reactor. This configuration involves two fluidized bed reactors operating in different conditions. In the first catalytic reactor (water-cooled reactor), the synthesis gas is partly converted to methanol after being preheated by the reaction heat in the second reactor (gas-cooled reactor). A two-phase generalized comprehensive reactor model, comprised of the flow in three different regimes is applied and a smooth transition between flow regimes is provided based on the probabilistic averaging approach. The optimal operating conditions are sought by employing differential evolution algorithm as a robust optimization strategy. The dimethyl ether mole fraction is considered as the objective function during the optimization. The results show considerable dimethyl ether enhancement by 16% and 14% compared to the conventional direct dimethyl ether synthesis reactor and dual-type fixed bed dimethyl ether reactor arrangements, respectively. - Highlights: • Dual-type catalytic fluidized bed reactors for dimethyl ether synthesis is studied. • A two-phase comprehensive model comprised of flow in three regimes is used. • Probabilistic averaging approach is applied for smooth transitions between regimes. • Differential evolution method is employed to determine optimal operating conditions. • Production capacity is remarkably enhanced compared to conventional reactor.

  4. Small scale thermal-hydraulic experiment for stable operation of a pius-type reactor

    International Nuclear Information System (INIS)

    Tasaka, K.; Tamaki, M.; Imai, S.; Irianto, I.D.; Tsuji, Y.; Kukita, Y.

    1994-01-01

    Thermal-hydraulic experiments using a small-scale atmospheric pressure test loop have been performed for the Process Inherent Ultimate Safety (PIUS)-type reactor to develop the new pump speed feedback control system. Three feedback control systems based on the measurement of flow rate, differential pressure, and fluid temperature distribution in the lower density lock have been proposed and confirmed by a series of experiments. Each of the feedback control systems had been verified in the simulation experiment such as a start-up simulation test. The automatic pump speed control based on the fluid temperature at the lower density lock was quite effective to maintain the stratified interface between primary water and borated pool water for stable operation of the reactor. (author)

  5. Numerical investigation of the coolant mixing during fast deboration transients for VVER-440 type reactors

    International Nuclear Information System (INIS)

    Hoehne, T.; Rhode, U.

    2000-01-01

    The VVER-440 (440 MW) V-230 was considered for analyzing the flow field and mixing processes. The V-230 has no elliptical sieve plate in the lower plenum. Previously, the 3D flow distribution in the downcomer and the lower plenum of the VVER-440 reactor have been calculated by means of the CFD code CFX-4 for operational conditions. The CFX-calculations were compared with the experimental data and the analytical mixing model. In this paper, CFD calculations for the start-up of the first main coolant pump in a VVER-440 type reactor are reported about. This scenario is important in case that there is a plug of lower borated water in one of the primary coolant loops. (orig.)

  6. The use of the codes from MCU family for calculations of WWER type reactors

    International Nuclear Information System (INIS)

    Abagijan, L.P.; Alexeyev, N.I.; Bryzgalov, V.I.; Gomin, E.A.; Glushkov, A.E.; Gorodkov, S.S.; Gurevich, M.I.; Kalugin, M.A.; Marin, S.V.; Shkarovsky, D.A.; Yudkevich, M.S.

    2000-01-01

    The MCU-RFFI/A and MCU-REA codes developed within the framework of the long term MCU project are widely used for calculations of neutron physic characteristics of WWER type reactors. Complete descriptions of the codes are available in both Russian and English. The codes are verified and validated by means of the comparison of calculated results with experimental data and mathematical benchmarks. The codes are licensed by Russian Nuclear and Criticality Safety Regulatory Body (Gosatomnadzor RF) (Code Passports: N 61 of 17.10.1966 and N 115 of 02.03.2000 accordingly)). The report gives examples of WWER reactor physic tasks important for practice solved using the codes from the MCU family. Some calculational results are given too. (Authors)

  7. Reactor type choice and characteristics for a small nuclear heat and electricity co-generation plant

    International Nuclear Information System (INIS)

    Liu Kukui; Li Manchang; Tang Chuanbao

    1997-01-01

    In China heat supply consumes more than 70 percent of the primary energy resource, which makes for heavy traffic and transportation and produces a lot of polluting materials such as NO x , SO x and CO 2 because of use of the fossil fuel. The utilization of nuclear power into the heat and electricity co-generation plant contributes to the global environmental protection. The basic concept of the nuclear system is an integral type reactor with three circuits. The primary circuit equipment is enclosed in and linked up directly with reactor vessel. The third circuit produces steam for heat and electricity supply. This paper presents basic requirements, reactor type choice, design characteristics, economy for a nuclear co-generation plant and its future application. The choice of the main parameters and the main technological process is the key problem of the nuclear plant design. To make this paper clearer, take for example a double-reactor plant of 450 x 2MW thermal power. There are two sorts of main technological processes. One is a water-water-steam process. Another is water-steam-steam process. Compared the two sorts, the design which adopted the water-water-steam technological process has much more advantage. The system is simplified, the operation reliability is increased, the primary pressure reduces a lot, the temperature difference between the secondary and the third circuits becomes larger, so the size and capacity of the main components will be smaller, the scale and the cost of the building will be cut down. In this design, the secondary circuit pressure is the highest among that of the three circuits. So the primary circuit radioactivity can not leak into the third circuit in case of accidents. (author)

  8. 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

  9. Relaciones entre afrontamiento del estrés cotidiano, autoconcepto, habilidades sociales e inteligencia emocional

    OpenAIRE

    Francisco Manuel Morales Rodríguez

    2017-01-01

    Existen menos estudios sobre estrategias de afrontamiento del estrés cotidiano y factores asociados como autoconcepto e inteligencia emocional en nuestro contexto. Este estudio analiza las relaciones entre estrategias de afrontamiento y los factores autoconcepto, habilidades sociales e inteligencia emocional. Se evaluaron las diferentes estrategias de afrontamiento del estrés cotidiano, autoconcepto, habilidades sociales e inteligencia emocional. La muestra se compuso de 154 estudiantes de Ed...

  10. Design and development of face seal type sealing plug for advanced heavy water reactor

    International Nuclear Information System (INIS)

    Bansal, S.; Bhattacharyya, S.; Patel, R.J.; Agrawal, R.G.; Vaze, K.K.

    2005-09-01

    Advanced Heavy Water Reactor is a vertical pressure tube type reactor having light water as its coolant and heavy water as moderator. Sealing plug is required to close the pressure boundary of main heat transport system of the reactor by preventing escape of light water/steam From the coolant channel. There are 452 coolant channels in the reactor located in square lattice pitch. Sealing plug is located at the top of each coolant channel (in the top end fitting). Top end fitting is having a stepped bore to create a sealing face. Sealing plug is held through its expanded jaws in a specially provided groove of the end fitting. The plug was designed and prototypes were manufactured considering its functional importance, intricate design and precision machining requirements. Sealing plug consists of about 20 components mostly made up of precipitation hardening stainless steel, which is suitable for water environment and meets other requirements of strength and resistance to wear and galling. Seal disc is a critical component of the sealing plug as it is the pressure-retaining component. It is a circular disc with protruded stem. One face of the seal disc is nickel plated in the peripheral area that creates the sealing by abutting against the sealing face provided in the end fitting. The typical shape and profile of seal disc provides flexibility and allows elastic deformation to assist in locking of sealing plug and creating adequate seating force for effective sealing. Design and development aspects of the sealing plug have been detailed out in this report. Also results of stress analysis and experimental studies for seal disc have been mentioned in the report. Stress analysis and experimental testing was required for the seal disc because high stresses are developed due to its exposure to high pressure and temperature environment of Main Heat Transport system. Hot testing was carried out to simulate the reactor-simulated condition. The performance was found to be

  11. Contact-type displacement measuring mechanism for fuel assembly in reactor

    International Nuclear Information System (INIS)

    Yokota, Yoshio; Ko, Kuniaki.

    1995-01-01

    The measuring mechanism of the present invention, which is used in a lmfbr type reactor, is suspended by a gripper of a fuel handing machine, and it comprises a combination of a displacement amount measuring jig allowed to be inserted into a handling head of a fuel assembly and a displacement amount measuring ring disposed at the lower portion in the handling head. The displacement amount measuring jig has a structure comprising a releasable handle and a columnar or cylindrical measuring portion allowable to be inserted into the handling head formed at the lower portion of the handle, which are connected with each other. When an interference (contact) occurred between the displacement amount measuring jig and the stepwise displacement amount measuring ring during the measurement, change of load and a phenomenon that the fuel handing machine can not be lowered are recognized, so that core displacement amount can be recognized based on the stroke of the gripper portion. Then, remote measurement is possible for displacement and deformation of the fuel assembly in the reactor container, and the measurement can be conducted by the same procedures and in the same period of time as in a case of ordinary fuel exchange operation. A flow channel for coolants passing through the fuel assembly can be ensured, thereby enabling to measure the amount of core displacement which is closer to an actual value in the reactor. (N.H.)

  12. A master-follower type distributed scheme for reactor inlet temperature control

    International Nuclear Information System (INIS)

    Garcia, H.E.; Dean, E.M.; Vilim, R.B.

    1995-01-01

    This paper describes the implementation of a computer-based controller for regulating reactor inlet temperature in a pool-type power plant. The elements of the control system are organized in a master-follower hierarchical architecture that takes advantage of existing in-plant hardware and software to minimize the need for plant modifications. Low level control algorithms are executed on existing local digital controllers (followers) with the high level algorithms executed on a new plant supervisory computer (master). A distributed computing strategy provides integration of the existing and additional computer platforms. The control system operates by having the master controller first estimate the secondary sodium flow needed to achieve a given reactor inlet temperature. The estimated flow is then used as a setpoint by the follower controller to regulate sodium flow using a motor-generator pump set. The control system has been implemented in a Hardware-In-the-Loop (FM) setup and qualified for operation in the Experimental Breader reactor 11 of Argonne National Laboratory. Some HIL results are provided

  13. Optimization activities on design studies of LHD-type reactor FFHR

    Energy Technology Data Exchange (ETDEWEB)

    Sagara, A. [National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu 509-5292 (Japan)], E-mail: sagara.akio@LHD.nifs.ac.jp; Mitarai, O. [Tokai University, 9-1-1 Toroku, Kumamoto 862-8652 (Japan); Tanaka, T.; Imagawa, S.; Kozaki, Y.; Kobayashi, M.; Morisaki, T.; Watanabe, T.; Takahata, K.; Tamura, H.; Yanagi, N.; Nishimura, K.; Chikaraishi, H.; Yamada, S. [National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu 509-5292 (Japan); Fukada, S. [Kyushu University, 6-10-1 Hakozaki, Fukuoka 812-8581 (Japan); Masuzaki, S. [National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu 509-5292 (Japan); Shishkin, A. [Kharkov Institute of Physics and Technology, Kharkov-108 (Ukraine); Igitkhanov, Y. [Max-Planck-Institute fuer Plasmaphysik, IPP-EURATOM Ass., Greifswald (Germany); Goto, T.; Ogawa, Y. [University of Tokyo, 5-1-5 Kashiwa, Chiba 277-8568 (Japan)] (and others)

    2008-12-15

    Recent activities on optimizing the base design of the large helical device (LHD)-type helical reactor FFHR (force free helical reactor) are presented. Three candidates to secure the blanket space are proposed with the aim of reactor size optimization without deteriorating {alpha}-heating efficiency and by taking cost analyses into account. In this way the key engineering aspects are investigated; from 3D blanket designs, it is demonstrated that the peaking factor of the neutron wall loading is 1.2-1.3 and a blanket covering ratio of over 90% is possible by proposing discrete pumping with a semi-closed shield (DPSS) concept. Helical blanket shaping along the divertor field lines is the next big issue. For large superconducting magnet systems under the maximum nuclear heating of 200 W/m{sup 3}, cable-in-conduit conductor (CICC) and alternative conductor designs are proposed with a robust design of cryogenic support posts. For access to ignited plasmas, new methods are proposed, in which a long rise-up time over 300 s reduces the heating power to 30 MW and a new proportional-integration-derivative (PID) control of the fueling can handle the thermally unstable plasma at high-density operation. This paper focuses on FFHR2m1, which is a modified version of FFHR.

  14. Organization and mechanization of maintenance operations at NPPs with the WWER type reactors

    International Nuclear Information System (INIS)

    Titov, A.A.

    1983-01-01

    The structure of capital investments defining organization and mechanization of maintepance operations at NPPs with the WWER type reactors is analyzed. The trends in development of optimum decisions for organization and mechanization of repair obs at NPPs being designed taking into account the prospects of nuclear powep enginerning development, the system of NPP maintenance servicing, as well as the structure of repair-productive capacities are discussed. On the basis of the analysis of the data obtained in designing the Zaporozhskaya NPP it is shown that the capital investments for organizing and mechanization of maintenance operations at the unified NPP site with four WWER-1000 reactors reach nearly 18 roubles/kW. A conclusion is drawn that at present the design of an NPP with the WWER-1000 reactor totally meets the requirements of realization of periodic maintenance operations. It is advisable to cooperate the NPP management with that of a thermal power station from the viewpoint of using manpower, which would improve the operating conditions and labour productivity of workers engaged in repair and, consequently, reduce the capital investments and repair expenditures

  15. Reliability assessment of emergency exhaust system in a pool-type research reactor

    International Nuclear Information System (INIS)

    Khan, S.A.

    1991-01-01

    The reliability of an extract system in a swimming-pool-type research reactor has been assessed. A global fault-tree analysis technique has been utilized. The basic event reliability data is based on both generic and reactor specific informations. The unavailability of the extract system is quantified in terms of the unavailability of the various functional requirements of the system. The unavailability is expressed as the probability of failure on demand. The computer system unavailability is determined from the minimal cutsets of the system. It is found that only three events have a major contribution to the top event, i.e., failures of compressed air supply, electric power supply and solenoid valve. A sensitivity analysis is performed to show the effects of variations in the data values of the dominant cutsets. An uncertainty analysis was also performend on the fault tree. The evaluations show that the reactor extract system lacks diversity and redundance in most of its components. It is tolerant of most minor degradations, as these are taken care of by the operating policies and procedures. However, it can not tolerate common cause failures, e.g. simultaneous compressed air and electric power supply failure. Based upon the results obtained, some recommendations are made. (orig.)

  16. Numerical analysis of coolant mixing in the pressure vessel of WWER-440 type nuclear reactors

    International Nuclear Information System (INIS)

    Boros, I.; Aszodi, A.

    2003-01-01

    The precise description of the coolant mixing processes taking place in the reactor pressure vessel (RPV) of pressurized water nuclear reactors has an essential importance during power operation, as well as in case of incidental or accidental conditions. In this paper the detailed CFD model of the pressure vessel of a WWER-440 type reactor and calculations performed with this RPV model are presented. The CFD model of the pressure vessel contains all the important internal structural elements of the RPV. Sensitivity study on the effect of these elements was also carried out. Both steady-state and transient calculation were performed using the CFD code CFX-5.5.1. The results of the steady-state calculations give the so called mixing factors, i.e. the effect of each single primary loop at the core inlet. The mixing factors can be given for nominal circumstances (i.e. all main coolant pumps are working) or in case of less than six working MCPs. In order to validate the model the calculated mixing factors are compared with the values measured in the Paks NPP (Authors)

  17. PWR type reactor equipped with a primary circuit loop water level gauge

    International Nuclear Information System (INIS)

    Suzuki, Mitsuhiro.

    1990-01-01

    The time of lowering a water level to less than the position of high temperature side pipeway nozzle has been rather delayed because of the swelling of mixed water level due to heat generation of the reactor core. Further, there has been a certain restriction for the installation, maintenance and adjustment of a water level gauge since it is at a position under high radiation exposure. Then, a differential pressure type water level gauge with temperature compensation is disposed at a portion below a water level gauge of a pressurizer and between the steam generator exit plenum and the lower end of the loop seal. Further, a similar water level system is disposed to all of the loops of the primary circulation circuits. In a case that the amount of water contained in a reactor container should decreased upon occurrence of loss of coolant accidents caused by small rupture and stoppage of primary circuit pumps, lowering of the water level preceding to the lowering of the water level in the reactor core is detected to ensure the amount of water. Since they are disposed to all of the loops and ensure the excess margin, reliability for the detection of the amount of contained water can be improved by averaging time for the data of the water level and averaging the entire systems, even when there are vibrations in the fluid or pressure in the primary circuit. (N.H.)

  18. Comunidades virtuales y producción de inteligencia económica y competitiva

    OpenAIRE

    Carvalho, Andrea Vasconcelos

    2007-01-01

    CARVALHO, Andréa Vasconcelos . Comunidades virtuales y producción de inteligencia económica y competitiva. Inteligencia y Seguridad: revista de análisis y prospectiva, v. 3, p. 13-45, 2007 Se defiende que las comunidades virtuales ofrecen información útil para la generación de inteligencia económica y competitiva. Así, se identifican y describen las principales aplicaciones de las comunidades virtuales para la producción de estos tipos de inteligencia. Sin embargo, no se disponen...

  19. INTELIGENCIA MUSICAL, RENDIMIENTO ESCOLAR Y DESARROLLO INTEGRAL EN EDUCACIÓN PRIMARIA

    OpenAIRE

    de la Villa-Santotomás, Lorena

    2014-01-01

    Con esta investigación se pretende diseñar un programa de intervención para mejorar la inteligencia musical y la discriminación auditiva, potenciando el rendimiento escolar y el resto de inteligencias. En primer lugar, se utilizó una muestra de 30 alumnos de segundo de Primaria. Se analizó el nivel de desempeño de las distintas inteligencias a través del Cuestionario de Inteligencias Múltiples (Armstrong, 2001). En segundo lugar, se evaluó el nivel de discriminación auditiva co...

  20. Inteligencia emocional y ansiedad en estudiantes universitarios

    Directory of Open Access Journals (Sweden)

    Ubaldo Rodríguez de Ávila

    2011-07-01

    Full Text Available Abstract This research paper presents the results of a study about the relationship between Perceived Emotional Intelligence and the State-Trait Anxiety psychology students in a public university in Magdalena, Colombia. The investigation was developed from the descriptive-correlational design through the application of the instruments TMMS-24 and INDARE to 167 subjects. The results indicated that there is direct and significant relationship between emotional perception and state anxiety and trait anxiety. By contrast, there was a significant inverse relationship between emotional understanding and state anxiety and trait anxiety, and also between emotional regulation and state anxiety and trait anxiety. Through statistical analysis with Chi2, dependence was also found between the sub-variables with a significance level less than 0.05. Resumen El presente artículo de investigación presenta los resultados de un estudio acerca de la relación entre la Inteligencia Emocional Percibida y la Ansiedad Rasgo-Estado en estudiantes de Psicología de una universidad pública del Magdalena, Colombia. La investigación se desarrolló a partir del diseño descriptivo-correlacional a través de la aplicación de los instrumentos TMMS-24 y el IDARE a 167 sujetos. Los resultados indicaron que existe relación directa y significativa entre la percepción emocional y la ansiedad estado y la ansiedad rasgo. Por el contrario, se presentó una relación inversa y significativa entre la comprensión emocional y la ansiedad estado y la ansiedad rasgo; igualmente entre la regulación emocional y la ansiedad estado y la ansiedad rasgo. A través del análisis con el estadístico Chi2, también se encontró dependencia entre las sub-variables estudiadas con un nivel de significancia menor de 0.05.

  1. Linear pulse motor type control element drive mechanism for the integral reactor

    International Nuclear Information System (INIS)

    Yu, J. Y.; Choi, S.; Kim, J. H.; Huh, H.; Park, K. B.

    2007-01-01

    The integral reactor SMART currently under development at Korea Atomic Energy Research Institute is designed with soluble boron free operation and use of nuclear heating for reactor startup. These design features require the Control Element Drive Mechanism (CEDM) for SMART to have fine-step movement capability as well as high reliability for the fine reactivity control. In this paper, design characteristics of a new concept CEDM driven by the Linear Pulse Motor (LPM) which meets the design requirements of the integral reactor SMART are introduced. The primary dimensions of the linear pulse motor are determined by the electro-magnetic analysis and the results are also presented. In parallel with the electro-magnetic analysis, the conceptual design of the CEDM is visualized and checked for interferences among parts by assembling three dimensional (3D) models on the computer. Prototype of LPM with double air-gaps for the CEDM sub-assemblies to lift 100 kg is designed, analysed, manufactured and tested to confirm the validity of the CEDM design concept. A converter and a test facility are manufactured to verify the dynamic performance of the LPM. The mover of the LPM is welded with ferromagnetic material and non-ferromagnetic material to get the magnetic flux path between inner stator and outer stator. The thrust forces of LPM predicted by analytic model have shown good agreement with experimental results from the prototype LPM. It is found that the LPM type CEDM has high force density and simple drive mechanism to reduce volume and satisfy the reactor operating circumstances with high pressure and temperature

  2. Improvement of nuclear ship engineering simulation system. Hardware renewal and interface improvement of the integral type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Hiroki; Kyoya, Masahiko; Shimazaki, Junya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kano, Tadashi [KCS, Co., Mito, Ibaraki (Japan); Takahashi, Teruo [Energis, Co., Kobe, Hyogo (Japan)

    2001-10-01

    JAERI had carried out the design study about a lightweight and compact integral type reactor (an advanced marine reactor) with passive safety equipment as a power source for the future nuclear ships, and completed an engineering design. We have developed the simulator for the integral type reactor to confirm the design and operation performance and to utilize the study of automation of the reactor operation. The simulator can be used also for future research and development of a compact reactor. However, the improvement in a performance of hardware and a human machine interface of software of the simulator were needed for future research and development. Therefore, renewal of hardware and improvement of software have been conducted. The operability of the integral-reactor simulator has been improved. Furthermore, this improvement with the hardware and software on the market brought about better versatility, maintainability, extendibility and transfer of the system. This report mainly focuses on contents of the enhancement in a human machine interface, and describes hardware renewal and the interface improvement of the integral type reactor simulator. (author)

  3. Optimization of seed-blanket type fuel assembly for reduced-moderation water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Shelley, Afroza; Shimada, Shoichiro; Kugo, Teruhiko; Okubo, Tsutomu E-mail: okubo@hems.jaeri.go.jp; Iwamura, Takamichi

    2003-10-01

    Parametric studies have been performed for a PWR-type reduced-moderation water reactor (RMWR) with the seed-blanket type fuel assembles to achieve a high conversion ratio, negative void reactivity coefficient and a high burnup by using MOX fuel. From the viewpoint of reactor safety analysis, the fuel temperature coefficients were also studied. From the result of the burnup calculation, it has been seen that ratio of 40-50% of outer blanket in a seed-blanket assembly gives higher conversion ratio compared to the other combination of seed-blanket assembly. And the recommended number of (seed+blanket) layers is 20, in which the number of seed (S) layers is 15 (S15) and blanket (B) layers is 5 (B5). It was found that the conversion ratio of seed-blanket assembly decreases, when they are arranged looks like a flower shape (Hanagara). By the optimization of different parameters, S15B5 fuel assembly with the height of seed of 1000 mmx2, internal blanket of 150 mm and axial blanket of 400 mmx2 is recommended for a reactor of high conversion ratio. In this assembly, the gap of seed fuel rod is 1.0 mm and blanket fuel rod is 0.4 mm. In S15B5 assembly, the conversion ratio is 1.0 and the burnup is 38.18 GWd/t in (seed+internal blanket+outer blanket) region. However, the burnup is 57.45 GWd/t in (seed+internal blanket) region. The cycle length of the core is 16.46 effective full power in month (EFPM) by six batches and the enrichment of fissile Pu is 14.64 wt.%. The void coefficient is +21.82 pcm/%void, however, it is expected that the void coefficient will be negative if the radial neutron leakage is taken into account in the calculation. It is also possible to use S15B5 fuel assembly as a high burnup reactor 45 GWd/t in (seed+internal blanket+outer blanket) region, however, it is necessary to decrease the height of seed to 500 mmx2 to improve the void coefficient. In this reactor, the conversion ratio is 0.97 and void coefficient is +20.81 pcm/%void. The fuel temperature

  4. Unlimited cooling capacity of the passive-type emergency core cooling system of the MARS reactor

    International Nuclear Information System (INIS)

    Bandini, G.; Caira, M.; Naviglio, A.; Sorabella, L.

    1995-01-01

    The MARS nuclear plant is equipped with a 600 MWth PWR type nuclear steam supply system, with completely innovative engineered core safeguards. The most relevant innovative safety system of this plant is its Emergency Core Cooling System, which is completely passive (with only one non static component). The Emergency Core Cooling System (ECCS) of the MARS reactor is natural-circulation, passive-type, and its intervention follows a core flow decrease, whatever was the cause. The operation of the system is based on a cascade of three fluid systems, functionally interfacing through heat exchangers; the first fluid system is connected to the reactor vessel and the last one includes an atmospheric-pressure condenser, cooled by external air. The infinite thermal capacity of the final heat sink provides the system an unlimited autonomy. The capability and operability of the system are based on its integrity and on the integrity of the primary coolant boundary (both of them are permanently enclosed in a pressurized containment; 100% redundancy is also foreseen) and on the operation of only one non static component (a check valve), with 400% redundancy. In the paper, all main thermal hydraulic transients occurring as a consequence of postulated accidents are analysed, to verify the capability of the passive-type ECCS to intervene always in time, without causing undue conditions of reduced coolability of the core (DNB, etc.), and to verify its capability to guarantee a long-term (indefinite) coolability of the core without the need of any external intervention. (author)

  5. Analysis of the integrity of the pressure vessel of the BWR type nuclear reactor

    International Nuclear Information System (INIS)

    Silva Luna, O.

    1982-01-01

    The presssure vessel of a BWR type reactor was monitored for cracking during alternating events of its in-service life. The monitoring was to determine criticality of fractures catastrophic fractures and the velocity of fracture propagation. Detected cracks were evaluated as specified in ASME code section XI, of a minimum wall thickness of 2.5% crack growths were compared a) of 1/10 of the critical maximum size and b) at in-service inspection intervals according to ASME recommendations to be established at the Laguna Verde nuclear plant. Finally conclusions are made and discussed. (author)

  6. Theoretical model for investigating the dynamic behaviour of the AST-500 type nuclear heating station reactor

    International Nuclear Information System (INIS)

    Grundmann, U.; Rohde, U.; Naumann, B.

    1985-01-01

    Studies on theoretical simulation of the dynamic behaviour of the AST-500 type reactor primary coolant system are summarized. The first version of a dynamic model in the form of the DYNAST code is described. The DYNAST code is based on a one-dimensional description of the primary coolant circuit including core, draught stack, and intermediate heat exchanger, a vapour dome model, and the point model of neutron kinetics. With the aid of the steady-state computational part of the DYNAST code, studies have been performed on different steady-state operating conditions. Furthermore, some methodological investigations on generalization and improvement of the dynamic model are considered and results presented. (author)

  7. Core physics design calculation of mini-type fast reactor based on Monte Carlo method

    International Nuclear Information System (INIS)

    He Keyu; Han Weishi

    2007-01-01

    An accurate physics calculation model has been set up for the mini-type sodium-cooled fast reactor (MFR) based on MCNP-4C code, then a detailed calculation of its critical physics characteristics, neutron flux distribution, power distribution and reactivity control has been carried out. The results indicate that the basic physics characteristics of MFR can satisfy the requirement and objectives of the core design. The power density and neutron flux distribution are symmetrical and reasonable. The control system is able to make a reliable reactivity balance efficiently and meets the request for long-playing operation. (authors)

  8. Computer programme for calculating LOCA in a pool type nuclear reactor

    International Nuclear Information System (INIS)

    Villanueva, L.

    1982-01-01

    A computer programme has been developed to calculate the loss of coolant accident at the top part of the fuel rod, for a pool type reactor. The following heat transfer modes are considered in the computer code: 1) forced convection in the transition regimes, 2) forced turbulent convection, 3) forced laminar convection, 4) natural convection in water, 5) natural convection in rectangular cells, 6) natural convection in air in partially closed channels, 7) laminar convection in steam, 8) thermal radiation between two parallel plates within the steam, 9) nucleate boiling in standing liquid

  9. Radiological performance of hot water layer system in open pool type reactor

    Directory of Open Access Journals (Sweden)

    Amr Abdelhady

    2013-06-01

    Full Text Available The paper presents the calculated dose rate carried out by using MicroShield code to show the importance of hot water layer system (HWL in 22 MW open pool type reactor from the radiation protection safety point of view. The paper presents the dose rate profiles over the pool surface in normal and abnormal operations of HWL system. The results show that, in case of losing the hot water layer effect, the radiation dose rate profiles over the pool surface will increase from values lower than the worker permissible dose limits to values very higher than the permissible dose limits.

  10. Radiological performance of hot water layer system in open pool type reactor

    OpenAIRE

    Amr Abdelhady

    2013-01-01

    The paper presents the calculated dose rate carried out by using MicroShield code to show the importance of hot water layer system (HWL) in 22 MW open pool type reactor from the radiation protection safety point of view. The paper presents the dose rate profiles over the pool surface in normal and abnormal operations of HWL system. The results show that, in case of losing the hot water layer effect, the radiation dose rate profiles over the pool surface will increase from values lower than th...

  11. On the reliability of steam generator performance at nuclear power plants with WWER type reactors

    International Nuclear Information System (INIS)

    Styrikovich, M.A.; Margulova, T.Kh.

    1974-01-01

    The problem of ensuring reliable operation of steam generators in a nuclear power plant with a water-cooled, water-moderated reactor (WWER) was studied. At a nuclear power plant with a vertical steam generator (specifically, a Westinghouse product) the steam generator tubes were found to have been penetrated. Shutdown was due to corrosion disintegration of the austenitic stainless steel, type 18/8, used as pipe material for the heater surface. The corrosion was the result of the action of chlorine ions concentrated in the moisture contained in the iron oxide films deposited in low parts of the tube bundle, directly at the tube plate. Blowing through did not ensure complete removal of the film, and in some cases the construction features of the steam generator made removal of the film practically impossible. Replacement of type 18/8 stainless steel by other construction material, e.g., Inconel, did not give good results. To ensure reliable operation of vertical steam generators in domestic practice, the generators are designed without a low tube plate (a variant diagram of the vertical steam generator of such construction for the water-cooled, water-moderated reactor 1000 is presented). When low tube plates are used the film deposition is intolerable. For organization of a non-film regime a complex treatment of the feed water is used, in which the amount of complexion is calculated from the stoichmetric ratios with the composition of the feed water. It is noted that, if 100% condensate purification is used with complexon processing of the feed water to the generator, we can calculate the surface of the steam-generator heater without considering the outer placement on the tubes. In this the cost of the steam generator and all the nuclear power plants with WWER type reactors is decreased even with installation of a 100% condensate purification. It is concluded that only simultaneous solution of construction and water-regime problems will ensure relaible operation of

  12. LHD type proton-boron reactor and the control of its peripheral potential structure

    Energy Technology Data Exchange (ETDEWEB)

    Matsumoto, Yutaka; Nagaura, Tatsuhiko; Itoh, Yasuyoshi; Oikawa, Shun-ichi [Graduate School of Engineering, Hokkaido Univ., Sapporo, Hokkaido (Japan); Watanabe, Tsuguhiro [National Inst. for Fusion Science, Toki, Gifu (Japan)

    2001-04-01

    An advanced Large Helical Device (LHD) type proton-boron reactor, in which the minority protons are heated by ICRF, is proposed. The ratio of the fusion power to the RF input power is evaluated. Numerical computation of particle orbits shows that the ICRF of LHD can accelerate protons in the p{sup -11} B fusion relevant energy. Numerical results also show that the LHD magnetic configuration can confine the high energy {sup 4}He well. An active peripheral potential control method and an active {sup 4}He ash exhaust scheme are discussed. (author)

  13. Experience feedback examination in PWR type reactors operating for the 1997-1999 period

    International Nuclear Information System (INIS)

    2004-01-01

    The present report is relative to the examination that the permanent group has made on the experience feedback in operation for PWR type reactors for the period 1997-1999 that was on eleven themes chosen by the Nuclear Safety and Radiation Protection Authority. It used analysis reports made by I.R.S.N. in support of four meetings of the permanent group devoted to this examination from April 2001 to June 2002. The different themes were operating uncertainties, machining to vibrations, analysis of incidents and gaseous releases, circuits, human factors, behaviour of electric batteries, risk of cold source loss. (N.C.)

  14. Data list of nuclear power plants of pressurized-water reactor type in Japan

    International Nuclear Information System (INIS)

    Izumi, Fumio; Harayama, Yasuo

    1981-08-01

    This report has collected and compiled the data concerning performances, equipments and installations for nuclear power plants of the pressurized-water reactor type in Japan. The data used in the report are based on informations that were collected before December in 1980. The report is edited by modifing changes of the data appeared after publication of 1979 edition (JAERI-M 8947), and extending the data-package to cover new plants proposed thereafter. All data have been processed and tabulated with a computer program FREP, which has been developed as an exclusive use of data processing. (author)

  15. Influence of reactor design on the establishment of natural circulation in pool-type LMFBR

    International Nuclear Information System (INIS)

    Durham, M.E.

    1976-01-01

    The general principles involved in establishing natural circulation in a pool-type liquid metal cooled fast breeder reactor following loss of a.c. supplies are elucidated and the effects of design features by use of the computer code MELANI are quantified. It is shown that natural circulation can provide a feasible means of emergency core cooling in addition to that provided by pony motors. The choice of primary pump rundown time has a significant effect in controlling peak core outlet temperatures in the hypothetical case of natural circulation alone being the core heat removal process. (author)

  16. The criticality problem in reflected slab type reactor in the two-group transport theory

    International Nuclear Information System (INIS)

    Garcia, R.D.M.

    1978-01-01

    The criticality problem in reflected slab type reactor is solved for the first time in the two group neutron transport theory, by singular eingenfunctions expansion, the singular integrals obtained through continuity conditions of angular distributions at the interface are regularized by a recently proposed method. The result is a coupled system of regular integral equations for the expansion coefficients, this system is solved by an ordinary interactive method. Numerical results that can be utilized as a comparative standard for aproximation methods, are presented [pt

  17. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-07-01

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

  19. INFLUENCIA DE TALLERES DE INTELIGENCIA EMOCIONAL EN EL DESARROLLO SOCIOEMOCIONAL DEL NIÑO DE 4 AÑOS DEL AULA LOS GENIECITOS DE LA INSTITUCIÓN EDUCATIVA N° 44 “SAN ANTONIO DE PUTINA”. PUNO, 2013

    OpenAIRE

    MASIAS SERRANO, KATHYE YOLANDA

    2015-01-01

    INTELIGENCIA EMOCIONAL FUNCIONAMIENTO DE LAS EMOCIONES COMPETENCIA HABILIDADES PROPIAS DE LA INTELIGENCIA EMOCIONAL CARACTERÍSTICAS DE LAS CAPACIDADES DE LA INTELIGENCIA EMOCIONAL IMPORTANCIA DE LA INTELIGENCIA EMOCIONAL ¿QUÉ PODEMOS HACER PARA DESARROLLAR LA INTELIGENCIA EMOCIONAL? CONCIENCIA EMOCIONAL ¿CÓMO DESARROLLAR LA INTELIGENCIA EMOCIONAL EN LA EDUCACIÓN INFANTIL? LA INTELIGENCIA EMOCIONAL EN EL CONTEXTO FAMILIAR CARACTERÍSTICAS DE LA PERSONA EMOCIONALMENTE INTELIGENTE AUTOCONCEPTO VA...

  20. Evaluación de un programa de inteligencia emocional dirigido a alumnos de 5 años

    OpenAIRE

    Granero, Fátima

    2012-01-01

    En este trabajo se evalúa la eficacia de un programa de Inteligencia Emocional (“Mejoramos la convivencia usando la Inteligencia Emocional") dirigido a niños de 5 años. Para ello se han medido los niveles de Inteligencia Emocional, Intrapersonal e Interpersonal pasando los cuestionarios de Inteligencias Múltiples de Howard Gardner a una muestra de alumnos, 15 forman el grupo control y 15 el grupo experimental. Los resultados han revelado que existen diferencias marginalmente signi...

  1. A novel reactor type for autothermal reforming of diesel fuel and kerosene

    International Nuclear Information System (INIS)

    Pasel, Joachim; Samsun, Remzi Can; Tschauder, Andreas; Peters, Ralf; Stolten, Detlef

    2015-01-01

    Highlights: • Development and experimental evaluation of Juelich’s novel ATR reactor type. • Constructive integration of steam generation chamber and nozzle for water injection. • Internal steam generator modified to reduce pressure drop to approx. a thirtieth. • Novel concept for ATR heat management proven to be suitable for fuel cell systems. • Reaction conditions during shut-down and start-up optimized to reduce byproducts. - Abstract: This paper describes the development and experimental evaluation of Juelich’s novel reactor type ATR AH2 for autothermal reforming of diesel fuel and kerosene. ATR AH2 overcomes the disadvantages of Juelich’s former reactor generations from the perspective of the fuel cell system by constructively integrating an additional pressure swirl nozzle for the injection of cold water and a steam generation chamber. As a consequence, ATR AH2 eliminates the need for external process configurations for steam supply. Additionally, the internal steam generator has been modified by increasing its cross-sectional area and by decreasing its length. This measure reduces the pressure drop of the steam generator from approx. 500 mbar to roughly a thirtieth. The experimental evaluation of ATR AH2 at steady state revealed that the novel concept for heat management applied in ATR AH2 is suitable for fuel cell systems at any reformer load point between 20% and 120% when the mass fractions of cold water to the newly integrated nozzle are set to values between 40% and 50%. The experimental evaluation of ATR AH2 during start-up and shut-down showed that slight modifications of the reaction conditions during these transient phases greatly reduced the concentrations of ethene, ethane, propene and benzene in the reformate. From the fuel cell system perspective, these improvements provide a very beneficial contribution to longer stabilities for the catalysts and adsorption materials

  2. [Continuous dry fermentation of pig manure using up plug-flow type anaerobic reactor].

    Science.gov (United States)

    Chen, Chuang; Deng, Liang-Wei; Xin, Xin; Zheng, Dan; Liu, Yi; Kong, Chui-Xue

    2012-03-01

    To solve the problems of ammonia inhibition and discharging difficulty in continuous dry fermentation of pig manure, under the experimental conditions of temperature of (25 +/- 2) degrees C and organic loading rate (TS) of 4.44 g x (L x d) (-1), a lab-scale up plug-flow type anaerobic reactor (UPAR) was setup to investigate biogas production, ammonia inhibition, effluent liquidity, and the feasibility of continuous dry fermentation of pig manure using up plug-flow type anaerobic reactor. The experiment was operated for 160 days using the pig manure with four different TS mass fractions (20%, 25%, 30%, 35%) as feeding. Results showed that the feeding TS mass fraction exerted a significant influence on the dry fermentation of pig manure; the stable volumetric biogas production rates of four different feeding TS mass fractions were 2.40, 1.73, 0.89, and 0.62 L x (L x d)(-1), respectively; the biogas producing efficiencies of the reactors with feeding TS mass fractions of 20%, 25% and 30% were obviously superior to that with feeding TS of 35%. With feeding TS mass fraction increased from 20% to 35%, obvious inhibition to biogas producing occurred when concentration of ammonia nitrogen reached more than 2 300 mg x L(-1). When the feeding TS mass fraction was 35%, the concentration of ammonia nitrogen could accumulate to 3 800 mg x L(-1) but biogas production rate decreased 74.1% of that with feeding TS of 20%. Additionally, while the feeding TS mass fraction was 35%, the effluent TS mass fraction achieved 17.1%, and the velocity of effluent was less than 0.002 m x s(-1) the effluent of UPAR could not be smoothly discharged.

  3. Reactor core T-H characteristics determination in case of parallel operation of different fuel assembly types

    International Nuclear Information System (INIS)

    Hermansky, J.; Petenyi, V.; Zavodsky, M.

    2009-01-01

    The WWER-440 nuclear fuel vendor permanently improve the assortment of produced nuclear fuel assemblies for achieving better fuel cycle economy and reactor operation safety. Therefore it is necessary to have the skilled methodology and computing code for analyzing factors which affecting the accuracy of flow redistributed determination through reactor on flows through separate parts of reactor core in case of parallel operation different assembly types. Whereas the geometric parameters of new manufactured assemblies were changed recently, the calculated flows through the fuel parts of different type of assemblies are depended also on their real position in reactor core. Therefore the computing code CORFLO was developed in VUJE Trnava for carrying out stationary analyses of T-H characteristics of reactor core within 60 deg symmetry. The CORFLO code deals the area of the active core which consists of 312 fuel assemblies and 37 control assemblies. Regarding the rotational 60 deg symmetry of reactor core only 1/6 of reactor core with 59 fuel assemblies is calculated. Computing code is verified and validated at this time. Paper presents the short description of computing code CORFLO with some calculated results. (Authors)

  4. Reactor core T-H characteristics determination in case of parallel operation of different fuel assembly types

    International Nuclear Information System (INIS)

    Hermansky, J.; Petenyi, V.; Zavodsky, M.

    2009-01-01

    The VVER-440 nuclear fuel vendor permanently improve the assortment of produced nuclear fuel assemblies for achieving better fuel cycle economy and reactor operation safety. Therefore it is necessary to have the skilled methodology and computing code for analyzing factors which affecting the accuracy of flow redistributed determination through reactor on flows through separate parts of reactor core in case of parallel operation different assembly types. Whereas the geometric parameters of new manufactured assemblies were changed recently, the calculated flows through the fuel parts of different type of assemblies are depended also on their real position in reactor core. Therefore the computing code CORFLO was developed in VUJE Trnava for carrying out stationary analyses of T-H characteristics of reactor core within 60 0 symmetry. The CORFLO code deals the area of the active core which consists of 312 fuel assemblies and 37 control assemblies. Regarding the rotational 60 0 symmetry of reactor core only 1/6 of reactor core with 59 fuel assemblies is calculated. Computing code is verified and validated at this time. Paper presents the short description of computing code CORFLO with some calculated results. (authors)

  5. Feasibility analysis of the Primary Loop of Pool-Type Natural Circulating Nuclear Reactor Dedicated to Seawater Desalination

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woonho; Jeong, Yong Hoon [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    In this study, the feasibility of natural circulation was evaluated for the reference plant AHR400 (Advanced Heating Reactor 400MWth). AHR400 is a pool-type desalination-dedicated nuclear reactor. As a consequence, AHR400 has low operating pressure and temperature which provides large safety margin. Removal of the reactor coolant pump from the AHR400 will enforce integrity of the reactor vessel and passive safety feature. Therefore, the study also tried to find out optimized primary loop design to achieve total natural circulation of the coolant. Natural circulation capacity of the primary loop of the desalination dedicated nuclear reactor AHR400 was evaluated. It was concluded that to remove RCP from the AHR400 and operates the reactor only by natural circulation of the coolant is impossible. Decreased core power as half make removal of RCP possible with 15m central height difference between the core and IHXs. Furthermore, validation and modification of pressure loss coefficients by small-scaled natural circulation experiment at a pool-type reactor would provide more accurate results.

  6. Parameter definition for reactor physics calculation of Obrigheim KWO PWR type reactor using the Gels and Erebus codes

    International Nuclear Information System (INIS)

    Faya, A.G.; Nakata, H.; Rodrigues, V.G.; Oosterkamp, W.J.

    1974-01-01

    The main variables for Obrigheim Reactor - KWO diffusion theory calculations, using the EREBUS code were defined. The variables under consideration were: mesh spacing for reactor description, time-step in burn-up calculation, and the temperature in both the moderator and the fuel. The best mesh spacing and time-step were defined considering the relative deviations and the computer time expended in each case. It has been verified that the error involved in the mean fuel temperature calculation (1317 0 K as given by SIEMENS and 1028 0 K as calculated by Dr. Penndorf) does not change substancially the calculation results

  7. Transient analysis of a typical MTR fuel type research reactor by RELAP5/MOD 3.3

    International Nuclear Information System (INIS)

    Montazeri, A.; Bousbia Salah, A.; D'Auria, F.

    2004-01-01

    In this work the Transient Analysis for two different scenarios in a typical research reactor are considered. The first case is T he Spurious opening of the safety flapper valve, following reactor trip . The second case is the same as the first one, but the corresponding trip signal is not initiated, i.e. an anticipated transient without scram. The safety flapper valve is employed for natural convection in a typical swimming pool type research reactor. In both cases it is considered that the core is in steady state operation at full power. The reactor under consideration is a pool-type MTR core with maximum thermal capacity of 1 MW. Light water moderates the neutrons and a downward forced circulation of light water cools off the core as well. The analysis is performed using advanced computational tools, i.e. RELAP5/MOD 3.3

  8. Using the CompGen code for developing new MMS modules specific to CANDU type reactors

    International Nuclear Information System (INIS)

    Bigu, Melania; Nita, Iulian Pavel; Prisecaru, Ilie; Dupleac, Daniel; Constantinescu, Adrian; Budu, Andrei; Dumitriu, Monica

    2004-01-01

    The Modular Modeling System, MMS, is an advanced tool for thermal hydraulic analyses. The MMS code is built upon a modular philosophy allowing users to construct their own schemes from the existing MMS modules. Also, it is possible to develop new MMS modules by using the CompGen sub-code. Developing new modules in the frame of MMS program was necessary because the standard modules of the program libraries are customized to the American reactors, particularly to PWR type reactors. As known the Cernavoda NPP is of PHWR type having equipment and components different from the structure point of view, hence differ from the point of view of the equation describing the transient process. An example is the module of low pressure part of the turbine in the secondary circuit of the plant, where the moisture extraction coefficients measured from equipment operation are different from the coefficient introduced in the module of the MMS library. The new modules developed in this work were compared with data from the thermal balance supplied by General Electric, with functional data from operation, and with the data from the Commissioning Report of the Cernavoda NPP Unit 1 commissioning. In this work new modules which or developed are presented as well as two examples of using the steam generator modules, high pressure turbine, low pressure turbine, and superheater separator

  9. Design of proportional-integral-derivative type optimal controller for a nuclear reactor

    International Nuclear Information System (INIS)

    Pal, Jayanta

    1976-01-01

    A theoretic approach to the design of a proportional integral derivative (PID) type optimal controller for a nuclear reactor is considered. A linearized version of the state-space model of a nuclear-reactor-plant is investigated which shows very 'sluggish' response (settling time of the order of 600 seconds) to changes in the power demand and frequency. It is shown that with a judicious choice of state variables a PID type optimal controller realisation is possible. A controller is designed to minimise the effects of (a) a sudden increase or decrease in the electrical power demand (b) change in frequency at grid. The above controller, designed for a tracking problem, reduces the steady-state error (in response to a step input) to zero and the dynamics of the system become 'faster' (setting time of the order of 100 seconds). The controller is also insensitive to changes in system parameters. The superiority in the performance of the system with the optimal PID controller as compared with that of the conventional regulator is conclusively established. (author)

  10. Optimizing the Design of Small Fast Spectrum Battery-Type Nuclear Reactors

    Directory of Open Access Journals (Sweden)

    Staffan Qvist

    2014-07-01

    Full Text Available This study is focused on defining and optimizing the design parameters of inherently safe “battery” type sodium-cooled metallic-fueled nuclear reactor cores that operate on a single stationary fuel loading at full power for 30 years. A total of 29 core designs were developed with varying power and flow conditions, including detailed thermal-hydraulic, structural-mechanical and neutronic analysis. Given set constraints for irradiation damage, primary cycle pressure drop and inherent safety considerations, the attainable power range and performance characteristics of the systems are defined. The optimum power level for a core with a coolant pressure drop limit of 100 kPa and an irradiation damage limit of 200 DPA (displacements per atom is found to be 100 MWt/40 MWe. Raising the power level of an optimized core gives significantly higher attainable power densities and burnup, but severely decreases safety margins and increases the irradiation damage. A fully optimized inherently safe battery-type fast reactor core with an active height and diameter of 150 cm (2.6 m3, a pressure drop limit of 100 kPa and an irradiation damage limit of 300 DPA can be designed to operate at 150 MWt/60 MWe for 30 years, reaching an average discharge burnup of 100 MWd/kg-actinide.

  11. Perspectives for practical application of the combined fuel kernels in VVER-type reactors

    International Nuclear Information System (INIS)

    Baranov, V.; Ternovykh, M.; Tikhomirov, G.; Khlunov, A.; Tenishev, A.; Kurina, I.

    2011-01-01

    The paper considers the main physical processes that take place in fuel kernels under real operation conditions of VVER-type reactors. Main attention is given to the effects induced by combinations of layers with different physical properties inside of fuel kernels on these physical processes. Basic neutron-physical characteristics were calculated for some combined fuel kernels in fuel rods of VVER-type reactors. There are many goals in development of the combined fuel kernels, and these goals define selecting the combinations and compositions of radial layers inside of the kernels. For example, the slower formation of the rim-layer on outer surface of the kernels made of enriched uranium dioxide can be achieved by introduction of inner layer made of natural or depleted uranium dioxide. Other potential goals (lower temperature in the kernel center, better conditions for burn-up of neutron poisons, better retention of toxic materials) could be reached by other combinations of fuel compositions in central and peripheral zones of the fuel kernels. Also, the paper presents the results obtained in experimental manufacturing of the combined fuel pellets. (authors)

  12. The design and installation of a core discharge monitor for CANDU-type reactors

    International Nuclear Information System (INIS)

    Halbig, J.K.; Monticone, A.C.; Ksiezak, L.; Smiltnieks, V.

    1990-01-01

    A new type of surveillance systems that monitors neutron and gamma radiation in a reactor containment is being installed at the Ontario Hydro Darlington Nuclear Generating Station A, Unit 2. Unlike video or film surveillance that monitors mechanical motion, this system measures fuel-specific radiation emanating from irradiated fuel as it is pushed from the core of CANDU-type reactors. Proof-of-principle measurements have been carried out at Bruce Nuclear Generating Station A, Unit 3. The system uses (γ,n) threshold detectors and ionization detectors. A microprocessor-based electronics package, GRAND-II (Gamma Ray and Neutron Detector electronics package), provides detector bias, preamplifier power, and signal processing. Firmware in the GRAND-2 controls the surveillance activities, including data acquisition and a level of detector authentication, and it handles authenticated communication with a central data logging computer. Data from the GRAND-II are transferred to an MS-DOS-compatible computer and stored. These data are collected and reviewed for fuel-specific radiation signatures from the primary detector and proper ratios of signals from secondary detectors. 5 figs

  13. LA INTELIGENCIA COMO CAMPO DE ACCION DE LA PEDAGOGIA

    Directory of Open Access Journals (Sweden)

    Servio Tulio Salazar Valencia

    2000-05-01

    Full Text Available Si la inteligencia se concibe como un conjunto de habilidades de pensamiento y de aprendizaje, utilizados para solucionar problemas tanto académicos como de la cotidianidad, constituye ésta un centro de especial interés para quienes hemos asumido la delicada tarea de intentar formar, y si es posible, transformar las conductas de las juventudes estudiosas de nuestro país. En el presente ensayo se critican algunos comportamientos de los docentes que, esconociendo que la inteligencia "es una extensión de algunas características biológicas fundamentales del ser" (Piaget, pretenden poseer una metodología única e irrefutable en su labor pedagógica.

  14. Inteligencia artificial, emoción y neurociencia

    Directory of Open Access Journals (Sweden)

    Mira, J.

    1999-05-01

    Full Text Available Not available.Presentamos en este trabajo un conjunto de interrelaciones entre Neurociencia y Computación desde una perspectiva metodológica común, basada en la distinción de tres niveles (fisiológico, de los símbolos y de conocimiento y dos dominios de descripción (el propio de cada nivel y el del observador externo. Se explora la potencial validez del paradigma computacional para ayudar a la explicación del funcionamiento del sistema nervioso. De forma complementaria, se razona también sobre la validez de la Neurociencia como fuente de inspiración en el campo de la Inteligencia Artificial. Finalmente, se analizan algunos de los términos básicos que, procedentes de la esfera semántica de lo emocional, han invadido recientemente el campo de la robótica y la Inteligencia Artificial.

  15. Treatment of sodium spills and leakage detection at loop-type fast reactors

    International Nuclear Information System (INIS)

    Foerster, K.; Fortmann, M.; Lang, H.; Moellerfeld, H.

    1979-01-01

    Sodium spills are of great importance in the safety analysis for sodium cooled nuclear plants. Large leakages can lead to a depletion of the heat transfer system and cause the loss of cooling of the reactor. Further the hot sodium may attack structural materials. In areas with air atmosphere large amounts of sodium can burn and cause great damages. Therefore the control of large leakages is an indispensable task in design and construction of sodium cooled reactor systems. Because of the typical arrangement of widespread long pipe systems loop type plants are subject to a gradually greater risk of damage than pool type plants. The sodium catching devices of the SNR-300 are described and their function is illustrated as an example for the treatment of large spills. Since the equipment for the control of large amounts of leaking sodium is very expensive, great efforts are made in order to save costs and to decrease safety problems. It is aimed to minimize the probability of such events to a degree that they no longer are to be considered realistic. The advantageous operating conditions and the favourable material properties support this aim. Under the well known keyword 'leak-before-rupture' criterion this task is pursued. Crack growth measurements are made at structural materials under LMFBR conditions, and leakage detecting systems are being developed. Some test results concerning this task are described. Despite the fact that there are good chances to verify the leak-before-rupture criterion it is assumed that certain hypothetical accidents occur, which are to be considered in the design of the reactor plant. The extremely improbable Bethe-Tait-accident (HCDA) is such an event. It would lead to a super spill, that means to the complete depletion of the reactor tank. For the SNR-300 plant a system is provided that is able to catch this super spill and the core melt. This core catcher must withstand the high temperatures and remove the decay heat. The purpose of this

  16. Personalidad eficaz e inteligencia emocional en contextos universitarios chilenos

    OpenAIRE

    Tapia Allende, Roxana

    2017-01-01

    La investigación da cuenta sobre la relación empírica que existe entre los constructos de Personalidad Eficaz e Inteligencia / Competencia Emocional Intrapersonal e Interpersonal en contextos universitarios chilenos. Para ello, los objetivos propuestos son: establecer la relación empírica existente entre los constructos de Personalidad Eficaz y las Competencias Emocionales Intrapersonales e Interpersonales en contextos universitarios chilenos; establecer los tipos de personalidad eficaz y l...

  17. Plan de marketing para la herramienta de inteligencia artificial Parlakuy

    OpenAIRE

    Farro Flores, César Augusto; Gonzales Gaspar, Juan Francisco

    2017-01-01

    Parlakuy es una empresa tecnológica en formación dedicada a utilizar herramientas de inteligencia artificial, específicamente machine learning, en las redes sociales. Tiene por objetivo ayudar a resolver las necesidades de las empresas y personas para que puedan entender a sus clientes en redes sociales, identificar temas importantes para su estudio y tomar acciones preventivas ante un suceso o acontecimiento en tiempo real. Para esto crea la herramienta Parlakuy, que tiene el mismo nombre...

  18. Conducta agresiva e inteligencia emocional en la adolescencia

    Directory of Open Access Journals (Sweden)

    Cándido J. Inglés

    2014-06-01

    Full Text Available Son escasos los estudios que analizan la relación entre conducta agresiva e inteligencia emocional. Este estudio examina la relación entre inteligencia emocional rasgo y los componentes motor (agresividad física y agresividad verbal, cognitivo (hostilidad y afectivo/emocional (ira de la conducta agresiva. El Trait Emotional Intelligence Questionnaire-Adolescents Short Form (TEIQue-ASF y el Aggression Questionnaire Short version (AQ-S fueron administrados a una muestra de 314 adolescentes (52.5% chicos de 12 a 17 años. Los resultados indicaron que los adolescentes con altas puntuaciones en conducta agresiva física, verbal, hostilidad e ira presentaron puntuaciones significativamente más bajas en inteligencia emocional rasgo que sus iguales con puntuaciones bajas en conducta agresiva física, verbal, hostilidad e ira. Este patrón de resultados fue el mismo tanto para la muestra total como para chicos, chicas y los grupos de edad de 12-14 años y 15-17 años. Además, en la mayoría de los casos se hallaron tamaños del efecto grandes apoyando la relevancia empírica de estas diferencias

  19. Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods

    International Nuclear Information System (INIS)

    Liu, Shichang; Wang, Guanbo; Liang, Jingang; Wu, Gaochen; Wang, Kan

    2015-01-01

    Highlights: • DRAGON & DONJON were applied in burnup calculations of plate-type research reactors. • Continuous-energy Monte Carlo burnup calculations by RMC were chosen as references. • Comparisons of keff, isotopic densities and power distribution were performed. • Reasons leading to discrepancies between two different approaches were analyzed. • DRAGON & DONJON is capable of burnup calculations with appropriate treatments. - Abstract: The burnup-dependent core neutronics analysis of the plate-type research reactors such as JRR-3M poses a challenge for traditional neutronics calculational tools and schemes for power reactors, due to the characteristics of complex geometry, highly heterogeneity, large leakage and the particular neutron spectrum of the research reactors. Two different theoretical approaches, the deterministic and the stochastic methods, are used for the burnup-dependent core neutronics analysis of the JRR-3M plate-type research reactor in this paper. For the deterministic method the neutronics codes DRAGON & DONJON are used, while the continuous-energy Monte Carlo code RMC (Reactor Monte Carlo code) is employed for the stochastic one. In the first stage, the homogenizations of few-group cross sections by DRAGON and the full core diffusion calculations by DONJON have been verified by comparing with the detailed Monte Carlo simulations. In the second stage, the burnup-dependent calculations of both assembly level and the full core level were carried out, to examine the capability of the deterministic code system DRAGON & DONJON to reliably simulate the burnup-dependent behavior of research reactors. The results indicate that both RMC and DRAGON & DONJON code system are capable of burnup-dependent neutronics analysis of research reactors, provided that appropriate treatments are applied in both assembly and core levels for the deterministic codes

  20. Development of in-vessel type control rod drive mechanism for a innovative small reactor (Contract research)

    Energy Technology Data Exchange (ETDEWEB)

    Yoritsune, Tsutomu; Ishida, Toshihisa [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    Although the control rod drive mechanism of an existing large scale light water reactor is generally installed outside the reactor vessel, an in-vessel type control rod drive mechanism (INV-CRDM) is installed inside the reactor vessel. The INV-CRDM contributes to compactness and simplicity of the reactor system, and it can eliminate the possibility of a rod ejection accident. Therefore, INV-CRDM is an important technology adopted in an innovative small reactor. Japan Atomic Energy Research Institute (JAERI) has developed this type of CRDM driven by an electric motor, which can work under high temperature and high pressure water for the advanced marine reactor. On the basis of this research result, a driving motor coil and a bearing were developed to be used under the high temperature steam, severe condition for an innovative small reactor. About the driving motor, we manufactured the driving motor available for high temperature steam and carried out performance test under room temperature atmosphere to confirm the electric characteristic and coolability of the driving coil. With these test results and the past test results under high temperature water, we analyzed and evaluated the electric performance and coolability of the driving coil under high temperature steam. Concerning bearing, we manufactured the test pieces using some candidate material for material characteristic test and carried out the rolling wear test under high temperature steam to select the material. Consequently, we confirmed that performance of the driving coil for the advanced type driving motor, is enough to be used under high temperature steam. And, we evaluated the performance of the bearing and selected the material of the bearing, which can be used under high temperature steam. From these results, we have obtained the prospect that the INV-CRDM can be used for an innovative small reactor under steam atmosphere could be developed. (author)

  1. Estimulación de la Inteligencia Emocional en mayores: El programa PECI-PM

    Directory of Open Access Journals (Sweden)

    Mª del Carmen Pérez-Fuentes

    2014-12-01

    Full Text Available El programa de Estimulación Cognitiva e Inteligencia Emocional para personas mayores (PECI-PM, combina técnicas de estimulación cognitiva con la intervención y estimulación sobre aspectos relacionados con la inteligencia emocional. El objetivo del presente trabajo es analizar los resultados obtenidos en inteligencia emocional, tras la primera fase de implementación del PECI-PM. Para ello, se contó con una muestra de 28 usuarios del programa, que habían completado 20 sesiones y participado en las dos evaluaciones (pre-post. La Inteligencia Emocional se evaluó, antes y después de la intervención, mediante el Inventario Breve de Inteligencia Emocional para Mayores (EQ-i-M20. Tras la intervención con el PECI-PM, se observa una mejora, en la mayoría de las dimensiones de inteligencia emocional (Intrapersonal, Interpersonal, Adaptabilidad y Estado de Ánimo. En la dimensión Manejo del Estrés, no se observa un cambio en las puntuaciones obtenidas tras la intervención, lo que lleva a replantear el peso de esta dimensión en la inteligencia emocional de la población mayor. Por otro lado, destaca el papel de la dimensión Interpersonal, que correlaciona significativamente con otros factores de la inteligencia emocional (Intrapersonal y Adaptabilidad, en mayores.

  2. Forced vibration test of BWR type nuclear reactor buildings considering through-soil coupling between adjacent buildings

    International Nuclear Information System (INIS)

    Mizuno, Norihiro; Moribe, Isamu; Sugiyama, Nobuo; Tsushima, Yoshiyuki; Kushida, Hiroshi

    1980-01-01

    The forced vibration test on two adjacent BWR type reactor buildings in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was carried out in 1977. The experiment on No. 1 reactor building had been made in 1973 and 1974 to evaluate the dissipation of vibrational energy to the earth. In 1977, No. 2 reactor building was under construction and nearly completed adjacently to the No. 1 reactor building, in which the reactor has been in operation since 1975. Three large vibration exciters with maximum exciting force of 150 tons each were installed on the 5th floor of the No. 2 reactor building, and the vibration ranging from 1 to 20 Hz was applied to the building in north-south, east-west and vertical directions. For obtaining the responses of the buildings, 24 and 33 pickups were placed on the floors of No. 1 and No. 2 buildings, respectively, and 17 dynamic earth pressure cells buried under the foundation of the No. 2 building were also employed. The natural frequency, viscous damping ratio and natural mode were analyzed by the regression analysis of many degrees of freedom, using the resonance curves with complex forms and many peaks. The vibrational behaviors of two adjacent reactor buildings coupled through the earth were given as the result of experiment. (J.P.N.)

  3. Qualitative and quantitative characteristics of fission products in spent nuclear fuel from RBMK-type reactor

    International Nuclear Information System (INIS)

    Adlys, G.; Adliene, D.

    2002-01-01

    Well-known empirical models or experimental instruments and methods for the estimation of fission product yields do not allow prediction of the behavior and evaluation of the time-dependent qualitative and quantitative characteristics of all fission products in spent nuclear fuel during long-term storage. Several computer codes were developed in different countries to solve this problem. French codes APOLLO1 and PEPIN were used in this work for modeling the characteristics of spent nuclear fuel in the RBMK reactor. The modeling results of qualitative and quantitative characteristics of long-lived fission products for different cooling periods of spent nuclear fuel, including 50-year cooling period, are presented in this paper. The 50-year cooling period conforms to the foreseen time of storage of spent nuclear fuel in CONSTOR and CASTOR casks at the Ignalina NPP. These results correlate well with evaluated quantities for the well-known yields of the nuclides and could be used for the compilation of the database for long-lived fission products in spent nuclear fuel from the RBMK-type reactor. They allow one to predict and to solve effectively safety problems concerning with long-term spent nuclear fuel storage in casks. (author)

  4. Conceptual design activities and key issues on LHD-type reactor FFHR

    International Nuclear Information System (INIS)

    Sagara, A.; Mitarai, O.; Imagawa, S.; Morisaki, T.; Tanaka, T.; Mizuguchi, N.; Dolan, T.; Miyazawa, J.; Takahata, K.; Chikaraishi, H.; Yamada, S.; Seo, K.; Sakamoto, R.; Masuzaki, S.; Muroga, T.; Yamada, H.; Fukada, S.; Hashizume, H.; Yamazaki, K.; Mito, T.; Kaneko, O.; Mutoh, T.; Ohyabu, N.; Noda, N.; Komori, A.; Sudo, S.; Motojima, O.

    2006-01-01

    An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and the proposal of a long-life blanket. A major radius of around 15 m is the present candidate under the constraints of the energy confinement achieved in LHD, a maximum magnetic field around 13 T with a current density around 30 A/mm 2 and a neutron wall loading around 1.5 MW/m 2 . R and D on super-conducting magnet systems of large scale, high field and high current-density are new challenging targets based on the LHD. The development of new design tools has been started aiming at establishing a virtual power plant (VPP) and a virtual reality system for 3D design assisting. Next design issues are mainly on engineering optimization of the first wall thickness, the detailed 3D blanket system, and unscheduled replacements of breeder blankets

  5. A Stochastic Proof of the Resonant Scattering Kernel and its Applications for Gen IV Reactors Type

    International Nuclear Information System (INIS)

    Becker, B.; Dagan, R.; Broeders, C.H.M.; Lohnert, G.

    2008-01-01

    Monte Carlo codes such as MCNP are widely accepted as almost-reference for reactor analysis. The Monte Carlo Code should therefore use as few as possible approximations in order to produce 'experimental-level' calculations. In this study we deal with one of the most problematic approximations done in MCNP in which the resonances are ignored for the secondary neutron energy distribution, namely the change of the energy and angular direction of the neutron after interaction with a heavy isotope with pronounced resonances. The endeavour of exploiting the influence of the resonances on the scattering kernel goes back to 1944 where E. Wigner and J. Wilkins developed the first temperature dependent scattering kernel. However only in 1998, the full analytical solution for the double differential resonant dependent scattering kernel was suggested by W. Rothenstein and R. Dagan. An independent stochastic approach is presented for the first time to confirm the above analytical kernel with a complete different methodology. Moreover, by manipulating in a subtle manner the scattering subroutine COLIDN of MCNP, it is proven that this very subroutine is, to some extent, inappropriate as well as the relevant explanation in the MCNP manual. The impact of this improved resonance dependent scattering kernel on diverse types of reactors, in particular for the Generation IV innovative core design HTR, is shown to be significant. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  7. Inteligencia Contextual Percibida en el Deporte. Desarrollo y Validación de un Cuestionario

    Directory of Open Access Journals (Sweden)

    Luis Miguel Ruiz Pérez

    2014-01-01

    Full Text Available El propósito de este estudio ha sido el desarrollo y validación de un Cuestionario de Inteligencia Contextual Percibida en el Deporte en una muestra de deportistas españoles de diferente nivel de pericia. Participaron 2091 deportistas (1519 hombres y 572 mujeres de edades comprendidas entre los 11 y los 59 años (M = 20,8; DT = 6,14. Los análisis factoriales exploratorio y confirmatorio mostraron que el cuestionario presentaba una estructura de tres dimensiones (inteligencia anticipatoria, inteligencia táctica e inteligencia competitiva, además de permitir obtener la obtención de un valor de la escala general denominado Inteligencia Contextual en el Deporte. Las propiedades psicométricas de validez y la fiabilidad del instrumento fueron excelentes para poder ser empleado en estudios en los que esta dimensión sea de interés.

  8. Study on the seismic response of reactor vessel of pool type LMFBR including fluid-structure interaction

    International Nuclear Information System (INIS)

    Tanimoto, K.; Ito, T.; Fujita, K.; Kurihara, C.; Sawada, Y.; Sakurai, A.

    1988-01-01

    The paper presents the seismic response of reactor vessel of pool type LMFBR with fluid-structure interaction. The reactor vessel has bottom support arrangement, the same core support system as Super-Phenix in France. Due to the bottom support arrangement, the level of core support is lower than that of the side support arrangement. So, in this reactor vessel, the displacement of the core top tends to increase because of the core's rocking. In this study, we investigated the vibration and seismic response characteristics of the reactor vessel. Therefore, the seismic experiments were carried out using one-eighth scale model and the seismic response including FSI and sloshing were investigated. From this study, the effect of liquid on the vibration characteristics and the seismic response characteristics of reactor vessel were clarified and sloshing characteristics were also clarified. It was confirmed that FEM analysis with FSI can reproduce the seismic behavior of the reactor vessel and is applicable to seismic design of the pool type LMFBR with bottom support arrangement. (author). 5 refs, 14 figs, 2 tabs

  9. Introducing a new type of fuel in EDF reactors: Main issues. Introducing a New Fuel in EDF Reactors: Main Issues

    International Nuclear Information System (INIS)

    Wong, Hing-Ip; Moatti, Marie

    2013-01-01

    The main issues associated with the introduction of a new fuel design at an industrial level in EDF reactors are the following: in-core operational feedback, coherence of the nuclear fuel cycle and mixed cores. In-core operational feedback Once all possible experimental results have been obtained for a new fuel design, in-core qualification is necessary to assess its robustness and reliability prior to an industrial use. That qualification involves several steps to gather the relevant operational feedback at minimum risk: - irradiation of a few LTA's during a number of operating cycles greater than what would be needed on an industrial scale, with specific exams and rod extractions at the end of each fuel cycle: that first step is 5 to 6 years long; - loading whole reloads with the new fuel design in a dedicated reactor is then requested if the new fuel design is associated with a new structure design; in that case, only a full core with the new design will enable checking the behaviour of that fuel with respect to GTRF and assembly bow: that second step may take another 5 to 6 years. Altogether, the whole in-core qualification process might need more than 10 years. Considering that 10 other years could be necessary to finalise a design for LTA's, the qualification on an industrial case could be targeted around 2032. By then, the average age of EDF existing reactors will be 47 years old. Coherence of the nuclear fuel cycle The feasibility of a new fuel design needs to be assessed for each step of the fuel cycle. The specificity in the French nuclear fuel cycle stems from the spent fuel processing performed at La Hague plant, and the recycling of the recovered recyclable materials (uranium and plutonium). When a new fuel is used at an industrial scale, it is necessary to keep the feasibility of plutonium and reprocessed uranium recycling safe, taking into account the reactors safety limitations. For example, the increase in the average fuel assembly

  10. Thermal-hydraulic experiment for safe and stable operation of a PIUS-type reactor

    International Nuclear Information System (INIS)

    Tasaka, K.; Imai, S.; Masaoka, H.; Irianto, I.D.; Kohketsu, H.; Tamaki, M.; Anoda, Y.; Murata, H.; Kukita, Y.

    1992-01-01

    A new automatic pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed for the PIUS-type reactor. This control system maintains the fluid temperature at the axial center of the lower density lock at the average of the fluid temperatures below and above the density lock in order to prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments such as start-up and power ramping tests for normal operation simulation and a loss of feedwater test for an accident condition simulation, using a small scale atmospheric pressure test loop which simulated the PIUS principle. (author)

  11. Declassification of radioactive water from a pool type reactor after nuclear facility dismantling

    Science.gov (United States)

    Arnal, J. M.; Sancho, M.; García-Fayos, B.; Verdú, G.; Serrano, C.; Ruiz-Martínez, J. T.

    2017-09-01

    This work is aimed to the treatment of the radioactive water from a dismantled nuclear facility with an experimental pool type reactor. The main objective of the treatment is to declassify the maximum volume of water and thus decrease the volume of radioactive liquid waste to be managed. In a preliminary stage, simulation of treatment by the combination of reverse osmosis (RO) and evaporation have been performed. Predicted results showed that the combination of membrane and evaporation technologies would result in a volume reduction factor higher than 600. The estimated time to complete the treatment was around 650 h (25-30 days). For different economical and organizational reasons which are explained in this paper, the final treatment of the real waste had to be reduced and only evaporation was applied. The volume reduction factor achieved in the real treatment was around 170, and the time spent for treatment was 194 days.

  12. Hydraulic model tests for 100D type primary reactor coolant pump

    International Nuclear Information System (INIS)

    Takezawa, Kiyomi; Miyamoto, Satoshi; Tagawa, Masashi; Yamada, Isao; Yoshida, Yoshiki; Uehara, Sakuichiro.

    1985-01-01

    We are now energetically promoting the design and development for domestic production of the 100D type (for 50 Hz) as the primary reactor coolant pump for units No. 1, 2 at the Tomari Nuclear Power Station of the Hokkaido Electric Power Co. In this connection, a hydraulic model test was conducted on a 1/2.54 scale model to evaluate the hydraulic characteristics of the pump, which is essential for the basic structure and reliability of the pump, and the fluid exciting force, which is indispensable for evaluating the soundness of the shafting. As a result, these characteristics were determined and the hydraulic characteristics were improved, while a hydraulic design base was established and the validity of the design was confirmed. This paper reports the results of the hydraulic model test, and discusses the optimum hydraulic structure for the designing of actual units to be manufactured henceforth. (author)

  13. Method of determining the composition of fuels for FBR type reactors

    International Nuclear Information System (INIS)

    Tsutsumi, Kiyoshi.

    1981-01-01

    Purpose: To improve the core safety of FBR type reactors by determining the composition of fuels composed of oxide mixture of plutonium and uranium, using a relation between specific plutonium seed and plutonium enrichment degree. Method: Relation is determined between the ratio of a specific plutonium seed for constituting plutonium oxide, for example 239 U ratio and a plutonium enrichment degree required for setting the assembly power to a constant level. The ratio of 239 U is plutonium having a given isotopic ratio is also determined. The accuracy of the 239 U ratio can be improved by the correction using the density coefficient. Then, the plutonium enrichment degree is determined using the relation determined as above based on the thus determined 239 U ratio. The composition of the fuel using oxide mixture of plutonium and uranium is determined by utilizing the thus obtained plutonium enrichment degree. (Moriyama, K.)

  14. Risk based definition of TS requirements for NPPs with WWER-1000 type reactor

    International Nuclear Information System (INIS)

    Morozov, V.; Tokmachev, G.

    2000-01-01

    The main regulations in safety related maintenance for NPPs in Russia are defined as a part of Technical Specifications (TSs). It includes limiting conditions for operation (surveillance requirements, allowed outage time, et.). In Russian practice the two levels of TSs are presented: general TSs that have been established as a master documents for similar designed NPPs and plant specific based on operation practice of each NPP unit. This paper presents a brief review of submissions to TS changes for NPPs with WWER type reactor were issued by AEP PSA team since 1988 year. Besides it provides an approach allows to estimate the complex affect on plant risk for both Limiting Conditions of Operation (LCO) and Surveillance Test Intervals (STI) based on relevant probabilistic tool (Minimal Cut Sets method and Marcov Chains methods). (author)

  15. Seismic response of high temperature gas-cooled reactor core with block-type fuel, (2)

    International Nuclear Information System (INIS)

    Ikushima, Takeshi; Honma, Toshiaki.

    1980-01-01

    For the aseismic design of a high temperature gas-cooled reactor (HTGR) with block-type fuel, it is necessary to predict the motion and force of core columns and blocks. To reveal column vibration characteristics in three-dimensional space and impact response, column vibration tests were carried out with a scale model of a one-region section (seven columns) of the HTGR core. The results are as follows: (1) the column has a soft spring characteristic based on stacked blocks connected with loose pins, (2) the column has whirling phenomena, (3) the compression spring force simulating the gas pressure has the effect of raising the column resonance frequency, and (4) the vibration behavior of the stacked block column and impact response of the surrounding columns show agreement between experiment and analysis. (author)

  16. A full scope nuclear power plant simulator for multiple reactor types with virtual control panels

    International Nuclear Information System (INIS)

    Yonezawa, Hisanori; Ueda, Hiroki; Kato, Takahisa

    2017-01-01

    This paper summarizes a full scope nuclear power plant simulator for multiple reactor types with virtual control panels which Toshiba developed and delivered. After the Fukushima DAIICHI nuclear power plants accident, it is required that all the people who are engaged in the design, manufacturing, operation, maintenance, management and regulation for the nuclear power plant should learn the wide and deep knowledge about the nuclear power plant design including the severe accident. For this purpose, the training with a full scope simulator is one of the most suitable ways. However the existing full scope simulators which are consist of the control panels replica of the referenced plants are costly and they are hard to remodel to fit to the real plant of the latest condition. That's why Toshiba developed and delivered the new concept simulator system which covers multiple referenced plants even though they have different design like BWR and PWR. The control panels of the simulator are made by combining 69 large Liquid Crystal Display (LCD) panels with touch screen instead of a control panel replica of referenced plant. The screen size of the each panel is 42 inches and 3 displays are arranged in tandem for one unit and 23 units are connected together. Each panel displays switches, indicators, recorders and lamps with the Computer Graphics (CG) and trainees operate them with touch operations. The simulator includes a BWR and a PWR simulator model, which enable trainees to learn the wide and deep knowledge about the nuclear power plant of BWR and PWR reactor types. (author)

  17. Status, results and usefulness of risk analyses for HTGR type reactors of different capacity accessory to planning

    International Nuclear Information System (INIS)

    Kroeger, W.; Mertens, J.

    1985-01-01

    As regards system-inherent risks, HTGR type reactors are evaluated with reference to the established light-water-moderated reactor types. Probabilistic HTGR risk analyses have shown modern HTGR systems to possess a balanced safety concept with a risk remaining distinctly below legally accepted values. Inversely, the development and optimization of the safety concepts have been (and are being) essentially co-determined by the probabilistic analyses, as it is technically sensible and economically necessary to render the specific safety-related HTGR properties eligible for licensing. (orig./HP) [de

  18. 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

  19. Design and fabrication of a fixed-bed batch type pyrolysis reactor for pilot scale pyrolytic oil production in Bangladesh

    Science.gov (United States)

    Aziz, Mohammad Abdul; Al-khulaidi, Rami Ali; Rashid, MM; Islam, M. R.; Rashid, MAN

    2017-03-01

    In this research, a development and performance test of a fixed-bed batch type pyrolysis reactor for pilot scale pyrolysis oil production was successfully completed. The characteristics of the pyrolysis oil were compared to other experimental results. A solid horizontal condenser, a burner for furnace heating and a reactor shield were designed. Due to the pilot scale pyrolytic oil production encountered numerous problems during the plant’s operation. This fixed-bed batch type pyrolysis reactor method will demonstrate the energy saving concept of solid waste tire by creating energy stability. From this experiment, product yields (wt. %) for liquid or pyrolytic oil were 49%, char 38.3 % and pyrolytic gas 12.7% with an operation running time of 185 minutes.

  20. Some economic aspects of natural uranium graphite gas reactor types. Present status and trends of costs in France

    International Nuclear Information System (INIS)

    Gaussens, J.; Tanguy, P.

    1964-01-01

    The first part of this report defines the economic advantages of natural uranium fuels, which are as follows: the restricted number and relatively simple fabrication processes of the fuel elements, the low cost per kWh of the finished product and the reasonable capital investments involved in this type of fuel cycle as compared to that of enriched uranium. All these factors combine to reduce the arbitrary nature of cost estimates, which is particularly marked in the case of enriched uranium due to the complexity of its cycle and the uncertainties of plutonium prices). Finally, the wide availability of yellowcake, as opposed to the present day virtual monopoly of isotope separation, and the low cost of natural uranium stockpiling, offer appreciable guarantees in the way of security of supply and economic and political independence as compared with the use of enriched uranium. As far as overall capital investments are concerned, it is shown that, although graphite-gas reactor costs are higher than those of light water reactors in certain capacity ranges, the situation becomes far less clear when we start taking into account, in the interest of national independence, the cost of nuclear fuel production equipment in the case of each of these types of reactor. Finally, the marginal cost of the power capacity of a graphite-gas reactor is low and its technological limitations have receded (owing particularly to the use of prestressed concrete). It is a well known fact that the trend is now towards larger power station units, which means that the rentability of natural uranium graphite reactors as compared to other types of reactors will become more and more pronounced. The second section aims at presenting a realistic short and medium term view of the fuel, running, and investment costs of French natural uranium graphite gas, reactors. Finally, the economic goals which this type of reactor can reach in the very near future are given. It is thus shown that considerable

  1. Performance of compact fast pyrolysis reactor with Auger-type modules for the continuous liquid biofuel production

    Science.gov (United States)

    Nishimura, Shun; Ebitani, Kohki

    2018-01-01

    Development of a compact fast pyrolysis reactor constructed using Auger-type technology to afford liquid biofuel with high yield has been an interesting concept in support of local production for local consumption. To establish a widely useable module package, details of the performance of the developing compact module reactor were investigated. This study surveyed the properties of as-produced pyrolysis oil as a function of operation time, and clarified the recent performance of the developing compact fast pyrolysis reactor. Results show that after condensation in the scrubber collector, e.g. approx. 10 h for a 25 kg/h feedstock rate, static performance of pyrolysis oil with approximately 20 MJ/kg (4.8 kcal/g) calorific values were constantly obtained after an additional 14 h. The feeding speed of cedar chips strongly influenced the time for oil condensation process: i.e. 1.6 times higher feeding speed decreased the condensation period by half (approx. 5 h in the case of 40 kg/h). Increasing the reactor throughput capacity is an important goal for the next stage in the development of a compact fast pyrolysis reactor with Auger-type modules.

  2. Flow pattern analysis of a full-scale expanded granular sludge bed-type reactor under different organic loading rates.

    Science.gov (United States)

    Zheng, M X; Wang, K J; Zuo, J E; Yan, Z; Fang, H; Yu, J W

    2012-03-01

    The hydraulic characteristics of a lab-scale and a full-scale (275 m(3)) expanded granular sludge bed (EGSB)-type reactor under different organic loading rates varying from 10 kg COD m(-3)d(-1) to 45 kg COD m(-3)d(-1) were investigated. A modified combined model composed of two completely mixing regions and a plug flow region was sufficient for simulating the flow pattern of a full-scale EGSB-type reactor. Moreover, the outputs fitted the measured tracer distribution results well. The simplified model structure was in very good agreement with the physical structure of a full-scale EGSB-type reactor. The upflow (liquid+gas) velocity, high concentration of granular sludge, and gas hold-up effect may contribute to the generation of dead spaces (maximum of 19.5%). The bed expansion characteristics indicated that the sludge bed of the EGSB-type reactor performed as a suspended bed, in which the bed expansion was controlled between 20% and 30%, rather than the usually considered expanded bed. Copyright © 2011 Elsevier Ltd. All rights reserved.

  3. Monitoring device for shaft oscillation of reactor incorporated-type recycling pump

    International Nuclear Information System (INIS)

    Miyashita, Kaoru; Shibasaki, Kimiyuki.

    1995-01-01

    The present invention concerns monitoring of recycling pump shaft oscillation in a BWR type reactor, which monitors by separating a rotation pulse signal and a shaft oscillation waveform signal obtained in a non-contact type displacement meter. Namely, a threshold value calculation means of a separation processing section takes in original waveform data and selects the maximum value and the minimum value among them. A threshold value is calculated based on the values. An average value of the original waveform data for portions which do not exceed the threshold value is calculated. A first calculation means compares each of the original data with the threshold value, and if the original data are greater than the threshold value, they are outputted as the original data corresponding to the rotation pulse signal. When the original data are smaller than the threshold value, they are outputted as they are as a shaft oscillation waveform signal. On the other hand, a second calculation means calculates an average value for the pulse of the original waveform data corresponding to the rotation pulse signal. An average value of the original waveform data which do not exceed the threshold value are subtracted from the average value, to form the shaft oscillation waveform signal and output the same. (I.S.)

  4. Inteligencias en diferentes enfoques teóricos

    Directory of Open Access Journals (Sweden)

    D'Antoni, Maurizia

    2004-06-01

    Full Text Available El siguiente artículo reflexiona sobre enfoques teóricos que sustentan el estudio de las inteligencias y su pertinencia. Se toman en cuenta dos diferentes enfoques teóricos: el humanismo –tomando en cuenta una de sus recientes reformulaciones- y el cognitivismo, específicamente el aporte de Gardner. Al preguntarse el texto si los conceptos de “inteligencias personales” y “persona autorrealizada” tienen alguna relación teórica, se reseñan y comparan algunas de las principales conclusiones de Abraham Maslow y Howard Gardner. Este artículo es parte del trabajo que se realiza para trazar el marco teórico de un proyecto de extensión para la Universidad Nacional, denominado “Olimpiadas de la Inteligencia Emocional”. En ese mismo ámbito, se reflexiona sobre la orientación teórica de otros estudios latinoamericanos y su validez. The next article is a reflection upon theoretical focuses that sustain the study of intelligence and their pertinence. It explores the perspective of two different theoretical approaches, humanism –taking into account one of the recent reformulations- and cognitivism, in the broadest sense of the term. The text queries whether the concepts of “personal intelligences” and “self realized person” have any theoretical relation, it resumes them and compares some of the principal contributions made by Abraham Maslow and Howard Gardner. This article is part of the work that was undertaken to establish the theoretical guidelines of an extension project by the Universidad Nacional, titled “Emotional Intelligence Olympics”. In the same context, there is a reflection on the theoretical orientation of other latinamerican studies and their validity.

  5. La inteligencia emocional y el sector financiero colombiano

    Directory of Open Access Journals (Sweden)

    Rodrigo Zárate Torres

    2010-08-01

    Full Text Available Existe un consenso general que dice que la inteligencia emocional es la habilidad de los individuos de lidiar con las emociones (Salovey y Mayer, 1990; Law, Wong y Song, 2004; Mayer, Caruso y Salovey, 2000; Wong, Law y Wong, 2004a; Wong, Wong y Law, 2007 y que es tan o más importante que el coeficiente intelectual en la vida de negocios y en la carrera profesional (Erkus, 2008; Goleman, 1995. Poco se ha estudiado acerca de la inteligencia emocional y la mayoría de estudios existentes se han realizado en los Estados Unidos, Europa y Asia. Este artículo reporta los resultados de una investigación acerca de la inteligencia emocional en los líderes que están a nivel de gerencia o supervisión del sector financiero colombiano. Para lograr la investigación se utilizó el instrumento desarrollado por Wong y Law (2002 y en total se obtuvo una muestra de 218 participantes. Este instrumento ha sido probado y validado y como resultado se ha concluido que puede ser usado en las áreas de gerencia, liderazgo y comportamiento organizacional (Aslan y Erkus, 2008. Los resultados sugieren que los líderes del sector financiero colombiano saben cómo usar sus emociones, es decir las direccionan hacia actividades constructivas y desempeño personal. Con una amplia ventaja, los líderes del sector financiero valoran y entienden sus propias emociones y las expresan de manera natural. A manera de oportunidad de mejoramiento, se encontró que a los líderes del sector financiero colombiano se les dificulta recobrarse rápidamente de los altibajos emocionales y de la angustia, y también se les dificulta percibir y entender las emociones de las personas a su alrededor.

  6. Predicción de quiebras empresariales mediante inteligencia artificial

    OpenAIRE

    Montero Casarejos, Álvaro

    2016-01-01

    El estudio de la predicción de quiebras empresariales ha incrementado su interés e importancia durante los últimos años, especialmente desde comienzo de la crisis de 2008, diferentes actores de la economía mundial, han requerido de sistemas capaces de identificar señales de insolvencia, con objeto de evitar los conocidos escenarios adversos asociados a las quiebras. A partir de los años 90, el campo de la Inteligencia Artificial se adentra en el estudio de la quiebra empresarial, consiguie...

  7. La Inteligencia colectiva en la productividad grupal: una prueba piloto

    OpenAIRE

    Cerro Ramón, Susana del; Chaves, Antonio; Ros, Eulàlia; Martí, Margarita; Soler, Guillem; Moreno, Carlos M.; Cifré, Ignacio; Noguera, Manel; Lugo, Oriol; Isanta, Carme; Pintado, Ignacio; Monzonis, Robert

    2016-01-01

    El trabajo en equipo ha sido siempre un elemento a tener presente en los grupos y, sobre todo, en la productividad de las organizaciones. Las características de los integrantes de una organización son esenciales para el objetivo productivo del grupo y no solo elementos como la motivación o la orientación a la tarea. Aspectos más intrínsecos del individuo como la sensibilidad social y la inteligencia emocional facilitan la consecución de los objetivos con mayor eficacia y eficiencia. En este s...

  8. La Inteligencia Economica como Herramienta para la Competitividad.

    OpenAIRE

    Carmen Rodríguez Acosta; Nidia Sánchez Puigbert; Aylyn Barrios Santana

    2005-01-01

    El concepto de competitividad se encuentra muy bien identificado en los procesos de modernización, reconversión o ajuste que se realiza en nuestras entidades económicas. Existen diferentes factores o instrumentos que permiten la materialización de los mismos; entre ellos se destacan la Planificación Estratégica, la Gestión de la Calidad, la Gestión Tecnológica, la Inteligencia Competitiva y la Prospectiva. Con respecto a estos dos últimos aspectos, debemos destacar que el éxito de la gesti...

  9. La inteligencia emocional en el ámbito enfermero

    OpenAIRE

    Villalba López, Alicia

    2017-01-01

    [EN] Este trabajo pretende mediante una revisión bibliográfica dar a conocer, en términos sencillos, el concepto de Inteligencia emocional (I.E) en general y específicamente en el ámbito enfermero y estudiantes de enfermería, a través de un proceso que sigue las distintas teorías que han tomado importancia a lo largo del tiempo, desde Salovey y Mayer, recalcando la importancia del maestro por excelencia Daniel Goleman. En el marco teórico nos vemos inmersos en la práctica de la IE y ...

  10. Tecnologías en la inteligencia ambiental

    OpenAIRE

    Corrales Ramón, Juan Antonio; Torres Medina, Fernando; Candelas Herías, Francisco Andrés

    2006-01-01

    En este artículo se presenta el término “Inteligencia Ambiental” (AmI) y se describen las distintas tecnologías que posibilitan su desarrollo: la computación ubicua, la comunicación ubicua y las interfaces inteligentes. Enumeraremos las distintas técnicas de localización que se usan en los entornos inteligentes para determinar la ubicación del usuario y poder ofrecerle así los servicios más adecuados. Para comprender mejor las posibilidades de la AmI, también mostraremos sus principales áreas...

  11. Inteligencias múltiples y aprendizaje: Un enfoque comparativo en alumnos de conservatorio

    OpenAIRE

    Athanassopoulos, Néstor; López-Fernández, Verónica

    2017-01-01

    La Teoría de las inteligencias Múltiples defiende que la competencia cognitiva se describe mejor en términos de un conjunto de habilidades o capacidades mentales que todos poseemos y podemos desarrollar. Método: Este trabajo pretende comparar dos grupos de estudiantes, formados por alumnos que cursan estudios de danza y alumnos que no los cursan, en su nivel de desarrollo de las Inteligencias Múltiples. La muestra está compuesta por 175 personas. Para conocer el nivel de las Inteligencias múl...

  12. TRANSFERENCIA DE INTELIGENCIAS MÚLTIPLES EN ALUMNOS CON AUTISMO DE EDUCACIÓN PRIMARIA

    OpenAIRE

    Plágaro-Martos, Miriam

    2015-01-01

    El presente estudio de investigación está basado en la Teoría de la Inteligencias Múltiples, descrita por Howard Gardner en 1983. Así como en el concepto de inteligencia emocional, acuñado por Daniel Goleman en 1995. Estudiamos el nivel de desarrollo en cada inteligencia múltiple, en alumnos diagnosticados con Trastorno de Espectro Autista, autismo. Componiéndose la muestra de estudio por 30 alumnos con dicho diagnóstico, escolarizados en la etapa educativa de educación primaria. Para el desa...

  13. Estudio de las Inteligencias Múltiples en el TDAH: propuesta de intervención

    OpenAIRE

    León-Sánchez, Susana de los Ángeles

    2013-01-01

    La Teoría de las Inteligencias Múltiples, (IM) aparece en 1983 como alternativa al concepto tradicional de inteligencia y reconoce la existencia de diferentes formas de entender y estudiar de forma más contextualizada y pragmática. En este estudio se investigan las dificultades que pueden mostrar, en sus inteligencias múltiples, un grupo de niños que padecen TDAH de los tres subtipos, con respecto a un grupo de niños que no padece dicho trastorno, para poder realizar un programa de intervenci...

  14. Creatividad e inteligencias múltiples. Estudio y plan de intervención.

    OpenAIRE

    Pazos-Pazos, Elisa María

    2013-01-01

    Gardner postuló en 1983 la Teoría de las Inteligencias Múltiples en contra de la visión unitaria de la inteligencia que había hasta entonces. Por otra parte, nuestra sociedad demanda infividuos creativos y críticos. La creatividad cada vez se exige más y es más importante en nuestra vida. Bajo estas premisas se desarrolla este trabajo de investigación con la finalidad de adaptar estos nuevos conceptos al aula. A tal fin, nos hemos preguntado si los niveles de inteligencias múltiples y creativ...

  15. Las inteligencias múltiples en Educación Infantil

    OpenAIRE

    Ceballos González, Eric

    2015-01-01

    El objetivo del presente trabajo fin de grado es dar una visión de la posibilidades que nos ofrece las inteligencias múltiples para trabajarlas en la educación infantil. Apoyándose en la base de la las teorías de la inteligencia y los avances de la misma hasta llegar a la teoría de las Inteligencias múltiples. Tomando como mayor representante de dicha teoría a Howard Gadner Grado en Educación Infantil

  16. Inteligencia emocional y rendimiento académico en estudiantes universitarios

    OpenAIRE

    Martha Luz Páez Cala; José Jaime Castaño Castrillón

    2015-01-01

    El estudio tuvo como objetivo describir la inteligencia emocional y determinar su relación con el rendimiento académico en estudiantes universitarios. Participaron 263 estudiantes, a quienes se les aplicaron diversos instrumentos, entre ellos el cuestionario EQ -i de Bar O n para medir la inteligencia emocional. Se encontró un cociente de inteligencia emocional promedio de 46,51, sin diferencias según género, pero sí para cada programa: 62,9 para Economía; 55,69 en Medicina; 54,28 en Ps...

  17. Frequency response analysis of NPP containment with WWER-1000 type reactor

    International Nuclear Information System (INIS)

    Zoubkov, D.; Isaikin, A.; Shablinsky, G.

    2005-01-01

    Analysis of vibration load on the building structures of nuclear power plants (NPP) has come to the fore due to extension of their operational lifetime. Such analysis could be carried out if dynamic characteristics test (natural vibration frequency and natural mode) of NPP building structures is conducted in full-scale conditions. In this paper we represent methods of frequency response analysis of the generating unit 1 (RO-1) reactor compartment at Kalininskaya NPP on the basis of technogenic vibration. Main vibration sources of RO-1 are turbine-type generators, main centrifugal pumps and pipelines of power generating units 1 and 2. Vibration of RO-1 has been measured alternately at three points of RO-1 containment which is 76 m high and 47.4 m in diameter: top of the dome (76.0 m), holdout ring (70.3 m), point on the ground next to containment (0.0 m). Three components of vibration velocity have been measured simultaneously at each point: vertical Z-component, horizontal Y-component along the axis of the apparatus room and horizontal X-component across the room axis. Magnetoelectric pendulum-type vibrometers have been used for measurement. They were modernized by ad hoc multiposition amplifier card installed into the sensor body. Vibrometers were connected to the recorder by vibration protected and jam resistant cables. The results of present researches testified that dominant frequencies of X- and Y-oscillation spectra at RO-1 of Kalininskaya NPP (1.7 and 1.9 Hz correspondingly) correspond to the first vibration mode of RO-1 as a rigid construction on elastic foundation. High peaks of spectra at 16.7 and 25 Hz result from vibrations caused by main centrifugal pumps and turbine-type generators and coincide with the number of their revolutions per minute (1000 and 1500 rpm). Other peaks of spectra are related to the vibration of pipelines of primary and secondary circuits. (authors)

  18. Experimental evaluation of two different types of reactors for CO2removal from gaseous stream by bottom ash accelerated carbonation.

    Science.gov (United States)

    Lombardi, L; Carnevale, E A; Pecorini, I

    2016-12-01

    Low methane content landfill gas may be enriched by removing carbon dioxide. An innovative process, based on carbon dioxide capture and storage by means of accelerated carbonation of bottom ash is proposed and studied for the above purpose. Within this research framework we devoted a preliminary research activity to investigate the possibility of improving the way the contact between bottom ash and landfill gas takes place: this is the scope of the work reported in this paper. Two different types of reactors - fixed bed and rotating drum - were designed and constructed for this purpose. The process was investigated at laboratory scale. As the aim of this phase was the comparison of the performances of the two different reactors, we used a pure stream of CO 2 to preliminarily evaluate the reactor behaviors in the most favorable condition for the process (i.e. maximum CO 2 partial pressure at ambient condition). With respect to the simple fixed bed reactor concept, some modifications were proposed, consisting of separating the ash bed in three layers. With the three layer configuration we would like to reduce the possibility for the gas to follow preferential paths through the ash bed. However, the results showed that the process performances are not significantly influenced by the multiple layer arrangement. As an alternative to the fixed bed reactor, the rotating drum concept was selected in order to provide continuous mixing of the solids. Two operating parameters were considered and varied during the tests: the filling ratio and the rotating speed. Better performances were observed for lower filling ratio while the rotating speed showed minor importance. Finally the performances of the two reactors were compared. The rotating drum reactor is able to provide improved carbon dioxide removal with respect to the fixed bed one, especially when the rotating reactor is operated at low filling ratio values and slow rotating speed values. Comparing the carbon dioxide

  19. Swelling, mechanical properties, and microstructure of Type 316 stainless steel at fusion reactor damage levels

    International Nuclear Information System (INIS)

    Horak, J.A.; Bloom, E.E.; Grossbeck, M.L.; Maziasz, P.J.; Stiegler, J.O.; Wiffen, F.W.

    1979-01-01

    Alloys such as AISI 316 stainless steel exhibit more swelling and larger decreases in ductility when irradiated to produce fusion reactor He and dpa levels than at fast reactor He and dpa levels. For T approx. 0 C to ensure adequate ductility for long-term service

  20. Development of the radiation models of a BWR type reactor and it facility in the SUN-RAH

    International Nuclear Information System (INIS)

    Barron A, I.

    2005-01-01

    This work about generation models, transport in processes and radioactive contamination of areas of a BWR central, is an amplification to the project developed in the UNAM to have a support tool in subjects or electric generation courses. It is planned about the implementation of models of radiation generation in a BWR type reactor for complement the functions developed in the University Simulator of Nucleo electric- Boiling water reactor (SUN-RAH) which it has been implemented in Simulink of MatLab and it has a model for the dynamics of one nucleo electric central that presents the main characteristics of the reactor vessel, the recirculation system, steam lines, turbines, generator, condensers and feeding water, defined by the main processes that intervene in the generation of energy of these plants. By this way the radiation monitoring systems for area and process, operate simultaneously with the processes of energy generation, with that is possible to observe the changes that present with respect to the operation conditions of the plant, and likewise to appreciate the radiation transport process through the components of the reactor, steam lines and turbines, for different operation conditions and possible faults that they could be presented during the reactor operation. (Author)

  1. Rearrangement of fuel assemblies in the RBMK type reactors to flatten power distribution and improve the fuel cycle

    International Nuclear Information System (INIS)

    Mityaev, Yu.I.; Vikulov, V.K.

    1982-01-01

    A possibility of increasing the burnup of uranium fuel unloaded from the RBMK type reactors is investigated. Three variants of a two-zone reactor-refueling are considered: 1. the simplest variant of continuous refueling used at present, when the central and peripherical reactor zones are additionally fueled independently by similar fuel assemblies (FA); 2. the variant under which new FA are loaded to the peripherical zone and are used there up to the same burnup as in the first case, then all the peripherical FA (PFA) are rearranged to the centre and they are used there up to maximum burnup; 3. the same as in the second variant, but not all the PFA are rearranged to the centre but only FA with small fuel burnup. It is shown by calculation that average fuel burnup for the third refueling variant is several per cent higher at the optimal burnup of rearranged FA. Besides, flattening of fuel channel power is improved in this case, that permits to increase uranium enrichment and burnup at the same maximum power. It essentially improves economic parameters of the reactor. It is concluded that realization of the considered variant of fuel refueling will produce the most essential effect for reactors refueled without shutdown

  2. Utilization of a HTR type reactor as a heat source for the processing of pyrobituminous shale by the Petrosix method

    International Nuclear Information System (INIS)

    Pessine, R.T.

    1977-01-01

    Some thermodynamics aspects of a system resulting from the coupling of a THTR nuclear power plant type (Thorium High Temperature Reactor) and a commercial shale oil processing plant are studied. The coupling is basically characterized by the application of all available energy from the nuclear reactor to the shale oil processing. The nuclear reactor employed is a PR-3000, with 2980,8 MW sub(t), developed in the Federal Republic of Germany for process heat applications (coal and steam reforming to produce reducers and products similar to the derivates of petroleum). The commercial shale oil plant considered (U.C.X.) uses the Petrosix process developed by the Superintendencia da Industrializacao do Xisto (S.I.X.) of Petrobras. Some flow diagrams are proposed for the coupling between the basic cycle of PR-3000 reactor with hot gas cycle of U.C.X. For a pre-determined flow diagram and boundary conditions, the thermodynamic parameters that lead to a maximum efficiency of the system are established. Also the main steam cycle parameters of PR-3000 reactor are determined, including those for the main heat exchanger, whose data are similar to the corresponding steam and coal reforming system used in process heat application of the PR-3000 [pt

  3. VEERA facility for studies of nuclear safety in VVER type reactors

    International Nuclear Information System (INIS)

    Puustinen, M.; Tuunanen, J.; Raussi, P.

    1994-01-01

    The VEERA facility was built in 1987 for experiments that simulate soluble neutron poison (boric acid) behaviour in a pressurized water reactor (PWR) during the long-term cooling period of loss-of-coolant accidents (LOCAs). The experiments provided insight especially into the processes of concentration, mixing and possible crystallization of boric acid in the core region of a PWR. In 1993 the facility was modified in order to use it for studies of the reflooding phenomenon. The results of the reflood experiments will be used as a data base for testing the capability of the reflood models of different computer codes. The VEERA facility in its original and modified forms is described in this report. Details of the geometry and dimensions of the components are given. This data is needed as a geometrical boundary condition in input deck preparation for thermal hydraulic analysis. The instrumentation and the data acquisition system are described so that the applicability of the facility and the accuracy of the measurements for different types of experiments can be evaluated. Initial and boundary conditions of the experiments and the principal test procedures are also summarized. (orig.) (24 figs., 6 tabs.)

  4. A practical methodology of radiological protection for the reduction of hot particles in BWR type reactors

    International Nuclear Information System (INIS)

    Alvarez G, G.

    1991-01-01

    The purpose of this work, in general form, is to describe a practical method for reduction of hot particles generated as consequence of the operational activities of BWR nuclear reactors. This methodology provides a description of the localizations and/or probable activities of finding particles highly radioactive denominated hot particles. For this purpose it was developed a strategy based on the decontamination lineaments, as well as the manipulation, gathering, registration, contention, documentation, control and final disposition of the hot particles. In addition, some recommendations are reiterated and alternative, in order to gathering the hot particles in a dynamic way given to the activities of the personal occupationally exposed in highly radioactive areas. The structure of the methodology of hot particles is supported in the radiological controls based on the Code of Federal Regulation 10 CFR 20 as well as the applicable regulatory documents. It provides an idea based on administrative controls of radiological protection, in order to suggesting the responsibilities and necessary directing for the control of the hot particles required in nuclear plants of the BWR type. (author)

  5. refining device for helium coolants capable of continuous tritium recovery for use with HTGR type reactors

    International Nuclear Information System (INIS)

    Tone, Hirohito.

    1981-01-01

    Purpose: To separate and recover hydrogen and tritium from helium coolants by a device comprising a tritium permeable metal film, a gas compressor and a recovery store container. Constitution: Impurity gas-containing helium sent from a primary helium coolant circuit exit of an HTGR type reactor to a helium refining system is introduced by way of a high temperature heat exchanger, a gas recycling device and a medium temperature heat exchanger to an absorber bed filled with absorber, where H 2 O and CO 2 in the impurity gas-containing helium are removed. Then, Kr, Xe, Ar, O 2 , N 2 , CO, CH 3 are removed and the remaining impurities, tritium and hydrogen, are introduced via each of heat exchangers into a tritium absorber bed. Then, they are permeated through a tritium permeable metal film, transferred to the low pressure side of a tritium permeation device and then compressed and stored in a tritium recovery store container by a gas compressor connected to the low pressure side. (Seki, T.)

  6. On modular stellarator coils of the W VII-AS type with reactor dimensions

    International Nuclear Information System (INIS)

    Hermeyer, E.; Kisslinger, J.; Rau, F.; Wobig, H.

    1985-01-01

    Modular Stellarator coil systems of the W VII-AS type with reactor dimensions are investigated. They comprise 5 field periods with 6 to 18 coils within each. Two groups of configurations are compared. The first group is characterized by the major torus radius of R 0 = 25.5 m and a distance between plasma and coils of ccdcc 1.8 m. The field on plasma axis amounts to B 3 = 5.3 T. In the second group the geometric dimensions are decreased. The major torus radius amounts to R 3 = 15.2 m, and a distance of about 1.2 m is chosen between plasma and coils. The field on plasma axis is enlarged to B 3 = 7 T. The total stored magnetic energy of the coil systems and the maximum magnetic flux density at the coils are calculated. Furthermore, the magnetic forces and mechanical stresses are evaluated, and two different support concepts for the coils are investigated: A single coil support scheme (outer and lateral support elements plus elastic padding), as well as a novel scheme of mutual coil support

  7. Not a mystery. Inner containment of the pressurized water reactor (EPR trademark type)

    Energy Technology Data Exchange (ETDEWEB)

    Ostermann, Dirk; Wienand, Burkhard; Krumb, Christian [AREVA NP GmbH (Germany)

    2012-11-01

    The containment of the advanced pressurized water reactor EPR trademark type is developed on the basis of the French nuclear power plant operational experience and consists of - The reinforced outer containment structure, designed to withstand external hazards (e.g. APC), - The pre-stressed inner containment structure, designed to bear the loads resulting from internal hazards (LOCA), - The steel liner, designed to provide leak tightness resulting from internal hazards. The main advantage of the pre-stressed inner containment design is that the structure remains in linear-elastic behavior during the whole life-time. Even in case of postulated design accidents (LOCA) concrete tensile strains are strongly limited. Due to pre-stressing the concrete structure remains practically free of cracks. Due to pre-stressing the leak tightness ensuring steel liner, embedded into the inner concrete shell, is exposed to more favorable compression loads. In addition to detailed calculations several test programs have been performed to verify and confirm the predicted behavior in normal operation and in accident condition. (orig.)

  8. Effect of conditions of air-lift type reactor work on cadmium adsorption

    International Nuclear Information System (INIS)

    Filipkowska, Urszula; Szymczyk, Paula Szymczyk; Kuczajowska-Zadrozna, Malgorzata; Joezwiak, Tomasz

    2015-01-01

    We investigated cadmium sorption by activated sludge immobilized in 1.5% sodium alginate with 0.5% polyvinyl alcohol. Experiments were conducted in an air-lift type reactor at the constant concentration of biosorbent reaching 5 d.m./dm 3 , at three flow rates: 0.1, 0.25 and 0.5 V/h, and at three concentrations of the inflowing cadmium solution: 10, 25 and 50mg/dm 3 . Analyses determined adsorption capacity of activated sludge immobilized in alginate as well as reactor's work time depending on flow rate and initial concentration of the solution. Results achieved were described with the use of Thomas model. The highest adsorption capacity of the sorbent (determined from the Thomas model), i.e., 200.2mg/g d.m. was obtained at inflowing solution concentration of 50mg/dm 3 and flow rate of 0.1V/h, whereas the lowest one reached 53.69mg/g d.m. at the respective values of 10mg/dm 3 and 0.1 V/h. Analyses were also carried out to determine the degree of biosorbent adsorption capacity utilization at the assumed effectiveness of cadmium removal - at the breakthrough point (C=0.05*C 0 ) and at adsorption capacity depletion point (C−0.9*C0). The study demonstrated that the effectiveness of adsorption capacity utilization was influenced by both the concentration and flow rate of the inflowing solution. The highest degree of sorbent capacity utilization was noted at inflowing solution concentration of 50mg/dm 3 and flow rate of 0.1 V/h, whereas the lowest one at the respective values of 10mg/dm 3 and 0.1 V/h. The course of the process under dynamic conditions was evaluated using coefficients of tangent inclination - a, at point C/C 0 =1/2. A distinct tendency was demonstrated in changes of tangent slope a as affected by the initial concentration of cadmium and flow rate of the solution. The highest values of a coefficient were achieved at the flow rate of 0.1 V/h and initial cadmium concentration of 50mg/dm 3 .

  9. Knowledge preservation of Atucha type reactor: Practical approaches and lessons learned

    International Nuclear Information System (INIS)

    Eppenstein, M.; Vetere, C.

    2004-01-01

    As Siemens, designer of the Atucha type HWRs, has transferred its nuclear activities to Framatome ANP, Argentina must undertake the knowledge preservation of this type of reactor, both if life extension is decided for the operating Atucha I NPP, and/or if ending the construction of Atucha II is decided. Another reason for undertaking a knowledge preservation program is aging and increasing retirement of personnel in the nuclear field, and the small number of young people in nuclear related disciplines at the universities. This situation motivated CNEA to implement a Knowledge Management system (KM), in order to capture and capitalize the tacit and explicit knowledge, to spread it and share it, making use of the technical and suitable tools through the organization. The strategy was based on recognizing the critical knowledge by means of a methodology incorporating the critical knowledge map technique. This map is a tool that uses the cognitive surfing in order to access to the organization heritage knowledge. Different techniques and methodologies are applied for identifying the critical knowledge domains. The result is a vigorous graphical tool with a certain formalism, able to describe knowledge in a hierarchical way in order to preserve it. It is used to analyze the criticality, and as an access portal to the knowledge patrimony, pointing out, according to each knowledge area, the people skills, publications, related documents and others. Experience obtained through the KM system development shows how training techniques are put into practice, in order not to interfere with normal plant operation, and how to initiate the KM processes in order to improve the criticity. (author)

  10. RENDIMIENTO ACADÉMICO Y AUTOPERCEPCIÓN DE INTELIGENCIAS MÚLTIPLES E INTELIGENCIA EMOCIONAL EN UNIVERSITARIOS DE PRIMERA GENERACIÓN

    Directory of Open Access Journals (Sweden)

    René Barraza López

    2016-01-01

    Full Text Available El objetivo del presente artículo fue determinar la relación entre la autopercepción de inteligencias múltiples e inteligencia emocional y el rendimiento académico alcanzado por 252 estudiantes de nivel universitario de diversas carreras de la Universidad Santo Tomás-La Serena, tras el primer año de educación universitaria. Los antecedentes teóricos y empíricos establecen que el rendimiento académico se asociaría a variables novedosas como: ser primer miembro familiar en iniciar estudios universitarios y a la autopercepción de habilidad; no obstante, la evidencia disponible respecto de esta relación es aún escasa y contradictoria, más todavía si se considera que el grupo evaluado proviene mayoritariamente de familias con padres sin formación universitaria. Desde un enfoque cuantitativo se aplicó la escala TMMS-24 para la evaluación de la autopercepción de inteligencia emocional y la escala MIDAS-teens para la evaluación de la autopercepción de inteligencias múltiples. Los resultados revelan correlaciones débiles entre rendimiento académico y la autopercepción de las inteligencias: lingüística, lógico-matemática, además de una correlación inversa con la autopercepción de la rama atención de inteligencia emocional; de este modo, no evidencia correlación con la otras dimensiones de la inteligencia emocional y de las inteligencias múltiples. A partir del análisis de regresión múltiple se establece que no es posible explicar la varianza del rendimiento académico desde la autopercepción de las inteligencias mencionadas. Queda abierta la interrogante en cuanto al real efecto de la autovaloración de las propias capacidades en el rendimiento académico, como también el efecto de las formas de evaluación utilizadas en diversas áreas disciplinares respecto de estos resultados.

  11. Rendimiento académico y autopercepción de inteligencias múltiples e inteligencia emocional en universitarios de primera generación

    Directory of Open Access Journals (Sweden)

    Barraza López, René

    2016-05-01

    Full Text Available El objetivo del presente artículo fue determinar la relación entre la autopercepción de inteligencias múltiples e inteligencia emocional y el rendimiento académico alcanzado por 252 estudiantes de nivel universitario de diversas carreras de la Universidad Santo Tomás-La Serena, tras el primer año de educación universitaria. Los antecedentes teóricos y empíricos establecen que el rendimiento académico se asociaría a variables novedosas como: ser primer miembro familiar en iniciar estudios universitarios y a la autopercepción de habilidad; no obstante, la evidencia disponible respecto de esta relación es aún escasa y contradictoria, más todavía si se considera que el grupo evaluado proviene mayoritariamente de familias con padres sin formación universitaria. Desde un enfoque cuantitativo se aplicó la escala TMMS-24 para la evaluación de la autopercepción de inteligencia emocional y la escala MIDAS-teens para la evaluación de la autopercepción de inteligencias múltiples. Los resultados revelan correlaciones débiles entre rendimiento académico y la autopercepción de las inteligencias: lingüística, lógico-matemática, además de una correlación inversa con la autopercepción de la rama atención de inteligencia emocional; de este modo, no evidencia correlación con la otras dimensiones de la inteligencia emocional y de las inteligencias múltiples. A partir del análisis de regresión múltiple se establece que no es posible explicar la varianza del rendimiento académico desde la autopercepción de las inteligencias mencionadas. Queda abierta la interrogante en cuanto al real efecto de la autovaloración de las propias capacidades en el rendimiento académico, como también el efecto de las formas de evaluación utilizadas en diversas áreas disciplinares respecto de estos resultados.

  12. Method of changing the control rod pattern in BWR type reactors

    International Nuclear Information System (INIS)

    Yoshida, Kenji.

    1984-01-01

    Purpose: To enable to change the control rod pattern in a short time with ease, as well as improve the availability factor of the reactor. Method: Control rods other than those being inserted into the reactor core are inserted into the reactor core to reduce the power by the reduction in the reactor core flow rate. Then, the control rod to be operated is operated partially for the change of the control rod pattern to restrict the linear heat rating of the fuels to less than 0.1 kW/ft per one hour to change the control pattern to the aimed control rod pattern. Then, the reactor core flow rate is increased after the pattern exchange for the control rod to increase the power. Since only the control rod operation is performed without adjusting the reactor core flow rate upon change of the control rod pattern, procedures can be made simply in a short time to thereby improve the availability factor of the reactor. (Moriyama, K.)

  13. 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

  14. Enseñanza de la inteligencia exitosa para alumnos superdotados y talentos

    Directory of Open Access Journals (Sweden)

    Robert STERNBERG

    2010-01-01

    Full Text Available El objetivo del trabajo es analizar el modelo de la inteligencia exitosa como estrategia de desarrollo cognitivo para atender las necesidades educativas de los alumnos con altas habilidades. En primer lugar, exponemos la teoría de la inteligencia exitosa como alternativa en el estudio de la complejidad cognitiva de la alta habilidad desde una perspectiva más amplia de la inteligencia. En segundo lugar, se analizan los roles de alumno y profesor en el proceso de enseñanza-aprendizaje. En tercer lugar, se indican una serie de estrategias de aprendizaje orientadas a favorecer el manejo de recursos de la inteligencia académica, sintética y práctica en el aula. Finalmente, se extraen algunas conclusiones.

  15. Fundamentos de Inteligencia Artificial: Entrevista con Antonio Benítez

    Directory of Open Access Journals (Sweden)

    Asier Arias

    2012-07-01

    Full Text Available Antonio Benítez, profesor de Lógica en la Universidad Complutense de Madrid, ha dedicado buena parte de su labor docente e investigadora a la inteligencia artificial y a la filosofía de la mente y de la ciencia cognitiva. Recientemente ha publicado una obra en tres volúmenes titulada Fundamentos de Inteligencia Artificial (el tercer volumen, dedicado a la inteligencia artificial bioinspirada, aparecerá en los próximos meses. La misma ofrece una guía práctica de introducción a la programación en inteligencia artificial de clara y cabal factura, además de una cuidada introducción a los aspectos teóricos de la disciplina. En esta entrevista nos habla de esta obra y de la ciencia cognitiva en general.

  16. Selection of Type I and Type II Methanotrophic Proteobacteria in a Fluidized Bed Reactor under Non-Sterile Conditions

    Science.gov (United States)

    2011-08-01

    recycle loop from a 70-L polypropylene storage tank. Temperature and pH were monitored with a Royce Model 5000 pH/ORP Analyzer system. The reactor was...the recirculation loop and mixed with recycled water prior to delivery at the base of the FBR. A metering pump delivered nutrient solu- tion to the...into the influent port of the FBR, and the reactor was placed in a complete recycle mode, with no influent addition for 2 h to facilitate bacte- rial

  17. La inteligencia emocional: una herramienta necesaria para el liderazgo. Concepto y componentes

    OpenAIRE

    Mart?nez Percy, Armando Martin

    2013-01-01

    La inteligencia emocional ser? la herramienta y/o recurso m?s importante del siglo XXI para sobrevivir a una ?poca de ?cambio permanente?. Es b?sica para incrementar el rendimiento profesional y el bienestar personal especialmente en profesiones complejas, como las que incluyen las relaciones personales como centro y principal motor de la actividad: educaci?n, recursos humanos, comunicaci?n, etc. Daniel Goleman (1995), conocido como el autor de la inteligencia emocional, arg...

  18. Inteligencia emocional y creatividad : factores predictores del rendimiento académico.

    OpenAIRE

    Belmonte Lillo, Víctor Manuel

    2013-01-01

    El objetivo del trabajo, “Inteligencia emocional y creatividad: factores predictores del rendimiento académico”, es estudiar la validez predictiva de la inteligencia emocional desde sus diferentes modelos (habilidad, competencia socioemocional y autoeficacia emocional) y la creatividad respecto al rendimiento académico tanto en general como por ámbitos en alumnado de ESO. En las dos primeras partes se analizan los constructos en estudio. En la tercera, se aborda las implicaciones de la creati...

  19. ¿Puede la Inteligencia Emocional predecir el rendimiento?. Potencial predictor de los Moldes Mentales

    Directory of Open Access Journals (Sweden)

    Pedro HERNÁNDEZ HERNÁNDEZ

    2005-01-01

    Mentales (HERNÁNDEZ, 2002, una nueva perspectiva de la Inteligencia Emocional, basados en los formatos de pensamiento implicativo, no sólo predicen destacadamente la adaptación o el bienestar subjetivo, sino, que explican el éxito-fracaso de la escolaridad general, matemáticas o ajedrez en mayor proporción que la propia inteligencia (CI u otro indicador.

  20. Experimental facility of innovative types as the laboratory analog of research reactor experimental device

    International Nuclear Information System (INIS)

    Androsenko, A.A.; Androsenko, P.A.; Zabud'ko, A.N.; Kremenetskij, A.K.; Nikolaev, A.N.; Trykov, L.A.

    1991-01-01

    The paper analyses capability of creating laboratory analogs of complex experimental facilities at research reactors utilizing power radionuclide neutron sources fabricated in industrial conditions. Some experimental and calculational investigations of neutron-physical characteristics are presented, which have been attained at the RIZ research reactor laboratory analog. Experimental results are supplemented by calculational investigations, fulfilled by means of the BRAND three-dimensional computational complex and the ROZ-6 one-dimensional program. 4 refs.; 3 figs

  1. Analysis of steam explosions in plate-type, uranium-aluminum fuel test reactors

    International Nuclear Information System (INIS)

    Taleyarkhan, R.P.

    1989-01-01

    The concern over steam explosions in nuclear reactors can be traced to prompt critical nuclear excursions in aluminum-clad/fueled test reactors, as well as to explosive events in aluminum, pulp, and paper industries. The Reactor Safety Study prompted an extensive analytical and experimental effort for over a decade. This has led to significant improvements in their understanding of the steam explosion issue for commercial light water reactors. However, little progress has been made toward applying the lessons learned from this effort to the understanding and modeling of steam explosion phenomena in aluminum-clad/fueled research and test reactors. The purposes of this paper are to (a) provide a preliminary analysis of the destructive events in test reactors, based on current understandings of steam explosions; (b) provide a proposed approach for determining the likelihood of a steam explosion event under scenarios in which molten U-Al fuel drops into a water-filled cavity; and (c) present a benchmarking study conducted to estimate peak pressure pulse magnitudes

  2. Inteligencias múltiples (Estudio de caso

    Directory of Open Access Journals (Sweden)

    José Joaquín Martínez-Lozano

    2012-01-01

    Full Text Available Gardner (1983 argues that there is a set of relatively autonomous human skills is called human intelligence. These intelligences can be modeled and combined in multiple ways. He does not deny the genetic component, but argues that such potential will be developed in one way or another depending on the environment, life experiences, education received, among others, for that reason, all human beings are capable of the extensive development of his intelligence, supported in their abilities and motivation. All intelligences are equally important and, accordingly, the problem is that the current school system does not treat them equally, and a significant portion of students do not achieve significant learning. The work consisted of applying a standardized test that measures the most prevalent types of intelligence in students of the College of Public Administration (ESAP for, based on the results to determine the education and teaching strategies that best adjusted for these students achieve significant learning and therefore academic success. Clearly, knowing what we know about learning styles, types of intelligence and learning styles, it was absurd to continue to insist that students learn in the same way. The same subject could be presented in many different ways that allow the student to assimilate based on their skills and building on their strengths. It would have to consider whether an education focused on only two types of intelligence is best suited to prepare students to live in a world increasingly complex and technological advances flowing at an incredible speed.

  3. Inteligencia emocional y prácticas de liderazgo en las organizaciones colombianas

    Directory of Open Access Journals (Sweden)

    Rodrigo A. Zárate Torres

    2012-06-01

    Full Text Available La relación entre inteligencia emocional y liderazgo ha sido explorada por varios autores (Barbuto y Burbach, 2006; Dulewics, Young y Dulewics, 2005; Gardner y Stough, 2002; Barling, Slater y Kelloway, 2000; sin embargo, esta relación aún no se ha estudiado a profundidad en Latinoamérica. Éste estudio muestra la relación existente entre las prácticas de liderazgo y la inteligencia emocional en los empleados colombianos. Para el efecto, se aplicó el inventario de prácticas de liderazgo de Kouzes y Posner (1997 y el instrumento desarrollado por Wong y Law (2002 de inteligencia emocional a una muestra de 339 empleados de organizaciones de diferentes sectores en la ciudad de Bogotá en Colombia. Los resultados sugieren que sí existe una relación entre la inteligencia emocional y las prácticas de liderazgo. Además, que los líderes que utilizan la inteligencia emocional pueden liderar más eficientemente sus grupos de trabajo. También se encontró una relación entre la edad, el género, el nivel educativo y los años de experiencia en manejo de personal con el desarrollo de la inteligencia emocional y las prácticas de liderazgo.

  4. Radiological impact of plutonium recycle in the fuel cycle of LWR type reactors: professional exposure during mormal operation

    International Nuclear Information System (INIS)

    White, I.F.; Kelly, G.N.

    1983-01-01

    The radiological impact of the fuel cycle of light water type reactors using enriched uranium may be changed by plutonium recycle. The impact on human population and on the persons professionally exposed may be different according to the different steps of the fuel cycle. This report analyses the differential radiological impact on the different types of personnel involed in the fuel cycle. Each step of the fuel cycle is separately studied (fuel fabrication, reactor operation, fuel reprocessing), as also the transport of the radioactive materials between the different steps. For the whole fuel cycle, one estimates that, with regard to the fuel cycle using enriched uranium, the plutonium recycle involves a small increase of the professional exposure

  5. Auditoría de inteligencia: Un método para el diagnóstico de sistemas de inteligencia competitiva y organizacional

    OpenAIRE

    Vasconcelos Carvalho, Andréa; Esteban Navarro, Miguel Ángel

    2013-01-01

    El objetivo general es la elaboración de un método de auditoría de inteligencia para el diagnóstico de los sistemas de inteligencia de las organizaciones que los contemple de modo holístico y que ofrezca resultados efectivos para su perfeccionamiento. Para ello se plantean estos objetivos específicos: la identificación y el análisis de los diversos tipos de auditoría de activos de información; el análisis de los sistemas de inteligencia en el marco de sus relaciones con la organización y el e...

  6. Estudio del razonamiento lógico-matemático desde el modelo de las inteligencias múltiples

    OpenAIRE

    Ferrándiz García, Carmen; Bermejo García, María Rosario; Sainz, Marta; Ferrando, Mercedes; Prieto, María Dolores

    2008-01-01

    El objetivo del trabajo es estudiar el razonamiento lógico-matemático de una muestra de alumnos de educación infantil y primaria. Se diseñará el perfil cognitivo de los participantes en las distintas inteligencias, se estudiará la relación entre la inteligencia lógico-matemática en el modelo de Gardner y la inteligencia valorada desde una perspectiva psicométrica; finalmente, se establecerán las diferencias en inteligencia lógico-matemática en función del género y edad. En el trabajo particip...

  7. Properties of bio-oil generated by a pyrolysis of forest cedar residuals with the movable Auger-type reactor

    International Nuclear Information System (INIS)

    Nishimura, Shun; Ebitani, Kohki; Miyazato, Akio

    2016-01-01

    Our research project has developed the new movable reactor for bio-oil production in 2013 on the basis of Auger-type system. This package would be a great impact due to the concept of local production for local consumption in the hilly and mountainous area in not only Japan but also in the world. Herein, we would like to report the properties of the bio-oil generated by the developing Auger-type movable reactor. The synthesized bio-oil possessed C: 46.2 wt%, H: 6.5 wt%, N: wt%, S: <0.1 wt%, O: 46.8 wt% and H 2 O: 18.4 wt%, and served a good calorific value of 18.1 MJ/kg. The spectroscopic and mass analyses such as FT-IR, GC-MS, 13 C-NMR and FT-ICR MS supported that the bio-oil was composed by the fine mixtures of methoxy phenols and variety of alcohol or carboxylic acid functional groups. Thus, it is suggested that the bio-oil generated by the new movable Auger-type reactor has a significant potential as well as the existing bio-oil reported previously

  8. Properties of bio-oil generated by a pyrolysis of forest cedar residuals with the movable Auger-type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nishimura, Shun; Ebitani, Kohki, E-mail: ebitani@jaist.ac.jp [School of Materials Science, Japan Advanced Institute of Science and Technology, 1-1 Asahidai, Nomi, Ishikawa 923-1292 (Japan); Miyazato, Akio [Nanotechnology Center, Japan Advanced Institute of Science and Technology, 1-1 Asahidai, Nomi, Ishikawa 923-1292 (Japan)

    2016-02-01

    Our research project has developed the new movable reactor for bio-oil production in 2013 on the basis of Auger-type system. This package would be a great impact due to the concept of local production for local consumption in the hilly and mountainous area in not only Japan but also in the world. Herein, we would like to report the properties of the bio-oil generated by the developing Auger-type movable reactor. The synthesized bio-oil possessed C: 46.2 wt%, H: 6.5 wt%, N: wt%, S: <0.1 wt%, O: 46.8 wt% and H{sub 2}O: 18.4 wt%, and served a good calorific value of 18.1 MJ/kg. The spectroscopic and mass analyses such as FT-IR, GC-MS, {sup 13}C-NMR and FT-ICR MS supported that the bio-oil was composed by the fine mixtures of methoxy phenols and variety of alcohol or carboxylic acid functional groups. Thus, it is suggested that the bio-oil generated by the new movable Auger-type reactor has a significant potential as well as the existing bio-oil reported previously.

  9. Technical report: technical development on the silicide plate-type fuel experiment at nuclear safety research reactor

    International Nuclear Information System (INIS)

    Yanagisawa, Kazuaki; Soyama, Kazuhiko; Ichikawa, Hiroki

    1991-08-01

    According to a reduction of fuel enrichment from 45 w/o 235 U to 20 w/o, an aluminide plate-type fuel used currently in the domestic research and material testing reactors will be replaced by a silicide plate-type one. One of the major concern arisen from this alternation is to understand the fuel behavior under simulated reactivity initiated accident (RIA) conditions, this is strongly necessary from the safety and licensing point of view. The in-core RIA experiments are, therefore, carried out at Nuclear Safety Research Reactor (NSRR) in Japan Atomic Energy Research Institute (JAERI). The silicide plate-type fuel consisted of the ternary alloy of U-Al-Si as a meat with uranium density up to 4.8 g/cm 3 having thickness by 0.51 mm and the binary alloy of Al-3%Mg as a cladding by thickness of 0.38 mm. Comparison of the physical properties of this metallic plate fuel with the UO 2 -zircaloy fuel rod used conventionally in commercial light water reactors shows that the heat conductivity of the former is of the order of about 13 times greater than the latter, however the melting temperature is only one-half (1570degC). Prior to in-core RIA experiments, there were some difficulties lay in our technical path. This report summarized the technical achievements obtained through our four years work. (J.P.N.)

  10. CORRELACIÓN ENTRE INTELIGENCIAS MÚLTIPLES Y LOS ESTILOS DE APRENDIZAJE EN LOS ESTUDIANTES UNIVERSITARIOS DE UN CENTRO DE IDIOMAS ACREDITADO DE AREQUIPA, 2012

    OpenAIRE

    BORJA VIZCARRA, MARÍA DEL PILAR SOFIA

    2014-01-01

    OBJETIVO GENERAL OBJETIVO ESPECÍFICOS PLAN DE TRABAJO DENOMINACIÓN DE LA ACTIVIDAD INVENTARIO DE INTELIGENCIAS MÚLTIPLES Y ESTILOS DE APRENDIZAJE ACTIVIDADES PARA INTELIGENCIAS MÚLTIPLES ACTIVIDADES PARA ESTILOS DE APRENDIZAJE EVALUACIÓN

  11. Inteligencia emocional en dos centros de Primaria de Sevilla: un estudio sobre variables que influyen en la inteligencia emocional del alumnado

    OpenAIRE

    Caballero Baliño, Ana; Caballero Baliño, Francisca

    2017-01-01

    El objetivo principal de esta investigación es estudiar el desarrollo de la inteligencia emocional en la escuela, en función de distintas variables como el contexto, el estrés del profesorado, el uso del teatro en las aulas, la inteligencia emocional del profesorado, el sexo, el curso, el rendimiento académico y el uso de técnicas innovadoras en los centros educativos. La muestra para esta investigación se obtiene de dos centros educativos de la localidad de Utrera (Sevilla), perteneciendo...

  12. Rendimiento académico y autopercepción de inteligencias múltiples e inteligencia emocional en universitarios de primera generación

    OpenAIRE

    Barraza López, René; González A., Mauricio

    2016-01-01

    El objetivo del presente artículo fue determinar la relación entre la autopercepción de inteligencias múltiples e inteligencia emocional y el rendimiento académico alcanzado por 252 estudiantes de nivel universitario de diversas carreras de la Universidad Santo Tomás-La Serena, tras el primer año de educación universitaria. Los antecedentes teóricos y empíricos establecen que el rendimiento académico se asociaría a variables novedosas como: ser primer miembro familiar en iniciar estudios univ...

  13. Seismic analysis of a large pool-type LMR [liquid metal reactor

    International Nuclear Information System (INIS)

    Wang, C.Y.; Gvildys, J.

    1989-01-01

    This paper describes the seismic study of a 450-MWe liquid metal reactor (LMR) under 0.3-g SSE ground excitation. Two calculations were performed using the new design configuration. They deal with the seismic response of the reactor vessel, the guard vessel and support skirt, respectively. In both calculations, the stress and displacement fields at important locations of those components are investigated. Assessments are also made on the elastic and inelastic structural capabilities for other beyond-design basis seismic loads. Results of the reactor vessel analysis reveal that the maximum equivalent stress is only about half of the material yield stress. For the guard vessel and support skirt, the stress level is very small. Regarding the analysis if inelastic structural capability, solutions of the Newmark-Hall ductility modification method show that the reactor vessel can withstand seismics with ground ZPAs ranging from 1.015 to 1.31 g, which corresponds to 3.37 to 4.37 times the basic 0.3-g SSE. Thus, the reactor vessel and guard vessel are strong enough to resist seismic loads. 4 refs., 10 figs., 5 tabs

  14. Inteligencia Artificial y Neurología. (III Parte)

    OpenAIRE

    Mario Camacho Pinto

    1987-01-01

    De acuerdo con mi anuncio esta III Parte estaría constituida por los mecanismos cerebrales susceptibles de extrapolación tal como fueron enumerados por mí: control de input-output para realizar conductas, y de inteligencia y aprendizaje, de los cuales por razón de espacio sólo se publica la mitad en esta edición de Medicina. Se trata de una presentación esquemática, auncuando ahora encuentro quizás más atractivo el enfoque de J’urgen Ruech expuesto en el Capítulo Comunicación y Psiqu...

  15. Inteligencia emocional percibida y optimismo disposicional en estudiantes universitarios

    Directory of Open Access Journals (Sweden)

    Óscar ANADÓN REVUELTA

    2006-01-01

    Full Text Available En la presente investigación se analizan las relaciones entre inteligencia emocional percibida (IEP y el optimismo disposicional, en una muestra de alumnos (N=102 de segundo curso de Magisterio (especialidades de Educación Primaria y de Lengua Extranjera: Inglés de la Facultad de Educación de Zaragoza. Se utilizaron los siguientes instrumentos: la Trait Meta-Mood Scale (TMMS, para evaluar la IEP, y el Life Orientation Test (LOT-R, para medir el optimismo disposicional. Los resultados muestran una moderada intercorrelación entre el subfactor de reparación de la IE y el optimismo disposicional. Ello sugiere que las personas con mayor capacidad para reparar sus estados emocionales negativos poseen expectativas generalizadas más favorables acerca de las cosas que les suceden en la vida.

  16. Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Bodey, Isaac T [ORNL

    2014-05-01

    Turbulent flow coupled with heat transfer is investigated for a High Flux Isotope Reactor (HFIR) fuel plate. The Reynolds Averaged Navier-Stokes Models are used for fluid dynamics and the transfer of heat from a thermal nuclear fuel plate using the Multi-physics code COMSOL. Simulation outcomes are compared with experimental data from the Advanced Neutron Source Reactor Thermal Hydraulic Test Loop. The computational results for the High Flux Isotope Reactor core system provide a more physically accurate simulation of this system by modeling the turbulent flow field in conjunction with the diffusion of thermal energy within the solid and fluid phases of the model domain. Recommendations are made regarding Nusselt number correlations and material properties for future thermal hydraulic modeling efforts

  17. Quantitative determination of uranium distribution homogeneity in material test reactor (MTR) fuel type plates

    International Nuclear Information System (INIS)

    Ferrufino, F.B.J.; Durazzo, M.

    2010-01-01

    IPEN-CNEN/SP produces the fuel to supply its nuclear research reactor IEA-R1. The fuel is assembled from fuel plates containing a core of U 3 Si 2 -Al composite. A good homogeneity in the distribution of uranium in the core of the fuel plate is important from the standpoint of performance under irradiation. Considering the low power reactor IEA-R1, currently the distribution of uranium in the fuel plate is evaluated only by visual inspection of radiographs. However, in view of the possibility of IPEN manufacture the fuel for the new Brazilian Multipurpose Reactor, which has high power, it became urgent to develop a methodology to determine quantitatively the distribution of uranium into the fuel. This paper presents a methodology based on X-ray attenuation, quantifying the distribution of the uranium concentration in the core of the fuel plate by using optical densities of radiographs and comparison with standards. (author)

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  19. Analysis of radiation safety for Small Modular Reactor (SMR) on PWR-100 MWe type

    Science.gov (United States)

    Udiyani, P. M.; Husnayani, I.; Deswandri; Sunaryo, G. R.

    2018-02-01

    Indonesia as an archipelago country, including big, medium and small islands is suitable to construction of Small Medium/Modular reactors. Preliminary technology assessment on various SMR has been started, indeed the SMR is grouped into Light Water Reactor, Gas Cooled Reactor, and Solid Cooled Reactor and from its site it is group into Land Based reactor and Water Based Reactor. Fukushima accident made people doubt about the safety of Nuclear Power Plant (NPP), which impact on the public perception of the safety of nuclear power plants. The paper will describe the assessment of safety and radiation consequences on site for normal operation and Design Basis Accident postulation of SMR based on PWR-100 MWe in Bangka Island. Consequences of radiation for normal operation simulated for 3 units SMR. The source term was generated from an inventory by using ORIGEN-2 software and the consequence of routine calculated by PC-Cream and accident by PC Cosyma. The adopted methodology used was based on site-specific meteorological and spatial data. According to calculation by PC-CREAM 08 computer code, the highest individual dose in site area for adults is 5.34E-02 mSv/y in ESE direction within 1 km distance from stack. The result of calculation is that doses on public for normal operation below 1mSv/y. The calculation result from PC Cosyma, the highest individual dose is 1.92.E+00 mSv in ESE direction within 1km distance from stack. The total collective dose (all pathway) is 3.39E-01 manSv, with dominant supporting from cloud pathway. Results show that there are no evacuation countermeasure will be taken based on the regulation of emergency.

  20. 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

  1. A calculation methodology applied for fuel management in PWR type reactors using first order perturbation theory

    International Nuclear Information System (INIS)

    Rossini, M.R.

    1992-01-01

    An attempt has been made to obtain a strategy coherent with the available instruments and that could be implemented with future developments. A calculation methodology was developed for fuel reload in PWR reactors, which evolves cell calculation with the HAMMER-TECHNION code and neutronics calculation with the CITATION code.The management strategy adopted consists of fuel element position changing at the beginning of each reactor cycle in order to decrease the radial peak factor. The bi-dimensional, two group First Order perturbation theory was used for the mathematical modeling. (L.C.J.A.)

  2. Contribution to the study of the conversion PWR type reactors to the thorium cycle

    International Nuclear Information System (INIS)

    Martins Filho, J.R.

    1980-01-01

    The use of the thorium cycle in PWR reactors is discussed. The fuel has been calculated in the equilibrium condition for a economic comparison with the uranium cycle (in the same condition). First of all, a code named EQUILIBRIO has been developed for the fuel equilibrium calculation. The results gotten by this code, were introduced in the LEOPARD code for the fuel depletion calculation (in the equilibrium cycle). Same important physics details of fuel depletion are studied, for instance: the neutron balance, power sharing, fuel burnup, etc. The calculations have been done taking as reference the Angra-1 PWR reactor. (Author) [pt

  3. Design of an equilibrium nucleus of a BWR type reactor based in a Thorium-Uranium fuel

    International Nuclear Information System (INIS)

    Francois, J.L.; Nunez C, A.

    2003-01-01

    In this work the design of the reactor nucleus of boiling water using fuel of thorium-uranium is presented. Starting from an integral concept based in a type cover-seed assemble is carried out the design of an equilibrium reload for the nucleus of a reactor like that of the Laguna Verde Central and its are analyzed some of the main design variables like the cycle length, the reload fraction, the burnt fuel, the vacuum distribution, the generation of lineal heat, the margin of shutdown, as well as a first estimation of the fuel cost. The results show that it is feasible to obtain an equilibrium reload, comparable to those that are carried out in the Laguna Verde reactors, with a good behavior of those analyzed variables. The cost of the equilibrium reload designed with the thorium-uranium fuel is approximately 2% high that the uranium reload producing the same energy. It is concluded that it is convenient to include burnable poisons, type gadolinium, in the fuel with the end of improving the reload design, the fuel costs and the margin of shutdown. (Author)

  4. Conceptual analysis of a preliminary model for instability study in normal operation of a natural circulation reactor type EBWR, using Relap5/Mod 3.2

    International Nuclear Information System (INIS)

    Ojeda S, J.; Morales S, J.; Chavez M, C.

    2009-10-01

    This work intends a model using the code Relap5/Mod 3.2, for the instability study in normal operation of a natural circulation reactor type ESBWR. A conceptual analysis is considered because all the information was obtained of the open literature, and some of reactor operation or dimension (not available) parameters were approached. As starting point was took the pattern developed for reactor type BWR, denominated Browns Ferry and changes were focused in elimination of bonds of forced recirculation, in modification of operation parameters, dimensions and own control parameters, according to internal code structure. Additionally the nodalization outline is described analyzing for separate the four fundamental areas employees in peculiar geometry of natural circulation reactor. Comparative analysis of results of stability behavior obtained with those reported in the open literature were made, by part of commercial reactor designer ESBWR. (Author)

  5. Evaluation of LOCA in a swimming-pool type reactor using the 3D-AIRLOCA code

    International Nuclear Information System (INIS)

    Nagler, A.; Gilat, J.; Hirshfeld, H.

    1991-01-01

    The 3D-AIRLOCA code was used to calculate core temperature evolution curves in the wake of a full LOCA in a swimming pool type reactor, resulting in complete core exposure and dryout within about 1000 sec of the initiating event. The results show that fuel integrity loss thresholds (450 C for softening and 650 C for melting) are reached and exceeded over large fractions of the core at power levels as low as 2 MW. At 4.5 MW, the softening threshold is reached even when the accident occurs up to 12 hours after reactor shutdown for continuous operation, and up to 2 hrs after shutdown for intermittent (6 hrs/day, 4 days a week) operation. The situation is even more severe in blockage cases, when the air flow through the core is blocked by residual water at the grid plate level. It is concluded that substantial fission product releases are quite likely in this class of accidents. (orig.)

  6. Evaluation of LOCA in a swimming-pool type reactor using the 3D-AIRLOCA code

    International Nuclear Information System (INIS)

    Nagler, A.; Gilat, J.; Hirshfeld, H.

    1991-01-01

    The 3D-AIRLOCA code was used to calculate core temperature evolution curves in the wake of a full LOCA in a swimming pool type reactor, resulting in complete core exposure and dryout within about 1000 sec of the initiating event. The results show that fuel integrity loss thresholds (450 C for softening and 650 C for melting) are reached and exceeded over large fractions of the core at powr levels as low as 2 MW. At 4.5 MW, the softening threshold is reached even when the accident occurs up to 12 hours after reactor shutdown for continuous operation, and up to 2 hrs after shutdown for intermittent (6 hrs/day, 4 days a week) operation. The situation is even more severe in blockage cases, when the air flow through the core is blocked by residual water at the grid plate level. It is concluded that substantial fission product releases are quite likely in this class of accidents. (orig.)

  7. Vibration and acoustic noise emitted by dry-type air-core reactors under PWM voltage excitation

    Science.gov (United States)

    Li, Jingsong; Wang, Shanming; Hong, Jianfeng; Yang, Zhanlu; Jiang, Shengqian; Xia, Shichong

    2018-05-01

    According to coupling way between the magnetic field and the structural order, structure mode is discussed by engaging finite element (FE) method and both natural frequency and modal shape for a dry-type air-core reactor (DAR) are obtained in this paper. On the basis of harmonic response analysis, electromagnetic force under PWM (Pulse Width Modulation) voltage excitation is mapped with the structure mesh, the vibration spectrum is gained and the consequences represents that the whole structure vibration predominates in the radial direction, with less axial vibration. Referring to the test standard of reactor noise, the rules of emitted noise of the DAR are measured and analyzed at chosen switching frequency matches the sample resonant frequency and the methods of active vibration and noise reduction are put forward. Finally, the low acoustic noise emission of a prototype DAR is verified by measurement.

  8. Determination of neutron energy spectrum at a pneumatic rabbit station of a typical swimming pool type material test research reactor

    International Nuclear Information System (INIS)

    Malkawi, S.R.; Ahmad, N.

    2002-01-01

    The method of multiple foil activation was used to measure the neutron energy spectrum, experimentally, at a rabbit station of Pakistan Research Reactor-1 (PARR-1), which is a typical swimming pool type material test research reactor. The computer codes MSITER and SANDBP were used to adjust the spectrum. The pre-information required by the adjustment codes was obtained by modelling the core and its surroundings in three-dimensions by using the one dimensional transport theory code WIMS-D/4 and the multidimensional finite difference diffusion theory code CITATION. The input spectrum covariance information required by MSITER code was also calculated from the CITATION output. A comparison between calculated and adjusted spectra shows a good agreement

  9. Inteligencia emocional en estudiantes de la Universidad Nacional del Centro del Perú, 2013

    Directory of Open Access Journals (Sweden)

    Cesar Reyes Lujan

    2014-06-01

    Full Text Available Objetivos: Determinar los niveles de inteligencia emocional predominantes en los estudiantes de la Facultad de Enfermería de la Universidad Nacional del Centro del Perú en el año 2013. Método: Se empleó el método descriptivo prospectivo. Se evaluaron un total de 195 estudiantes de 16 a 30 años de edad en toda la facultad. Para la recolección de datos, se aplicó el inventario Emocional de BarOn y el inventario de coeficiente emocional (ICE que permitió conocer su inteligencia emocional. Resultados: Se determinó los niveles de inteligencia emocional general siendo la capacidad emocional “adecuada” o promedio en un 49% seguido de una capacidad emocional “por debajo del promedio” y “muy bajo” con el 36% y 11% respectivamente. En cuanto a los componentes, intrapersonal, presenta una capacidad emocional adecuada del 83%, siendo la más alta respecto a los demás componentes seguido del interpersonal 55%, y el estado de ánimo 54%, quienes presentaron inteligencia emocional adecuada o promedio, los estudiantes que alcanzaron una baja capacidad emocional por debajo del promedio fueron en los componentes de adaptabilidad 53%, en manejo de estrés 42%. En relación al sexo masculino en el componente interpersonal y manejo de estrés presenta un 56% y 39% por debajo del promedio; en mujeres en el componente adaptabilidad y manejo de estrés con 54% y 44% presentan capacidad emocional debajo del promedio. Conclusión: Los componentes de inteligencia emocional general, adaptabilidad y manejo de estrés, tienen niveles de riesgo y deberán ser mejorados al igual que la inteligencia emocional interpersonal en sexo masculino. No se encontraron diferencias significativas entre varones y mujeres en la inteligencia emocional general.

  10. Coupled neutronic core and subchannel analysis of nanofluids in VVER-1000 type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Zarifi, Ehsan; Sepanloo, Kamran [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor and Nuclear Safety School; Jahanfarnia, Golamreza [Islamic Azad Univ., Tehran (Iran, Islamic Republic of). Dept. of Nuclear Engineering, Science and Research Branch

    2017-05-15

    This study is aimed to perform the coupled thermal-hydraulic/neutronic analysis of nanofluids as the coolant in the hot fuel assembly of VVER-1000 reactor core. Water-based nanofluid containing various volume fractions of Al{sub 2}O{sub 3} nanoparticle is analyzed. WIMS and CITATION codes are used for neutronic simulation of the reactor core, calculating neutron flux and thermal power distribution. In the thermal-hydraulic modeling, the porous media approach is used to analyze the thermal behavior of the reactor core and the subchannel analysis is used to calculate the hottest fuel assembly thermal-hydraulic parameters. The derived conservation equations for coolant and conduction heat transfer equation for fuel and clad are discretized by Finite volume method and solved numerically using visual FORTRAN program. Finally the analysis results for nanofluids and pure water are compared together. The achieved results show that at low concentration (0.1 percent volume fraction) alumina is the optimum nanoparticles for normal reactor operation.

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

    International Nuclear Information System (INIS)

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

    2015-09-01

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

  12. Comparison of decay heat exchangers placing in the primary circuit of pool type fast reactor

    International Nuclear Information System (INIS)

    Birbraer, P.N.; Gorbunov, V.S.; Zotov, V.G.; Kuzavkov, N.G.; Pykhonin, V.A.; Sobolev, V.A.; Ryzhov, V.A.

    1993-01-01

    Description of two alternative arrangements of decay beat exchangers (DHXs) in the fast reactor tank is presented: in 'hot' cavity and in 'cold' cavity. The results of calculation for the two alternative arrangements as regards static and dynamic parameters in the primary circuit on 1-D program are given. (author)

  13. Evaluation of neutron streaming through injection ports in a tokamak-type fusion reactor

    International Nuclear Information System (INIS)

    Ide, Takahiro; Seki, Yasushi; Iida, Hiromasa

    1976-03-01

    The effects of neutron streaming through injection ports in the fusion reactor designed in JAERI have been studied, especially those on tritium breeding ratio and the shielding of the superconducting magnet. In placement of the injection ports in the blanket, the tritium breeding ratio decreases by up to 1.3%, and shielding problem of the superconducting magnet is very important. (auth.)

  14. Standardization of specifications and inspection procedures for LEU plate-type research reactor fuels

    International Nuclear Information System (INIS)

    1988-06-01

    With the transition to high density uranium LEU fuel, fabrication costs of research reactor fuel elements have a tendency to increase because of two reasons. First, the amount of the powder of the uranium compound required increases by more than a factor of five. Second, fabrication requirements are in many cases nearer the fabrication limits. Therefore, it is important that measures be undertaken to eliminate or reduce unnecessary requirements in the specification or inspection procedures of research reactor fuel elements utilizing LEU. An additional stimulus for standardizing specifications and inspection procedures at this time is provided by the fact that most LEU conversions will occur within a short time span, and that nearly all of them will require preparation of new specifications and inspection procedures. In this sense, the LEU conversions offer an opportunity for improving the rationality and efficiency of the fuel fabrication and inspection processes. This report focuses on the standardization of specifications and inspection processes of high uranium density LEU fuels for research reactors. However, in many cases the results can also be extended directly to other research reactor fuels. 15 refs, 1 fig., 3 tabs

  15. Modelling and simulation the radioactive source-term of fission products in PWR type reactors

    International Nuclear Information System (INIS)

    Porfirio, Rogilson Nazare da Silva

    1996-01-01

    The source-term was defined with the purpose the quantify all radioactive nuclides released the nuclear reactor in the case of accidents. Nowadays the source-term is limited to the coolant of the primary circuit of reactors and may be measured or modelled with computer coders such as the TFP developed in this work. The calculational process is based on the linear chain techniques used in the CINDER-2 code. The TFP code considers forms of fission products release from the fuel pellet: Recoil, Knockout and Migration. The release from the gap to the coolant fluid is determined from the ratio between activity measured in the coolant and calculated activity in the gap. Considered the operational data of SURRY-1 reactor, the TFP code was run to obtain the source=term of this reactor. From the measured activities it was verified the reliability level of the model and the employed computational logic. The accuracy of the calculated quantities were compared to the measured data was considered satisfactory. (author)

  16. Core characteristics on a hybrid type fast reactor system combined with proton accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Kowata, Yasuki; Otsubo, Akira [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1997-06-01

    In our study on a hybrid fast reactor system, we have investigated it from the view point of transmutation ability of trans-uranium (TRU) nuclide making the most effective use of special features (controllability, hard neutron spectrum) of the system. It is proved that a proton beam is superior in generation of neutrons compared with an electron beam. Therefore a proton accelerator using spallation reaction with a target nucleus has an advantage to transmutation of TRU than an electron one. A fast reactor is expected to primarily have a merit that the reactor can be operated for a long term without employment of highly enriched plutonium fuel by using external neutron source such as the proton accelerator. Namely, the system has a desirable characteristic of being possible to self-sustained fissile plutonium. Consequently in the present report, core characteristics of the system were roughly studied by analyses using 2D-BURN code. The possibility of self-sustained fuel was investigated from the burnup and neutronic calculation in a cylindrical core with 300w/cc of power density without considering a target material region for the accelerator. For a reference core of which the height and the radius are both 100 cm, there is a fair prospect that a long term reactor operation is possible with subsequent refueling of natural uranium, if the medium enriched (around 10wt%) uranium or plutonium fuels are fully loaded in the initial core. More precise analyses will be planed in a later fiscal year. (author)

  17. Modeling in fast dynamics of accidents in the primary circuit of PWR type reactors

    International Nuclear Information System (INIS)

    Robbe, M.F.

    2003-12-01

    Two kinds of accidents, liable to occur in the primary circuit of a Pressurized Water Reactor and involving fast dynamic phenomena, are analyzed. The Loss Of Coolant Accident (LOCA) is the accident used to define the current PWR. It consists in a large-size break located in a pipe of the primary circuit. A blowdown wave propagates through the circuit. The pressure differences between the different zones of the reactor induce high stresses in the structures of the lower head and may degrade the reactor core. The primary circuit starts emptying from the break opening. Pressure decreases very quickly, involving a large steaming. Two thermal-hydraulic simulations of the blowdown phase of a LOCA are computed with the Europlexus code. The primary circuit is represented by a pipe-model including the hydraulic peculiarities of the circuit. The main differences between both computations concern the kind of reactor, the break location and model, and the initialization of the accidental operation. Steam explosion is a hypothetical severe accident liable to happen after a core melting. The molten part of the core (called corium) falls in the lower part of the reactor. The interaction between the hot corium and the cold water remaining at the bottom of the vessel induces a massive and violent vaporization of water, similar to an explosive phenomenon. A shock wave propagates in the vessel. what can damage seriously the neighbouring structures or drill the vessel. This work presents a synthesis of in-vessel parametrical studies carried out with the Europlexus code, the linkage of the thermal-hydraulic code Mc3d dedicated to the pre-mixing phase with the Europlexus code dealing with the explosion, and finally a benchmark between the Cigalon and Europlexus codes relative to the Vulcano mock-up. (author)

  18. The reactor core TRIGA Mark-III with fuels type 30/20; El nucleo del reactor TRIGA Mark-III con combustible tipo 30/20

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F., E-mail: fortunato.aguilar@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2012-10-15

    This work describes the calculation series carried out with the program MCNP5 in order to define the configuration of the reactor core with fuels 30/20 (fuels with 30% of uranium content in the Or-Zr-H mixture and a nominal enrichment of 20%). To select the configuration of the reactor core more appropriate to the necessities and future uses of the reactor, the following criterions were taken into account: a) the excess in the reactor reactivity, b) the switch out margin and c) to have new irradiation facilities inside the reactor core. Taking into account these criterions is proceeded to know the characteristics of the components that form the reactor core (dimensions, geometry, materials, densities and positions), was elaborated a base model of the reactor core, for the MCNP5 code, with a configuration composed by 85 fuel elements, 4 control bars and the corresponding structural elements. The high reactivity excess obtained with this model, gave the rule to realize other models of the reactor core in which the reactivity excess and the switch out margin were approximate to the values established in the technical specifications of the reactor operation. Several models were realized until finding the satisfactory model; this is composite for 74 fuels, 4 control bars and 6 additional experimental positions inside the reactor core. (Author)

  19. Optimization activities on design studies of LHD-type reactor FFHR

    Energy Technology Data Exchange (ETDEWEB)

    Sagara, A.; Kobayashi, M. [National Inst. for Fusion Science, Gifu (Japan); Mitarai, O. [Kyushyu Tokai Univ., Kumamoto (JP)] (and others)

    2007-07-01

    An overview of recent activities on optimizing the base design of LHD-type helical power reactor FFHR is presented, including key design improvements on blanket and divertor configurations, neutronics performance, large superconducting coils and cost models. New proposals of plasma operation candidates are also shown. In the reference design FFHR2m1 with the major radius R of 14 m, one of the main issues is the structural compatibility between blanket and divertor configurations. In particular, the blanket space at the inboard side is still insufficient due to the interference between the first walls and the ergodic layers surrounding the last closed flux surface. To overcome this problem, helical x-point divertor (HXD) has been proposed to remove the interference. In this concept, very effective screening of recycling neutrals with 99% ionization is expected according to 3D simulations. Another approach for obtaining larger clearance is also being examined by modifying the configurations of the helical coils. Neutronics performances on liquid breeder blanket have been also improved with optimizing the neutron multiplier to achieve the local TBR over 1.3 and a sufficient shielding efficiency of the fast neutron fluence of lower than 10{sup 22} n/m{sup 2} in 30 years. This issue on the blanket configurations also includes the issue on net cover rate of the inner wall for the total TBR over 1.2. For this requirement, the discrete pumping with semi-closed shield (DPSS) is proposed to achieve the net cover rate of over 0.9, which is very advantageous to suppress nuclear streaming. The other key issues are the engineering aspects on large superconducting coils. Poloidal coils positions are optimized to be compatible with 3D configurations of blankets within an acceptable total magnetic energy. Promising candidates of R and W (react and winding) of CICC (cable in conduit conductor), indirect cooling magnets with external dumping for quenching, and the LHD-type support

  20. Problems of underclad type defects in reactor pressure vessel integrity evaluation

    International Nuclear Information System (INIS)

    Lauerova, D.; Brumovsky, M.; Simpanen, P.; Kohopaa, J.

    2003-01-01

    Experiments were performed on specimens with a test section of 70x100 mm. The specimens were manufactured from reactor pressure vessel of WWER-440/V-213 type materials, i.e. from base metal and/or weld metal. One half of the specimens were unclad, containing a through or semi-elliptical crack, and the second half of specimens contained an underclad crack, again of the through or semi-elliptical type. The materials were tested both as received and in the aged condition, the latter representing the RPV end-of-life state. FE analyses showed that the evaluation of experiments with underclad cracks meets with nonstandard problems, compared to the evaluation of unclad specimens with surface cracks. The following experiences were gained from the evaluations: Experimental records of cladded specimens contain pop-ins and 'change in slopes' in the linear parts of the load vs. strain curves. The pop-ins are assumed to be associated with crack propagation (and arrest). As far as the 'changes in slopes' are concerned, these might be a consequence of of a deformation band arising on the cladding surface, in combination with the eccentric location of the strain gauge on the cladding surface. It was also shown that the effect of residual stresses can be simulated as an effect of stress-free temperature, using different volume deformations of the cladding and base/weld metal that correspond to cooling down from the stress-free temperature to the test temperature. The pop-in study revealed that numerical simulations of the crack growth on their own do not allow us to decide where the crack propagated during the pop-in, whether into the cladding or into the base/weld metal. For a more effective evaluation of the experiments with underclad cracks, additional information from experiments is needed, primarily including a more sophisticated experimental set-up or more sophisticated control of the experiments. During the evaluation of the experiments with underclad cracks, problems with

  1. Study on characteristics for different moderation ratios of heavy water coolant with different reactor types in equilibrium states

    International Nuclear Information System (INIS)

    Permana, Sidik; Takaki, Naoyuki; Sekimoto, Hiroshi

    2005-01-01

    Several characteristics for different moderation ratios of heavy water coolant with different reactor types in equilibrium states have been investigated. Performances of PWR and CANDU reactors are compared. A calculation method for determining the required uranium enrichment for criticality of the systems has been developed by coupling the equilibrium fuel cycle burn-up calculation and cell calculation of PIJ module of SRAC2000 code. In the present study, we have compared the characteristics for different moderator to fuel ratio (MFR, 0.1 to 30), different burn-up for CANDU type and four fuels cycle schemes. Nuclide density of 235 U at MFR=1.9 decreases with increasing number of confined HM, while 235 U at higher MFR has the opposite trend. However, the nuclide density of fissile material at higher MFR is lower except 238 U. CANDU type requires lower uranium enrichment and obtains higher conversion ratio than PWR type. Lowest burn-up requires the lowest uranium enrichment and obtains the highest conversion ratio. The breeding condition can be obtained for plutonium recycle cases at MFR=2.1 of Case 4 and MFR=1.4 of Case 3. The natural uranium can be achieved at MFR=14 of plutonium recycle cases, and it can be used easier by increasing number of confined HM. (author)

  2. Creatividad e Inteligencias Múltiples según el género en alumnado de Educación Primaria

    Directory of Open Access Journals (Sweden)

    María Pilar Garín-Vallverdú

    2016-02-01

    Full Text Available Los primeros años de escolarización son fundamentales para potenciar el desarrollo de la creatividad y las inteligencias múltiples. Bajo el sustento de los marcos teóricos de referencia que explican ambas variables, el objetivo del estudio fue analizar las diferencias significativas existentes en la creatividad y las inteligencias múltiples entre niños y niñas de 1º de Educación primaria. La muestra se compuso de 60 estudiantes (chicos=31; chicas=29 de 6 y 7 años escolarizados en un centro público de Zaragoza. Los instrumentos utilizados fueron el Cuestionario del profesorado para diagnosticar Inteligencias Múltiples en Primaria y el Test de Pensamiento Creativo de Torrance. Los resultados mostraron diferencias significativas en la creatividad, siendo las chicas quienes obtuvieron mayores puntuaciones. Respecto a las inteligencias múltiples, la inteligencia interpersonal fue la que mayores puntuaciones obtuvo en ambos géneros. Paralelamente, la inteligencia musical fue la de menor puntuación en ambos géneros, siendo la única que mostró diferencias significativas. Estos hallazgos se discuten argumentando la necesidad de realizar un programa de intervención que potencie la creatividad y la inteligencia musical en ambos géneros a través del resto de inteligencias, significando un aprendizaje transversal que optimice la formación del alumnado de manera íntegra.

  3. La Cultura de la Inteligencia desde la Perspectiva de la Investigación Histórica

    OpenAIRE

    Goberna Falque, Juan

    2006-01-01

    Desde las más altas instancias del Centro Nacional de Inteligencia (CNI) se viene proponiendo desde hace algunos años la creación y difusión de algo que se ha dado en llamar la «cultura de la inteligencia». Como miembro de un equipo de investigaci

  4. SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Evans, D.J.R.; Downs, W.E.

    1974-01-01

    The SLOWPOKE reactor is described, which is a small pool type with thermal neutron fluxes ranging from 10 11 -10 12 n cm -2 sec -1 . It differs in many ways from conventional pool type, namely small critical mass, beryllium reflector and a closed reactor container. The reactor is designed as small and simply as possible, and consistently with safety and good operating practice. Access to the present model is via pneumatic irradiation tubes only, which limits the use of the facility to activation analysis, tracer production and training. (Mori, K.)

  5. A novel water perm-selective membrane dual-type reactor concept for Fischer-Tropsch synthesis of GTL (gas to liquid) technology

    International Nuclear Information System (INIS)

    Rahimpour, M.R.; Mirvakili, A.; Paymooni, K.

    2011-01-01

    The present study proposes a novel configuration of Fischer-Tropsch synthesis (FTS) reactors in which a fixed-bed water perm-selective membrane reactor is followed by a fluidized-bed hydrogen perm-selective membrane reactor. This novel concept which has been named fixed-bed membrane reactor followed by fluidized-bed membrane reactor (FMFMDR) produces gasoline from synthesis gas. The walls of the tubes of a fixed-bed reactor (water-cooled reactor) of FMFMDR configuration are coated by a high water perm-selective membrane layer. In this new configuration, two membrane reactors instead of one membrane reactor are developed for FTS reactions. In other words, two different membrane layers are used. In order to investigate the performance of FMFMDR, a one-dimensional heterogeneous model is taken into consideration. The simulation results of three schemes named fluidized-bed membrane dual-type reactor (FMDR), FMFMDR and conventional fixed-bed reactor (CR) are presented. They have been compared in terms of temperature, gasoline and CO 2 yields, H 2 and CO conversions and the water permeation rate through the membrane layer. Results show that the gasoline yield in FMFMDR is higher than the one in FMDR. The FMFMDR configuration not only decreases the undesired product such as CO 2 but also produces more gasoline. -- Research highlights: → The application of H-SOD membrane layer in FTS reactors. → Approximate 7.5% and 37% increase in the gasoline yield in terms of [g/g feed x 100] in comparison with FMDR and CR, respectively. → A remarkable decrease in CO 2 emission to the environment. → A good configuration mainly due to reduction in catalysts sintering as a result of in situ water removal.

  6. Safety related investigations of the VVER-1000 reactor type by the coupled code system TRACE/PARCS

    International Nuclear Information System (INIS)

    Jaeger, Wadim; Lischke, Wolfgang; Sanchez Espinoza, Victor Hugo

    2007-01-01

    This study was performed at the Institute of Reactor Safety at the Research Center Karlsruhe. It is embedded in the ongoing investigations of the international code application and maintenance program (CAMP) for qualification and validation of system codes like TRACE [1] and PARCS [2]. The predestinated reactor type for the validation of these two codes was the Russian designed VVER-1000 because the OECD/NEA VVER-1000 Coolant Transient Benchmark Phase 2 [3] includes detailed information of the Bulgarian nuclear power plant (NPP) Kozloduy unit 6. The posttest-investigations of a coolant mixing experiment have shown that the predicted parameters (coolant temperature, pressure drop, etc.) are in good agreement to the measured data. The coolant mixing pattern especially in the downcomer has been also reproduced quiet well by TRACE. The coupled code system TRACE/PARCS which was applied on a postulated main steam line break (MSLB) provides good results compared to reference values and the ones of other participants of the benchmark. It can be pointed out that the developed three-dimensional nodalisation of the reactor pressure vessel (RPV) is appropriate for the description of transients where the thermal-hydraulics and the neutronics are strongly linked. (author)

  7. Theoretical and Experimental Evaluation of the Temperature Distribution in a Dry Type Air Core Smoothing Reactor of HVDC Station

    Directory of Open Access Journals (Sweden)

    Yu Wang

    2017-05-01

    Full Text Available The outdoor ultra-high voltage (UHV dry-type air-core smoothing reactors (DASR of High Voltage Direct Current systems are equipped with a rain cover and an acoustic enclosure. To study the convective heat transfer between the DASR and the surrounding air, this paper presents a coupled model of the temperature and fluid field based on the structural features and cooling manner. The resistive losses of encapsulations calculated by finite element method (FEM were used as heat sources in the thermal analysis. The steady fluid and thermal field of the 3-D reactor model were solved by the finite volume method (FVM, and the temperature distribution characteristics of the reactor were obtained. Subsequently, the axial and radial temperature distributions of encapsulation were investigated separately. Finally, an optical fiber temperature measurement scheme was used for an UHV DASR under natural convection conditions. Comparative analysis showed that the simulation results are in good agreement with the experimental data, which verifies the rationality and accuracy of the numerical calculation. These results can serve as a reference for the optimal design and maintenance of UHV DASRs.

  8. Measurement of flow field in the pebble bed type high temperature gas-cooled reactor

    International Nuclear Information System (INIS)

    Lee, Sa Ya; Lee, Jae Young

    2008-01-01

    In this study, flow field measurement of the Pebble Bed Reactor(PBR) for the High Temperature Gascooled Reactor(HTGR) was performed. Large number of pebbles in the core of PBR provides complicated flow channel. Due to the complicated geometries, numerical analysis has been intensively made rather than experimental observation. However, the justification of computational simulation by the experimental study is crucial to develop solid analysis of design method. In the present study, a wind tunnel installed with pebbles stacked was constructed and equipped with the Particle Image Velocimetry(PIV). We designed the system scaled up to realize the room temperature condition according to the similarity. The PIV observation gave us stagnation points, low speed region so that the suspected high temperature region can be identified. With the further supplementary experimental works, the present system may produce valuable data to justify the Computational Fluid Dynamics(CFD) simulation method

  9. Life time of nuclear power plants and new types of reactors

    International Nuclear Information System (INIS)

    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.)

  10. Inteligencia emocional y rendimiento académico en estudiantes universitarios

    Directory of Open Access Journals (Sweden)

    Martha Luz Páez Cala

    2015-01-01

    Full Text Available El estudio tuvo como objetivo describir la inteligencia emocional y determinar su relación con el rendimiento académico en estudiantes universitarios. Participaron 263 estudiantes, a quienes se les aplicaron diversos instrumentos, entre ellos el cuestionario EQ -i de Bar O n para medir la inteligencia emocional. Se encontró un cociente de inteligencia emocional promedio de 46,51, sin diferencias según género, pero sí para cada programa: 62,9 para Economía; 55,69 en Medicina; 54,28 en Psicología y 36,58 para Derecho. Se encontró correlación entre el valor de IE y nota promedio hasta el momento (p = .019, mayor para Medicina (p = .001, seguido de Psicología (p = .066; no se encontró relación en los otros programas. Se presenta un modelo de dependencia cúbica entre coeficiente de inteligencia emocional y rendimiento académico significativo para el total de la población de Medicina y Psicología. Así mismo se encontró dependencia significativa de este coeficiente con programa (p = .000 y semestre (p = .000, aunque esta última presenta tendencia clara solo para Medicina. Los resultados coinciden con los de otros estudios que encuentran correlación entre inteligencia emocional y rendimiento académico.

  11. Heat transfer burnout in tube-type fuel elements of nuclear power reactors

    International Nuclear Information System (INIS)

    Subbotin, V.; Alexeev, G.; Peskov, O.; Sapankevic, A.

    1976-01-01

    The conditions are formulated under which the results of the experimental research of the boilino. water heat transfer burnout carried out on models may be applied to fuel elements of nuclear reactors. Experimental material providing data on the heat transfer burnout was expanded by the results of measurements of the uneven (cosine) longitudinal distribution of heat sources. The results of the effects of helical fins or wires on heat transfer burnout are presented. (F.M.)

  12. DRUCK - a programme for the calculation of the dynamic behaviour of FDR-type reactors

    International Nuclear Information System (INIS)

    Fiebig, R.

    1975-01-01

    The programme DRUCK calculates the dynamic behaviour of advanced pressurized-water reactors with the aid of a model for time-lag-linked channels. With this programme the process of discharging the pressure vessel and pressure changes between 200 and 2 at can be calculated. Reactivity feedback of the point model core is done with quasi-stationary equations which, by means of suitable interpolation formulas, have very wide validity. (orig./AK) [de

  13. Observation of inner surface of flame-tower type reactor for uranium conversion

    International Nuclear Information System (INIS)

    Amamoto, Ippei; Terai, Takayuki; Umetsu, Hiroshi

    2003-01-01

    A fluorination reactor, which has been used to convert uranium tetrafluoride (UF 4 ) into uranium hexafluoride (UF 6 ), was completed after approximately 6000 hours operation at the uranium conversion facility in Japan. The observation of its inner surface was carried out to understand its corrosive condition and mechanism. The main wall of the reactor is made of Monel Alloy and its operational temperature is approximately 450degC at external surface under gaseous fluorine atmosphere. A sampling was undertaken from the most corrosive part of the reactor wall, and its analysis was carried out to obtain the data for the condition of appearance, thickness, macro and micro structure, etc. The results of observation are as follows: (1) The thickness decreased evenly (average 3.9 mm/year); (2) The chemical composition of corrosive products as coating was mainly nickel fluoride (NiF 2 ), which suggested that the corrosion mechanism could have been caused by the high temperature gas corrosion; (3) The total amount of coating was lower than that of a loss in thickness. For some reason, some of coating would seem to become extinct on the surface of the wall. The deterioration of coating, which formed a protector on the wall due to excess heating of the wall, the sand erosion effect by UF 4 , etc. have contributed to this state of condition. (author)

  14. Preliminary assessment of an S.G.H.W. type research reactor

    International Nuclear Information System (INIS)

    Bicevskis, A.; Chapman, A.G.; Hesse, E.W.

    1970-08-01

    A preliminary design study has been made of a research reactor, based on the enriched S.G.H.W.R. concept, to be used for power reactor fuel irradiation, isotope production, basic research, and training in nuclear technology. A reactor physics assessment established a core size which would allow uninterrupted operation for the required irradiation period consistent with low capital and operating costs. A design was selected with 24 channels, a D 2 O calandria diameter of 2.7 m and an overall core height of 4.0 m. The capital cost was estimated as $750,000 for the fuel and $1,600,000 for the moderator, the refuelling cost being $340,000 per annum. A thermal design study showed that the fission heat of 65 MW could be transmitted to pressurised light water at 200 lb/in 2 abs. and rejected to sea water in two conventional U-tube heat exchangers. The basic design is flexible and can be adapted to meet many special requirements. (author)

  15. Studies on a stellarator reactor of the Helias type: The power balance

    International Nuclear Information System (INIS)

    Beidler, C.D.; Harmeyer, E.; Kisslinger, J.; Ott, I.; Rau, F.; Wobig, H.

    1993-06-01

    The power balance of a Helias reactor is analysed using empirical scaling laws which describe current stellarator experiments. Since neoclassical transport in Helias configurations is not prohibitive to ignition, anomalous transport determines the parameters of the ignited state. In the following study the plasma profiles are taken as given and the power balance with an external heating power is evaluated numerically. Three empirical scaling laws, LHD-scaling, Gyro-Bohm scaling and Lackner-Gottardi scaling are extrapolated to reactor parameters. Present experiments (Wendelstein 7-AS, ATF, Heliotron E and CHS) can be described by these scaling laws, in Wendelstein 7-AS preference is given to the Lackner-Gottardi scaling since confinement improves with increasing rotational transform. LHD scaling and Gyro-Bohm scaling do not satisfy the ignition conditions; an improvement of confinement is necessary. However, Lackner-Gottardi scaling meets the ignition condition and the operating window of the Helias reactor was found in the following regime: Major radius 20 m, average plasma radius 1.6 m, magnetic field 5 T, density n(0)=3-4x10 20 m -3 and temperature T(0)∼15-17 keV. The fusion output power is 2.5-3.0 GW and the average value of β=4-5%. This lies within the MHD-stability limits of a Helias configuration. The effects of various parameter variations on the power balance (isotope effect, α-particle content, major radius, magnetic field) are also investigated. (orig.)

  16. CARBONACEOUS, NITROGENOUS AND PHOSPHORUS MATTERS REMOVAL FROM DOMESTIC WASTEWATER BY AN ACTIVATED SLUDGE REACTOR OF NITRIFICATION-DENITRIFICATION TYPE

    Directory of Open Access Journals (Sweden)

    MOHAMAD ALI FULAZZAKY

    2009-03-01

    Full Text Available This paper proposes an environmental engineering method based on biotechnology approach as one of the expected solutions that should be considered to implementing the activated sludge for improving the quality of water and living environment, especially to remove the major pollutant elements of domestic wastewater. Elimination of 3 major pollutant elements, i.e., carbon, nitrogen and phosphor containing the domestic wastewater is proposed to carry out biological method of an anoxic-aerobic reactor therein these types of pollutants should be consecutively processed in three steps. Firstly, eliminate the carbonaceous matter in the aerobic reactor. Secondly, to remove the carbonaceous and nitrogenous matters, it is necessary to modify the reactor’s nature from the aerobic condition to an anoxic-aerobic reactor. And finally, when the cycle of nitrification-denitrification is stable to achieve the target’s efficiency of reactor by adding the ferric iron into the activated sludge, it can be continued to remove the carbonaceous, nitrogenous and phosphorous matters simultaneously. The efficiency of carbonaceous and nitrogenous matters removal was confirmed with the effluent standard, COD is less than 100 mgO2/L and the value of global nitrogen is less than 10 mgN/L. The effectiveness of suspended matter removal is higher than 90% and the decantation of activated sludge is very good as identifying the Molhman’s index is below of 120 mL/L. The total phosphorus matter removal is more effective than the soluble phosphorus matter. By maintaining the reactor’s nature at the suitable condition, identifying the range of pH between 6.92 and 7.16 therefore the excellent abatement of phosphor of about 80% is achieving with the molar Fe/P ratio of 1.4.

  17. Study on the Modeling Method for Computational Fluid Dynamics to Predict Coolant Flow Behavior in a Tank-in-pool Type Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong Hark; Chae, Hee Taek; Park, Cheol; Kim, Heon Il; Lee, Doo Jeong; Seo, Kyoung Woo; Oh, Jae Min; Yoon, Ju Hyeon; Ha, Jae Joo

    2009-08-15

    This is a study on the modeling method for computational fluid dynamics (CFD) to analyze and to predict primary coolant flow behavior in a tank-in-pool type research reactor at the conceptual design stage. It is very hard to conduct a CFD analysis on an enormous complex equipment integrated system like a nuclear reactor with no simplification and alternative model treatment, so it is required a new methodological approach to be adopted to such an enormous CFD model. In this study it is proposed a new modeling method to solve a nuclear reactor employing plate type nuclear fuel assemblies. The idea attributes fuel assembly modeling to simplification, but the effect and the influence to a flow by fuel assembly can be reproduced as close as possible to physical phenomena. The idea is applied to CFD analysis model for a tank-in-pool type research reactor. A careful evaluation of the CFD analysis result is carried out whether the CFD model can provide a reasonable prediction or not. According to the evaluation it can be said that the proposed modeling method is so useful idea for the CFD analysis model to solve the whole nuclear reactor. The CFD result provides valuable predictions to the flow phenomena in the tank-in-pool type research reactor, which contributes to the more understanding of flow characteristics of primary coolant flow in the reactor. It is shown by the CFD analysis that the reactor core would have even flow distribution within {+-}3% deviation to the design flow rate, and that the primary coolant of PCHT(Primary Coolant Hold-up Tank) would flow out to reactor pool via the NC flow gates. The outstanding grasping of the flow in the PCHT leads to a remedy to reduce the flowing out from the NC flow gates.

  18. Leak-before-break concept for evaluation of flows detected in pressure tubes in a Candu type reactor

    International Nuclear Information System (INIS)

    Crespi, J.C.

    1992-01-01

    This paper reviews the role of the Leak-Before-Break concept for evaluation of flaws detected in cold-worked Zr 2.5% Nb pressure tubes in a CANDU type reactors. The acceptance criteria are intended to prevent failure by brittle fracture, plastic collapse of the ligament and delayed hydride cracking. The methodology developed here was of great help in order to establish the operative conditions for fuel channel garter springs repositioning by means of the SLA Rette tool at Embalse Nuclear Generating Station, Cordoba, Argentina. (author)

  19. Recovery of enriched Uranium (20% U-235) from wastes obtained in the preparation of fuel elements for argonaut type reactors

    Energy Technology Data Exchange (ETDEWEB)

    Uriarte, A.; Ramos, L.; Estrada, J.; Val, J. L. del

    1962-07-01

    Results obtained with the two following installations for recovering enriched uranium (20% U-235) from wastes obtained in the preparation of fuel elements for Argonaut type reactors are presented. Ion exchange unit to recover uranium form mother liquors resulting from the precipitation ammonium diuranate (ADU) from UO{sub 2}F{sub 2} solutions. Uranium recovery unit from solid wastes from the process of manufacture of fuel elements, consisting of a) waste dissolution, and b) extraction with 10% (v/v) TBP. (Author) 9 refs.

  20. Quality verification for plate-type uranium-aluminum fuel elements for use in research reactors (Revision 1) - July 1976

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Paragraph (a) (7) of 50.34, Contents of Applications: Technical Information, of 10 CFR Part 50, Licensing of Production and Utilization Facilities, requires that each applicant for a construction permit to build a production or utilization facility include in its Preliminary Safety Analysis Report (PSAR) a description of the quality assurance program to be applied to the design, fabrication, construction, and testing of the structures, systems, and components of the facility. The Regulatory Guide presented describes a method acceptable to the NRC staff for establishing and executing a quality assurance program for verifying the quality of plate-type uranium-aluminum fuel elements used in research reactors

  1. Technical update on pressure suppression type containments in use in U.S. light water reactor nuclear power plants

    International Nuclear Information System (INIS)

    1978-07-01

    In 1972, Dr. S. H. Hanauer (Technical Advisor to the NRC's Executive Director for Operations) wrote a memorandum that raised several questions on the viability of pressure suppression containment concepts. The concerns raised by Dr. Hanauer have recently become the subject of considerable discussion by several members of the U.S. Congress and public. The report provides a response to these expressed concerns and a status summary for various technical matters that relate to the safety of pressure suppression type containments for light water cooled reactor plants

  2. Inteligencia Artificial y Neurología. (III Parte

    Directory of Open Access Journals (Sweden)

    Mario Camacho Pinto

    1987-04-01

    Full Text Available

    De acuerdo con mi anuncio esta III Parte estaría constituida por los mecanismos cerebrales susceptibles de extrapolación tal como fueron enumerados por mí: control de input-output para realizar conductas, y de inteligencia y aprendizaje, de los cuales por razón de espacio sólo se publica la mitad en esta edición de Medicina. Se trata de una presentación esquemática, auncuando ahora encuentro quizás más atractivo el enfoque de J’urgen Ruech expuesto en el Capítulo Comunicación y Psiquiatría de la obra extensa de Freedman (1 así: Input = percepción; análisis de datos = reconocimiento; procesamiento de datos = pensamiento; almacenamiento de datos = memoria; output = expresión y acción. A mi modo de ver se completaría este encuadre funcional con el tópico aprendizaje, proceso contiguo al de la memoria. Antes de entrar en materia hago unas consideraciones preliminares. En la primera me refiero a otro enfoque del concepto de LA. no incluido anteriormente. Se trata de Schank Roger y Hunter Larry (2 para quienes las indagaciones a que conduce el trasegar acerca de lA son las más atrevidas de nuestra existencia: ¿cuál es la naturaleza de la mente, qué pasa cuando estamos pensando, sintiendo, viendo o entendiendo? ¿Es posible comprender cómo trabaja nuestra mente realmente? Preguntas milenarias en cuyas respuestas no se ha registrado progreso. La lA ofrece una nueva herramienta para avanzar en este sentido: el computador.

    Las teorías sobre la mente han consistido en procesos descriptivos. Y los planteamientos iníciales hechos sobre lA por los investigadores han sido enfocados hacia lo que ellos mismos consideraron como manifestaciones de alta inteligencia: problemas matemáticos, ajedrez, rompecabezas complejos, etc.; gran cantidad de energía fue dedicada y se encontraron técnicas computacionales exitosas. Pero se comprendió que las técnicas desarrolladas no eran las mismas que emplea el cerebro, por lo cual se

  3. Conocimiento que Poseen los Docentes de Matemática sobre Inteligencia Emocional

    Directory of Open Access Journals (Sweden)

    Emmar Márquez Noguera

    2015-12-01

    Full Text Available Los docentes deben desarrollar su inteligencia emocional en cuanto al control de las emociones, el autoconocimiento, empatía, relaciones interpersonales, entre otros aspectos que le permiten desenvolverse en la vida diaria de la institución donde labora. Sobre tal consideración se elabora esta investigación con el objetivo de Identificar los conocimientos que poseen los docentes de matemática del Liceo Militar Oficial Bolivariano 4 de Agosto sobre inteligencia emocional. Para su logro se realizó un trabajo de campo, descriptivo, en un paradigma cualitativo, las técnicas seleccionadas fueron la entrevista y la observación participativa, los sujetos de estudio son los cuatro (04 docentes de matemática del liceo antes mencionado. El  proceso investigativo, dio como resultado que en los docentes hay debilidades respecto a las competencias referidas a la inteligencia emocional.

  4. Compromiso e inteligencia emocional en mediadores del Poder Judicial de Oaxaca, México

    Directory of Open Access Journals (Sweden)

    Carmen María Salvador Ferrer

    2010-01-01

    Full Text Available Este trabajo es un estudio transversal descriptivo, cuyo interés es conocer el papel que desempeñan el compromiso organizacional y la inteligencia emocional en la labor de los mediadores mexicanos. Para tal finalidad, se utilizó una muestra de 38 mediadores del Poder Judicial de Oaxaca. Además, para realizar el análisis de la situación, a través de ecuaciones estructurales, nos centraremos en el estudio de diferentes constructos, tales como: el compromiso, la inteligencia emocional, el sexo y la edad. Así, los resultados de esta investigación indican el impacto que estas variables tienen en el comportamiento del mediador. Además, encontramos que, según la edad y el sexo de los participantes, existen notables diferencias en los componentes del compromiso e inteligencia emocional.

  5. Capacidad predictiva del apoyo social en la inteligencia emocional de adolescentes

    Directory of Open Access Journals (Sweden)

    Lorea Azpiazu

    2015-06-01

    Full Text Available El objetivo de este estudio es analizar la relación entre el apoyo social (familiar, amistades y profesorado y la inteligencia emocional (atención, claridad y reparación. La muestra está compuesta por 1543 adolescentes, 728 chicos (47.18% y 815 chicas (52.81%, entre los 11 y 18 años (Medad = 14.24, DT = 1.63. Los análisis estadísticos se llevan a cabo con el programa SPSS 21 para Windows. Los resultados del análisis correlacional señalan que el apoyo social y la inteligencia emocional están significativamente relacionados en ambos sexos. Por otro lado, el análisis de regresión demuestra la capacidad predictiva de los diferentes apoyos en la inteligencia emocional tanto en la muestra masculina como en la femenina.

  6. Analysis of two different types of hydrogen combustion during severe accidents in a typical pressurized water reactor

    International Nuclear Information System (INIS)

    Ko Yuchih; Lee Min

    2005-01-01

    Hydrogen combustion is an important phenomenon that may occur during severe accidents of Nuclear Power Plants (NPPs). Depending on the specific plant design, the initiating events, and mitigation actions executed, hydrogen combustion may have distinct characteristics and may damage the plant in various degrees. The worst scenario will be the catastrophic failure of containment. In this study two specific types of hydrogen combustion are analyzed to evaluate their impact on the containment integrity. In this paper, Station Blackout (SBO) and Loss of Coolant Accidents (LOCAs) sequences are analyzed using MAAP4 (Modular Accident Analysis Program) code. The former sequence is used to represent hydrogen combustion phenomenon under the condition that the reactor pressure vessel (RPV) breaches at high pressure and the latter sequence represents the phenomenon that RPV fails at low pressure. Two types of hydrogen combustion are observed in the simulation. The Type I hydrogen combustion represents global and instantaneous hydrogen combustion. Large pressure spike is created during the combustion and represents a threat to containment integrity. Type II hydrogen combustion is localized burn and burn continuously over a time period. There is hardly any impact of this type hydrogen burn on the containment pressurization rate. Both types of hydrogen combustion can occur in the severe accidents without any human intervention. From the accident mitigation point of view, operators should try to bring the containment into conditions that favor the Type II hydrogen combustion. (authors)

  7. Cryogenic aspects of a demountable toroidal field magnet system for tokamak type fusion reactors

    International Nuclear Information System (INIS)

    Hsieh, S.Y.; Powell, J.; Lehner, J.

    1977-01-01

    A new concept for superconducting Toroidal Field (TF) magnet construction is presented. It is termed the ''Demountable Externally Anchored Low Stress'' (DEALS) magnet system. In contrast to continuous wound conventional superconducting coils, each magnet coil is made from several straight coil segments to form a polygon which can be joined and disjoined to improve reactor maintenance accessibility or to replace failed coil segments if necessary. A design example is presented of a DEALS magnet system for a UWMAK II size reactor. The overall magnet system is described, followed by a detailed analysis of the major heat loads in order to assess the refrigeration requirements for the concept. Despite the increased heat loads caused by high current power leads (200,000 amps) and the coil warm reinforcement support system, the analysis shows that at most, only about one percent (approximately 20 Mw) of the plant electrical output (approximately 2,000 Mw) is needed to operate the magnet cryogenic system. The advantages and the drawbacks of the DEALS magnet system are also discussed. The advantages include: capability to replace failed coils, increased accessibility to the blanket shield assembly, reduced reliability requirements for the magnet, much lower stress in conductor, easier application of improved high field brittle superconductors like Nb 3 Sn, improved magnet safety features, etc. The drawbacks are the increased refrigeration requirements and the necessity of a movable coil support system. A comparison with a conventional magnet system is made. It is concluded that the benefits of the DEALS approach far outweigh its penalties, and that the DEALS concept is the most practical, economical way to construct TF magnet systems for Tokamak reactors

  8. Sensitivity analysis on hot channel of PWR type reactors using matricial formalism

    International Nuclear Information System (INIS)

    Maciel, Edisson Savio G.; Andrade Lima, Fernando Roberto de; Lira, Carlos Alberto B.O.

    1995-01-01

    The matricial formalism of the perturbation theory is applied in a simplified model to study the hot channel of PWR reactors. Mass, linear momentum and energy conservation equations and appropriated heat transfer and fluid mechanics correlations describe the discretized system. After calculating system's thermalhydraulic properties, the matricial formalism is applied and the sensitivity coefficients are determined for each case of interest. Comparisons between perturbative method and direct results of the model have shown good agreement which demonstrates that the matricial formalism is an important tool for discretized system analysis. (author). 6 refs, 2 tabs

  9. Improvement to surface lagging systems in a nuclear reactor, particularly of the fast neutron type

    International Nuclear Information System (INIS)

    Lemercier, Guy.

    1979-01-01

    Improvements to surface lagging systems in a nuclear reactor, particularly of the fast neutron kind. This system is composed of an assembly of panels each formed of a stack of metal fabric or trellis held against the surface to be protected, by a double fixing system comprising (a) a tubular component passing through a hole in the panel and applying it against the surface through a bearing plate, and (b) a bolt fitted in the centre of the tubular component, also secured to the surface and holding a washer capable of preventing the fall of the tubular component and the panel should the tubular component fracture [fr

  10. The conversion of the DIDO-type reactor FRJ-2. Studies and conclusions

    International Nuclear Information System (INIS)

    Stroemich, A.; Siebertz, Ch.; Wickert, M.

    1985-01-01

    For the FRJ-2 (23 MW) of the KFA-Juelich the conversion from HEU- to LEU-fuel was investigated. Before starting the conversion calculations our methods were qualified for the application to heavy water moderated research reactors. A combination of LEU-elements with two different U-235 loadings of 180 g and 225 g was found as suitable for conversion. With these LEU-elements a working core and a transition phase was calculated. The change of the mechanical fuel element design was taken into account. (author)

  11. Aproximación a la base teórica de la inteligencia policial

    Directory of Open Access Journals (Sweden)

    Yofre Luis Cortés Vargas

    2013-08-01

    Full Text Available Este trabajo de investigación es una juiciosa aproximación que se realizó con el propósito de describir los fundamentos de conocimiento que caracterizan la inteligencia policial como disciplina científica. Los resultados obtenidos se centran en identificar el marco teórico afín con la práctica de la actividad que se desarrolla en la Dirección de Inteligencia Policial, proponer un concepto de inteligencia policial y fundamentar en forma teórica los rasgos característicos de esta. El precedente para iniciar la indagación, a través de consulta documental, grupos focales y seminario, se fundó en la identificación de un problema medular: la ausencia de una estructura sistemática de proposiciones que versara sobre los fundamentos de conocimiento que dan soporte a la inteligencia policial, y la cotidiana confusión de esta con otras áreas de conocimiento, al considerárseles, de manera errónea, como sinónimos. Cuando se propone, con elementos argumentativos de rigor, que dicha inteligencia tiene las características de una disciplina científica, y que se diferencia sustancialmente de cualquier otra actividad, se busca suscitar una reflexión crítica respecto de que la inteligencia policial la desarrollan de manera exclusiva los cuerpos de policía, para orientar la acción del ente de policía en materia de convivencia.

  12. Estimación del efecto de la inteligencia emocional sobre el bienestar en sacerdotes

    Directory of Open Access Journals (Sweden)

    María Purificación Vicente-Galindo

    2017-01-01

    Full Text Available Antecedentes/Objetivo: La inteligencia emocional es una variable que ha sido objeto de un incremento notable de investigación a lo largo de los últimos años. La inteligencia emocional ha mostrado numerosas relaciones con múltiples variables psicológicas, destacando su conexión con diversos trastornos físicos y psicológicos. El objetivo del presente estudio es analizar los efectos directos e indirectos que la inteligencia emocional ejerce sobre la manifestación de sintomatología somática y psicológica, así como sobre el desarrollo de trastornos como el síndrome de burnout en un grupo de profesionales cuya labor social resulta esencial. Método: Se aplicaron las escalas Trait Meta-Mood Scale-24, Maslach Burnout Inventory-22 y General Health Questionnaire-28 a un total de 881 sacerdotes católicos latinoamericanos (M edad=45,89; DT edad=11,58. Resultados: Mediante path analysis se muestra el efecto que la inteligencia emocional, especialmente la atención y claridad emocional, ejerce sobre las alteraciones somáticas y psicológicas. Conclusiones: Tanto los trastornos específicos como el bienestar general presentan una relación clara con la inteligencia emocional. Proporcionar programas formativos efectivos que desarrollen la inteligencia emocional podría reducir la aparición de trastornos físicos y emocionales. © 2017 Asociación Española de Psicología Conductual. Published by Elsevier España, S.L.U. This is an open access article under the CC BY−NC−ND license (http://creativecommons. org/licenses/by−nc−nd/4.0/.

  13. Survey of research reactors

    International Nuclear Information System (INIS)

    Boek, H.; Villa, M.

    2004-06-01

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  14. Effect of application rates and media types on nitrogen and surfactant removal in trickling filters applied to the post-treatment of effluents from UASB reactors

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, P. G. S. de; Taveres, F. v. F.; Chernicharo, C. A. I.

    2009-07-01

    Tricking filters are a very promising alternative for the post treatment of effluents from UASB reactors treating domestic sewage,especially in developing countries. Although a fair amount of information is already available regarding organic mater removal in this combined system, very little is known in relation to nitrogen and surfactant removal in trickling filters post-UASB reactors. Therefore, the purpose of this study was to evaluate and compare the effect evaluate and compare the effect of different application rates and packing media types on trickling filters applied to the post-treatment of effluents from UASB reactors, regarding the removal of ammonia nitrogen and surfactants. (Author)

  15. Effect of application rates and media types on nitrogen and surfactant removal in trickling filters applied to the post-treatment of effluents from UASB reactors

    International Nuclear Information System (INIS)

    Almeida, P. G. S. de; Taveres, F. v. F.; Chernicharo, C. A. I.

    2009-01-01

    Tricking filters are a very promising alternative for the post treatment of effluents from UASB reactors treating domestic sewage,especially in developing countries. Although a fair amount of information is already available regarding organic mater removal in this combined system, very little is known in relation to nitrogen and surfactant removal in trickling filters post-UASB reactors. Therefore, the purpose of this study was to evaluate and compare the effect evaluate and compare the effect of different application rates and packing media types on trickling filters applied to the post-treatment of effluents from UASB reactors, regarding the removal of ammonia nitrogen and surfactants. (Author)

  16. Single Phase Natural Circulation Behaviors of the Integral Type Marine Reactor Simulator under Rolling Motion Condition

    Directory of Open Access Journals (Sweden)

    Hou-jun Gong

    2015-01-01

    Full Text Available During operation in the sea the reactor natural circulation behaviors are affected by ship rolling motion. The development of an analysis code and the natural circulation behaviors of a reactor simulator under rolling motion are described in this paper. In the case of rolling motion, the primary coolant flow rates in the hot legs and heating channels oscillated periodically, and the amplitude of flow rate oscillation was in direct proportion to rolling amplitude, but in inverse proportion to rolling period. The total mass flow rate also oscillated with half the rolling period, and the average total mass flow rate was less than that in steady state. In the natural circulation under a rolling motion, the flow rate oscillations in the hot legs were controlled by the tangential force; however, the mass flow rate oscillations in the total natural circulation and the heating channels were a result of the combined action of the change of inclination angle, flow resistance, and the extra force arising from the rolling motion. The extra tangential force brought about intense flow rate oscillations in the hot legs, which resulted in increasing total flow resistance; however the extra centrifugal force played a role in increasing thermal driving head.

  17. The tensile and fatigue properties of type 1.4914 ferritic steel for fusion reactor applications

    International Nuclear Information System (INIS)

    Marmy, P.; Victoria, M.; Ruan, Y.

    1989-08-01

    Martensitic steels have received considerable attention as structural materials in fusion reactor applications. In present designs, fusion reactors are expected to operate in a cyclic mode, thus producing cyclic thermal stresses in the first wall. Due to its thermal expansion coefficient and very low swelling rate, 1.4914 martensitic steel is a suitable candidate for the first wall with high neutron loadings. This paper presents the preirradiation results obtained with subsize-specimens designed to be irradiated with a proton beam in the PIREX facility at the Paul Scherrer Institute (PSI) of Wuerenlingen. Both tensile and low cycle fatigue tests were performed in vacuum in the region from 300 K to 870 K (720 K in the case of fatigue tests). Tensile tests on the subsize specimens (0.33 mm thick) compared well to those on bulk specimens, showing a minimum in ductility at around 620 K. The fatigue tests, performed on tubular specimens (3.4 mm external diameter, 0.35 mm wall thickness) showed substantial softening setting in at a low number of cycles. The initial microstructure observed in transmission microscopy consists of fine martensite laths. As cyclic deformation proceeds, dislocation cells form, that gradually replace the martensitic laths. (author) 19 figs., 5 tabs., 16 refs

  18. Development of advanced nuclear core analysis system applicable to various reactor types (II)

    International Nuclear Information System (INIS)

    Kaneko, Kunio

    2003-03-01

    A 900 group cross section library based on the specification determined last year was produced for 27 nuclei of the fast reactor benchmark problem evaluated in nuclear data file JENDL-3.2. In addition, the new SLAROM code, which has been developed as an advanced detail analysis system, was revised so as to make cell calculations effectively with the above 900 group library. Furthermore, new functions were added to the SLAROM so that the SLAROM evaluates assembly parameters using effective cross sections derived by the SLAROM and produces any condensed effective cross section set for core performance analysis. With the 900 group cross section library and the revised SALROM, three cell calculations for fast and medium neutron speed reactors having different neutron spectrum were performed, and the results were compared with those calculated by the continuos energy Monte Carlo code MVP. By the comparisons, it is concluded that the newly revised SLAROM and a 900 group cross section library give accuracy comparable to MVP for predicting core performances. (author)

  19. Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    El-Sahlamy, Neama M. [Nuclear and Radiological Regulatory Authority, Cairo (Egypt)

    2017-11-15

    In the current work, comparisons between the core performances when using different LEU fuels are done. The fuels tested are UA1{sub X}-A1, U{sub 3}O{sub 8}-Al, and U{sub 3}Si{sub 2}-Al fuels with 19.7 % enrichment. Calculations are done using RELAP5 code to evaluate the thermal-hydraulic performance of the IAEA benchmark 10 MW reactor. First, a reassessment of the slow reactivity insertion transient with UA1{sub X}-A1 LEU fuel to compare the results with those reported in the IAEA TECDOC [1]. Then, comparisons between the thermal-hydraulic core performances when using the three LEU fuels are done. The assessment is performed at initial power of 1.0 W. The reactor power is calculated using the RELAP5 point kinetic model. The reactivity feedback, from changes in water density and fuel temperature, is considered for all cases. From the results it is noticed that U{sub 3}Si{sub 2}-Al fuel gives the best fuel performance since it has the minimum value of peak fuel temperature and the minimum peak clad surface temperature, as operating parameters. Also, it gives the maximum value of the Critical Heat Flux Ratio and the lowest tendency to flow instability occurrence.

  20. Significance of coast down time on safety and availability of a pool type fast breeder reactor

    International Nuclear Information System (INIS)

    Natesan, K.; Velusamy, K.; Selvaraj, P.; Chellapandi, P.

    2015-01-01

    Highlights: • Plant dynamics studies for quantifying the benefits of flow coast down time. • Establishment of minimum flow coast down time required for safety. • Assessment of influence of flow coast down on enhancing plant availability. • Synthesis of thermo mechanical benefits of flow coast down time on component design. - Abstract: Plant dynamic investigation towards establishing the influence of flow coast down time of primary and secondary sodium systems on safety and availability of plant has been carried out based on one dimensional analysis. From safety considerations, a minimum flow coast down time for primary sodium circuit is essential to be provided to limit the consequences of loss of flow event within allowable limits. Apart from safety benefits, large primary coast down time also improves plant availability by the elimination of reactor SCRAM during short term power failure events. Threshold values of SCRAM parameters also need optimization. By suitably selecting the threshold values for SCRAM parameters, significant reduction in the inertia of pumping systems can be derived to obtain desirable results on plant availability. With the optimization of threshold values and primary flow coast down behaviour equivalent to a halving time of 8 s, there is a possibility to eliminate reactor SCRAM during short term power failure events extending up to 0.75 s duration. Benefits of secondary flow halving on reducing transient thermal loading on components have also been investigated and mixed effects have been observed

  1. Inteligencia espiritual y respuesta inmunológica

    Directory of Open Access Journals (Sweden)

    José Manuel Barboza

    2013-12-01

    Full Text Available La inteligencia espiritual se define como la capacidad de entender de manera profunda los problemas existenciales, observándolos desde un punto de vista más amplio y reconociendo la relación que existe entre la percepción, las creencias y la conducta, de tal manera que puedan ser manejados de manera adecuada para una mejor adaptación a los mismos. En años recientes, la relación entre ésta y la medicina ha sido el foco de considerable atención ya que los estudios sugieren que hay una correlación positiva entre la espiritualidad/religiosidad (E/R y múltiples indicadores de salud, el bienestar y la sobrevida de los individuos. Los mecanismos mediante las cuales la E/R puede impactar la calidad de vida y por ende afectar la salud de los pacientes son los métodos de afrontamiento, las prácticas de salud y los nexos sociales, tanto los recomendados como los proscritos, de tal manera que mediante la activación del tono parasimpático vagal (reflejo colinérgico antiinflamatorio, estos son capaces de atenuar el incremento del tono simpático, estabilizando así las vías pro-inflamatorias.

  2. Educación ambiental, inteligencia espiritual y naturaleza

    Directory of Open Access Journals (Sweden)

    Jordi PUIG BAGUER

    2014-12-01

    Full Text Available La conciencia ambiental es característica en nuestra cultura, y plantea múltiples retos educativos. Las elecciones ambientales no dejan de construirnos… o destruirnos, tanto personal como colectivamente, en dimensiones corporales o culturales, en el individuo humano y en su paisaje. Entre ser humano y naturaleza existe un vínculo, común a ambos, de humanidad y naturalidad que no puede olvidarse en la educación sin erosionar el valor y el respeto del ser humano y la naturaleza a la vez.Este artículo busca impulsar la educación en medio ambiente mediante el desarrollo de la inteligencia espiritual y viceversa, con el fin de alimentar nuestro conocimiento con una profundidad y universalidad que necesitamos. En particular, destaca el papel cultural de la ciencia ecológica y resalta que la diferencia esencial entre los seres humanos y su medio natural permite –y debe– alimentar el respeto de ambos a través de la importancia y valor del recíproco. 

  3. Los Servicios de Inteligencia en la Transición

    Directory of Open Access Journals (Sweden)

    de Peñaranda y Algar, Juan María

    2005-01-01

    Full Text Available En el desarrollo de nuestra Transición política tuvieron un importante protagonismo los Servicios de Información españoles. Entre ellos, los mejor considerados como de «Inteligencia» eran los vinculados, durante aquellos años, a la Presidencia del Gobierno en la persona de su Presidente: la Tercera Sección del Alto Estado Mayor (AEM, la Organización Contrasubversiva Nacional (OCN y el Servicio Central de Documentación (SECED. El presente artículo se refiere al periodo comprendido entre los años 1968 en que se monta la Organización «Conde» -germen de la OCN- y 1977 en que terminan su vida oficial la Tercera Sección AEM y el SECED para constituir conjuntamente el nuevo Centro Superior de Información de la Defensa (CESID…

  4. Actualidad de la capacitación en Inteligencia de Negocios brindada por organizaciones latinoamericanas

    OpenAIRE

    Kuna, H. D.; Zamudio, Eduardo; Yatchesen, F. J.; Guerrero, F.; Lozina, M.; Rambo, A.; Caballero, S.; Marinelli, M.; Refosco, H. D.; Sequeira, G.; Rey, Martín Gustavo; Escalante, G. C.

    2016-01-01

    En la actualidad no se ha identificado un programa de capacitación que defina con claridad las estrategias didácticas y pedagógicas adecuadas para la formación de usuarios finales de soluciones de Inteligencia de Negocios en el ámbito de organizaciones de la Provincia de Misiones (Argentina). Este trabajo presenta un relevamiento de la oferta de capacitación en Inteligencia de Negocios en America Latina, e identifica un conjunto de características de las alternativas de capacitación ofrecidas...

  5. Inteligencia emocional, calidad de las relaciones interpersonales y empatía en estudiantes universitarios

    OpenAIRE

    NATALIO EXTREMERA PACHECO; PABLO FERNÁNDEZ BERROCAL

    2004-01-01

    El objetivo de este estudio fue examinar las conexiones entre inteligencia emocional, evaluada con medidas de auto-informe y de habilidad, la calidad de las relaciones interpersonales y la empatía en estudiantes universitarios. Además, se examinó la contribución de la inteligencia emocional como predictor de estas dimensiones. Ciento ochenta y cuatro estudiantes universitarios españoles completaron una batería de cuestionarios que incluía la versión española del Trait Meta-Mood Scale-24 (una ...

  6. EFECTO AGUDO DEL EJERCICIO FISICO EN LA INTELIGENCIA Y LA MEMORIA EN HOMBRES, SEGUN LA EDAD

    OpenAIRE

    Yorleny Alfaro Chavarría; Wálter Salazar Rojas

    2001-01-01

    Con muy diversas investigaciones se han demostrado los efectos agudos del ejercicio físico en los procesos cognitivos (memoria, inteligencia, tiempo de reacción, creatividad, etc.) según la edad. Sin embargo, gran cantidad de variables se ven involucradas en los diferentes tratamientos. Es, por esto, que se pretendió realizar una investigación específica y homogénea, de manera que los cambios obtenidos en la inteligencia y la memoria en las diferentes edades se deban al tratamiento en sí, y n...

  7. La importancia de la Inteligencia Emocional en los docentes en Educación Primaria.

    OpenAIRE

    Covacho-Antón, Arancha

    2012-01-01

    Este trabajo refleja la importancia de la Inteligencia Emocional en los docentes, que parece estar en un segundo plano, siendo eclipsada por el cociente intelectual, pero no por no ser evaluada es menos importante. De aquí en adelante se verá cómo no hay una sola inteligencia, pues que para un éxito tanto laboral como personal son necesarias unas habilidades emocionales que ayuden a afrontar diferentes situaciones a las que los docentes se enfrentan día a día. Por tanto será tan importante un...

  8. LA EPISTEMOLOGÍA Y LOS SISTEMAS DE INFORMACIÓN BASADOS EN INTELIGENCIA ARTIFICIAL

    OpenAIRE

    Miguel Rendueles Mata; Mercedes Dreher Grosch

    2007-01-01

    La Epistemología ha sido una disciplina Filosófica que toma su autonomía en particular desde distintas corrientes del siglo XVII. El campo de acción de esta disciplina ha versado esencialmente sobre la posibilidad de representación de la inteligencia humana. Ante el surgimiento de los Sistemas de Información basados en la Inteligencia Artificial, la Epistemología se enfrenta a un reto, pues se muestra que aun falta mucho por aclarar acerca de los avances en esta área. Este artículo presenta e...

  9. Inteligencia emocional en estudiantes de la Universidad Nacional del Centro del Perú, 2013

    OpenAIRE

    Cesar Reyes Lujan; Iris Carrasco Díaz

    2014-01-01

    Objetivos: Determinar los niveles de inteligencia emocional predominantes en los estudiantes de la Facultad de Enfermería de la Universidad Nacional del Centro del Perú en el año 2013. Método: Se empleó el método descriptivo prospectivo. Se evaluaron un total de 195 estudiantes de 16 a 30 años de edad en toda la facultad. Para la recolección de datos, se aplicó el inventario Emocional de BarOn y el inventario de coeficiente emocional (ICE) que permitió conocer su inteligencia emocional. Resul...

  10. Personalidad, inteligencia emocional y estilos de afrontamiento en los conciliadores de la ciudad de Arequipa

    OpenAIRE

    Walter Lizandro Arias Gallegos; Alejandra E. Infantes Chávez; Karla D. Ceballos Canaza

    2016-01-01

    RESUMEN: El presente estudio analiza las características psicológicas de un grupo de 26 conciliadores de la ciudad de Arequipa. Para ello se ha evaluado la personalidad con el Inventario de Personalidad de Eysenck, los estilos de afrontamiento con el Cuestionario de Modos de Afrontamiento de Lazarus y Folkman, la inteligencia emocional con el Cuestionario de Inteligencia Emocional y para valorar algunas manifestaciones clínicas de la personalidad se utilizó el MINI-MULT. Los resultados indica...

  11. Inteligencia emocional y desempeño laboral en trabajadores del Hospital Hermilio Valdizan 2016

    OpenAIRE

    Paredes Ruíz, Karla

    2016-01-01

    El objetivo del presente trabajo de investigación es determinar como se relaciona la inteligencia emocional y el desempeño laboral en los trabajadores del Hospital Hermilio Valdizan en el año 201 6. Y como problema general ¿Cómo se relaciona la inteligencia emocional con el desempeño laboral en los trabajadores del Hospital Hermilio Valdizan en el año 2016? El tipo de investigación es de tipo básica diseño no experimental, descriptivo correlacional, y transversal. Se utiliz...

  12. Inteligencia emocional y desempeño laboral de los trabajadores de una empresa peruana

    OpenAIRE

    Orué Arias, Elsa

    2011-01-01

    Objetivo: Determinar cuál es la relación entre los niveles de inteligencia emocional de los trabajadores de una empresa peruana y su desempeño laboral. Método: Investigación descriptiva–explicativa. Se aplicó una encuesta en una muestra de 187 trabajadores de diversas áreas de la empresa, identificándose cuatro variables para medir la inteligencia emocional: autoconocimiento, automotivación, autocontrol y control de las relaciones interpersonales. Resultados: La relación entre las variables i...

  13. Resilencia en Adolescentes y su Relación con la Inteligencia Emocional

    OpenAIRE

    Morán Gómez, Miriam

    2015-01-01

    La resilencia cobra importancia hoy en día por la gran cantidad de transformaciones del mucho y las situaciones adversas que aparecen en la vida cotidiana. Por ello es necesario conocer que elementos permiten desarrollar la resilencia, como por ejemplp la Inteligencia Emocional. Además mediante un estudio empírico se analiza esa relacion entre resilencia y la Inteligencia Emocional en una población especialmente vulnerable: la adolescencia. Departamento de Psicología Máster en Profesor ...

  14. INTELIGENCIA EMOCIONAL, ESTRÉS, AUTOEFICACIA, LOCUS DE CONTROL Y RENDIMIENTO ACADÉMICO EN UNIVERSITARIOS

    OpenAIRE

    Melissa Cristina Aguilar Rivera; Orlando Francisco Gil Llanes; Viviane Angélica Pinto Garrido; César Ricardo Quijada Maldonado; Carlos Alberto Zúñiga Sánchez

    2014-01-01

    La inteligencia emocional desempeña un papel importante en la determinación del éxito en la vida académica al permitir lidiar de una manera más eficaz con las situaciones estresantes. La presente investigación tuvo como objetivo conocer y comparar los niveles de inteligencia emocional, distrés, factores psicosomáticos, autoeficacia y locus de control para identificar el impacto que ejercían en el rendimiento académico de 368 estudiantes de una universidad pública. Los resultados mostraron un ...

  15. Fundamentos psicopedagógicos de las inteligencias múltiples

    OpenAIRE

    Ferrándiz, Carmen; Prieto, María Dolores; Bermejo, María Rosario; Ferrando, Mercedes

    2006-01-01

    El objetivo del trabajo es estudiar las raíces psicopedagógicas del modelo de las Inteligencias Múltiples. Analizamos los datos procedentes de nuestro estudio realizado con 294 alumnos (preescolar y primeros niveles de educación primaria). Es hacia 1983 cuando Gardner publica su libro titulado Estructura de la Mente, donde propone la existencia de siete inteligencias, que más tarde amplia a ocho (lingüística, lógico-matemática, visoespacial, corporal-cinestésica, musical, interpersonal, i...

  16. Inteligencia Emocional en los docentes de la Universidad Militar Nueva Granada

    OpenAIRE

    López Pacheco, Jenny Carolina; Pedraza Ortíz, Alexandra Patricia

    2016-01-01

    La presente investigación tuvo como objetivo principal describir el estado actual de la inteligencia emocional en los docentes de la Universidad Militar Nueva Granada. Se utilizaron los siguientes instrumentos: escala Trait Meta Mood Scale 24 (TMMS-24) y una encuesta de variables sociodemográficas. También se describió la percepción que tienen los docentes con relación al concepto de Inteligencia Emocional. La investigación fue de tipo observacional descriptiva, se realizó un muestreo por con...

  17. Técnicas actorales e inteligencia emocional para profesionales de la salud: aprendizaje transformacional

    OpenAIRE

    Esther Solsona de la Serna; Jordi Pujol; Salvador Llistar; Elena Barbera; Nuria Giménez

    2015-01-01

    El trabajo del profesional sanitario combina ciencia y arte, conocimientos y medios técnicos, junto con inteligencia emocional. Objetivo: Conocer la experiencia de los profesionales que recibieron una intervención educativa para potenciar la inteligencia emocional mediante técnicas de formación actoral. Metodología: Desde 2008 hasta 2013, un equipo multidisciplinar impartió quince ediciones de formación sobre cómo reconocer y gestionar las propias emociones. Se utilizó metodología mixta: cual...

  18. Inteligencia Contextual Percibida en el Deporte. Desarrollo y Validación de un Cuestionario

    OpenAIRE

    Luis Miguel Ruiz Pérez; José Luis Graupera Sanz; Virginia García Coll

    2014-01-01

    El propósito de este estudio ha sido el desarrollo y validación de un Cuestionario de Inteligencia Contextual Percibida en el Deporte en una muestra de deportistas españoles de diferente nivel de pericia. Participaron 2091 deportistas (1519 hombres y 572 mujeres) de edades comprendidas entre los 11 y los 59 años (M = 20,8; DT = 6,14). Los análisis factoriales exploratorio y confirmatorio mostraron que el cuestionario presentaba una estructura de tres dimensiones (inteligencia anticipatoria, i...

  19. Un sistema de inteligencia interno para la organización inteligente

    Directory of Open Access Journals (Sweden)

    Stephanie Lorena Fallas Navarro

    2010-10-01

    Full Text Available Este artículo resume la investigación que se realizó en el marco del Trabajo de Graduación titulado "La Organización Inteligente: diseño de una propuesta para un Sistema de Inteligencia Interno"en Administración de Empresas con énfasis en Gestión Organizacional de la Universidad Estatal a Distancia (UNED. La propuesta presenta un marco metodológico para el desarrollo de un Sistema de Inteligencia Interno de aplicación práctica, para orientarse a una estructura de Organización Inteligente.

  20. ¿Puede la Inteligencia Emocional predecir el rendimiento?. Potencial predictor de los Moldes Mentales

    OpenAIRE

    Pedro HERNÁNDEZ HERNÁNDEZ

    2005-01-01

    Los numerosos estudios que investigan el rendimiento académico están influidos por los paradigmas psicológicos dominantes en cada época. Actualmente está emergiendo el paradigma "cognitivo-emocional", que evidencia la circularidad de lo intelectivo y lo socioafectivo, a pesar de la incapacidad de la Inteligencia Emocional para predecir hasta ahora el rendimiento. Sin embargo, los Moldes Mentales (HERNÁNDEZ, 2002), una nueva perspectiva de la Inteligencia Emocional, basados en los formatos ...

  1. Relación entre Inteligencia Emocional y salud mental en Orientadores Educativos

    OpenAIRE

    Cejudo Prado, Manuel Javier

    2016-01-01

    Introducción. El objetivo de la presente investigación está dirigido a estudiar la relación de la inteligencia emocional como capacidad y la inteligencia emocional como rasgo con salud mental en una muestra de orientadores educativos. Método. La muestra ha estado compuesta de 203 orientadores. Los instrumentos utilizados han sido: Mayer-Salovey-Caruso Emotional Intelligence Test (MSCEIT), Trait Emotional Intelligence Questionnaire Short Form (TEIQUE-SF) y la Escala de Salud Mental (MH5). En p...

  2. Capacidad predictiva del apoyo social en la inteligencia emocional de adolescentes

    OpenAIRE

    Lorea Azpiazu; Igor Esnaola; Marta Sarasa

    2015-01-01

    El objetivo de este estudio es analizar la relación entre el apoyo social (familiar, amistades y profesorado) y la inteligencia emocional (atención, claridad y reparación). La muestra está compuesta por 1543 adolescentes, 728 chicos (47.18%) y 815 chicas (52.81%), entre los 11 y 18 años (Medad = 14.24, DT = 1.63). Los análisis estadísticos se llevan a cabo con el programa SPSS 21 para Windows. Los resultados del análisis correlacional señalan que el apoyo social y la inteligencia emocional es...

  3. La Inteligencia Emocional aplicada a la Administración de Personal

    OpenAIRE

    Seco Aguilar, José Joaquín

    2013-01-01

    Cada día se impone un nuevo concepto en elmanejo del personal de las empresas. Se trata dela inteligencia emocional, que le ha dado vida a lasrelaciones humanas, tanto internas como externas, hapotenciado las actividades gerenciales y ha logradoque se aproveche al máximo la energía que aportan losseres humanos, quienes constituyen lo más importantede la actividad de cualquier empresa. Por esta razón,se exploran los conceptos de inteligencia emocional,así como su aplicación en el ámbito de las...

  4. Inteligencia emocional y responsabilidad social en Educación Primaria

    OpenAIRE

    Sancho Arranz, Verónica

    2014-01-01

    Inteligencia Emocional y Responsabilidad Social en Educación Primaria es un Trabajo de Fin de Máster teórico-experimental. Consiste en estudiar qué grado de relación e influencia tiene la Responsabilidad Social entre el alumnado del tercer ciclo de Educación Primaria para la mejora de la Inteligencia Emocional-Social, con el propósito de promover intervenciones didácticas en esa línea. Para la obtención de datos se aplicaron dos cuestionarios (EARSA-P y EQ-i YV) en alumnado de 5º y 6º curso d...

  5. Inteligencia emocional y liderazgo en los gerentes bancarios del Perú

    OpenAIRE

    Bustamante Panez, Sheilla; Kawakami Okada, Roxana; Reátegui Medina, Sandro

    2010-01-01

    La presente investigación cuantitativa correlacional examinó la relación entre la inteligencia emocional y los estilos de liderazgo de los gerentes bancarios en el Perú. Para la muestra, se contó con la participación de 102 gerentes bancarios, quienes respondieron el cuestionario BarOn EQ-i adaptado a la realidad peruana por la Dra. Ugarriza, para medir la inteligencia emocional; y el cuestionario MLQ 5X-Short, para medir los estilos de liderazgo (transformacional, transacciona...

  6. Inteligencia emocional y prácticas de liderazgo en las organizaciones colombianas

    OpenAIRE

    Rodrigo A. Zárate Torres; Sergio Matviuk

    2012-01-01

    La relación entre inteligencia emocional y liderazgo ha sido explorada por varios autores (Barbuto y Burbach, 2006; Dulewics, Young y Dulewics, 2005; Gardner y Stough, 2002; Barling, Slater y Kelloway, 2000); sin embargo, esta relación aún no se ha estudiado a profundidad en Latinoamérica. Éste estudio muestra la relación existente entre las prácticas de liderazgo y la inteligencia emocional en los empleados colombianos. Para el efecto, se aplicó el inventario de prácticas de liderazgo de Kou...

  7. La inteligencia emocional y la atención plena (mindfulness como estrategia para la gestión de emociones negativas

    Directory of Open Access Journals (Sweden)

    Edgar Bresó

    2013-07-01

    Full Text Available Abstract This reflection paper aims to summarize the empirical evidence about the efficitiveness of the strategies based on mindfulness and the emotional intelligence (EI oriented to solve problems which make possible to show negative emotions. In addition, this paper also proposes future challenges in order to distinguish the proposal that these two coping strategies (emotional inteligence and mindfulness have at the time of managing and adapting to the experiencies of such emotions. The methodology used focuses on identifying experimental studies which have assessed the effect of programs directed to develop emotional intelligence and mindfulness. Finally, new types of research are proposed for futures studies which will be able to give answers to the current questions. Resumen El objetivo del presente artículo de reflexión consiste en resumir la evidencia empírica sobre la eficacia de las estrategias basadas en la atención plena y en la inteligencia emocional para gestionar la solución de problemas que comportan la aparición de emociones afectivamente negativas. Además, se proponen retos futuros con el fin de distinguir el aporte que cada una de estas dos estrategias de afrontamiento (inteligencia emocional y atención plena tienen a la hora de gestionar y adaptarse a la experiencia de dichas emociones. La metodología utilizada se centra en la identificación de estudios experimentales, que han probado el efecto de programas dirigidos a desarrollar la inteligencia emocional y la atención plena. Finalmente, se proponen nuevas líneas de investigación para futuros estudios que puedan dar respuestas a las preguntas que se plantean en la actualidad.

  8. 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.)

  9. Controlling method for impurity concentration in the feedwater system of a BWR type reactor

    International Nuclear Information System (INIS)

    Yamazaki, Kenji

    1987-01-01

    Purpose: To decrease ionic radioactive deposition and reduce the exposure dose upon inspection in the recycling system of a nuclear reactor. Method: Fe concentration is analyzed based on the crud concentration measured by a turbidimeter and the concentration is calculated. Further, Ni density is analyzed by an ion crossed meter and the density is calculated. From the calculated values, the density between Fe density and Ni density, i.e., Fe/Ni is calculated. If the calculated value for Fe/Ni is lower than a setting value (Fe/Ni = 2), an open signal is outputted for an iron injection valve disposed at the midway of a pipeway connected from a tank containing suspended iron oxide or iron hydroxide to a feedwater pipe. Then, the opening degree of the iron injection valve is adjusted based on the deviation value between the setting value (Fe/Ni = 2) and the calculated value for Fe/Ni. (Yoshino, Y.)

  10. Development of a neutronic model for the fuel of a high temperature gas reactor type PBMR

    International Nuclear Information System (INIS)

    Oropeza C, I.; Carmona H, R.; Francois L, J. L.

    2008-01-01

    In this work was developed the neutronic model of a fuel sphere of a nuclear reactor of gas of high temperature to modulate of bed of spheres (PBMR), using the Monte Carlo method with the MCNPx code. In order to be able to verify the fuel model constructed in this investigation, it is used a case of reference, based on an international exercise b enchmark . The benchmark report contains the results sent by different international participants for five phases with respect to the high temperature gas reactor (HTR), fed with uranium, plutonium and thorium. In particular, in first stage of benchmark an infinite adjustment of uranium compound fuel spheres is considered unique, with which our results were compared. This first stage considers two cases: cell calculations with spherical external frontier and cell calculations with cubic external frontier. The objective is to identify any increase in the uncertainty, related to the uranium fuel, that is associated with the plutonium and thorium fuels. In order to validate our results, the values of the neutron multiplication factor were taken in account, in cold and in the heat of the moment from the participants who sent their results obtained with Monte Carlo and deterministic calculations. The model of the fuel sphere developed in this work considers a regular distribution of 15000 Triso particles, in a cubic mesh centered within the sphere. For it was necessary to define the step firstly or p itch o f the cubic mesh. Generally, the results obtained by the participants of benchmark and those of this investigation present good agreement, nevertheless, appear some discrepancies, attributed to factors like different libraries of cross sections used, the nature of the solution: Monte Carlo or deterministic, and the difficulty of some participants to model the external frontier condition of reflection. (Author)

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  12. Thermohydraulic calculations in rectangular channels for RA-6 type reactors with transition regime

    International Nuclear Information System (INIS)

    Sillin, N; Vertullo, A.; Masson, V.; Hilal, R

    2009-01-01

    In August 2000 and within the framework of the RA-6 core conversion from high to low enrichment (20%), a preliminary analysis was performed to evaluate the maximum power that the reactor could operate with the new kernel without makeing substantial changes. This meant keeping intact, for example, the concrete shield of the pool and the nucleus inlet and outlet pipes embedded in the walls. Preliminary results indicated that for these boundary conditions a maximum power of about 3 MWt could be achieved. In August 2005 the project was resumed and new calculations performed taking as a starting point the ECBE plate fuel element(U3O8-Al). A core was developed with cooling channle widths of 2.6 mm for the control fuel elements and 2.7 mm for standard fuel elements. The thermo-hydraulic calculation puts in evidence that coolant flow into the core was in the transitional regime for the vast majority of configurations. While TERMIC code, used for thermo-hydraulic design, has been extensively tested and validated for use in research reactors under turbulent and laminar flows, this is not so for transition conditions. The transition regime is strongly dependent on conditions such as flow inlet characteristics, channel geometry, etc.. and therefore there are no reliable correlations for general use. For this reason we found it convenient to carry out experiments simulating the working conditions in order to adjust the code results with experimental data. In the present work we show the experimental results, the simulation of the experiences using the TERMIC code, and the adjustments made to the correlations used by the code so that it can be applied to the thermo-hydraulic design of the new core. [es

  13. Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core

    International Nuclear Information System (INIS)

    Zheng, Meiyin; Tian, Wenxi; Chu, Xiao; Zhang, Dalin; Qiu, Suizheng; Su, Guanghui

    2014-01-01

    Highlights: • A 1500MWt radial fuel shuffling sodium cooled breed and burn reactor core was designed. • The board type radial fuel shuffling strategy was applied and demonstrated. • Influences of the fuel height and core radius were investigated. - Abstract: In this paper, a preliminary board type radial fuel shuffling sodium cooled breed and burn reactor core is designed. In the current design, a number of breeding subassemblies are arranged in the center core to ensure enough breeding. A self-developed MCNP-ORIGEN coupled system with the ENDF/B-VI data library is applied to perform neutronics and burn-up calculations. For a 2.0 m radius and 2.5 m height core, the results demonstrate the feasibility of the board type radial fuel shuffling strategy. Breeding mainly occurs in the breeding subassemblies during the first 6 fuel cycles as they are moved to the burning/breeding region. The core will become asymptotically stable after about 24 years. The discharged burn-up of most subassemblies is about 15.0–30.0%. The influences of the core size on the major core parameters, such as initial k eff , steady k eff , maximum power density, peak burn-up and burn-up ratio between breeding and ignition subassemblies are calculated and investigated. The results indicate that the initial k eff increases with fuel height and core radius and finally reaches stability; the steady k eff increases with fuel height and core radius, then reaches peak value and finally decreases; the maximum power density, the peak burn-up and the burn-up ratio between breeding and ignition subassemblies decrease with the increase of fuel height and core radius; if core radius is less than 1.875 m, they increase sharply with the decrease of core radius

  14. Evaluation of different types of anaerobic seed sludge for the high rate anaerobic digestion of pig slurry in UASB reactors.

    Science.gov (United States)

    Rico, Carlos; Montes, Jesús A; Rico, José Luis

    2017-08-01

    Three different types of anaerobic sludge (granular, thickened digestate and anaerobic sewage) were evaluated as seed inoculum sources for the high rate anaerobic digestion of pig slurry in UASB reactors. Granular sludge performance was optimal, allowing a high efficiency process yielding a volumetric methane production rate of 4.1LCH 4 L -1 d -1 at 1.5days HRT (0.248LCH 4 g -1 COD) at an organic loading rate of 16.4gCODL -1 d -1 . The thickened digestate sludge experimented flotation problems, thus resulting inappropriate for the UASB process. The anaerobic sewage sludge reactor experimented biomass wash-out, but allowed high process efficiency operation at 3days HRT, yielding a volumetric methane production rate of 1.7LCH 4 L -1 d -1 (0.236LCH 4 g -1 COD) at an organic loading rate of 7.2gCODL -1 d -1 . To guarantee the success of the UASB process, the settleable solids of the slurry must be previously removed. Copyright © 2017 Elsevier Ltd. All rights reserved.

  15. A model for the analysis of loss of decay heat removal accident in MTR pool type research reactors

    International Nuclear Information System (INIS)

    Bousbia-Salah, A.

    2005-01-01

    During a loss of coolant accident leading to total emptying of the reactor pool, the decay heat could be removed through air natural convection. However, under partial pool emptying the core is partially submerged and the coolant circulation inside the fuel element could no more be possible. In such conditions, a core overheat take place, and the heat is essentially diffused from the core to its periphery by combined thermal radiation and conduction. In order to predict fuel element temperature evolution under such conditions a mathematical model is performed. The model is based on a three dimensional geometry and takes into account a variety of core configurations including fuel elements (standard and control), reflector elements and grid plates. The homogeneous flow model is used and the time and space dependent non-linear partial differential fluid conservation equations are solved using a semi-implicit finite difference method. Preliminary tests of the developed model were made by considering a series of hypothetical accidents. In the current framework a loss of decay heat removal accidents in the IAEA benchmark open pool MTR-type research reactor is considered. It is shown that in the case of a low core immersion height no water boiling is observed and the fuel surface temperature rise remains below the melting point of the aluminium cladding. (author)

  16. The status of the Bubbler Condenser Containment System for the Reactors of the VVER-440/213 Type

    International Nuclear Information System (INIS)

    Karwat, H.; Rosinger, H.E.

    1998-01-01

    VVER-440/213 Pressurized Water Reactors have a pressure-suppression containment structure called a 'Bubbler Condenser' tower which can reduce the design pressure of the entire containment following a design basis accident (DBA), such as a loss-of-coolant accident (LOCA). The bubbler condenser pressure suppression system provides reduction of the LOCA containment pressure by the condensation of released steam in a water pool. World-wide there are 14 nuclear power plants of the VVER-440/213 type in Eastern Europe and Russia. One of the safety concerns for the VVER-440/213 reactors relates to the ability of the bubbler condenser containment system to function satisfactorily and to maintain its integrity following certain postulated accidents and thus limit the release of radioactive material to the environment. The complicated geometry of the bubbler condenser unit, and the dependence on several moving devices and interlocks are the main doubts expressed by different specialists with regard to the design. General description of the bubbler condenser containment system, the physical processes, concerns and design assessment of the bubbler condenser containment system, presentation of the OECD's Unified Bubbler Condenser Research Project (UBCRP) and the European Commission PHARE/TACIS project. Recent utility investigations are also discussed

  17. Environmental impact assessment of a package type IFAS reactor during construction and operational phases: a life cycle approach.

    Science.gov (United States)

    Singh, Nitin Kumar; Singh, Rana Pratap; Kazmi, Absar Ahmad

    2017-05-01

    In the present study, a life cycle assessment (LCA) approach was used to analyse the environmental impacts associated with the construction and operational phases of an integrated fixed-film activated sludge (IFAS) reactor treating municipal wastewater. This study was conducted within the boundaries of a research project that aimed to investigate the implementation related challenges of a package type IFAS reactor from an environmental perspective. Along with the LCA results of the construction phase, a comparison of the LCA results of seven operational phases is also presented in this study. The results showed that among all the inputs, the use of stainless steel in the construction phase caused the highest impact on environment, followed by electricity consumption in raw materials production. The impact of the construction phase on toxicity impact indicators was found to be significant compared to all operational phases. Among the seven operational phases of this study, the dissolved oxygen phase III, having a concentration of ∼4.5 mg/L, showed the highest impact on abiotic depletion, acidification, global warming, ozone layer depletion, human toxicity, fresh water eco-toxicity, marine aquatic eco-toxicity, terrestrial eco-toxicity, and photochemical oxidation. However, better effluent quality in this phase reduced the eutrophication load on environment.

  18. Cryogenic distillation: a fuel enrichment system for near-term tokamak-type D-T fusion reactors

    International Nuclear Information System (INIS)

    Misra, B.; Davis, J.F.

    1980-02-01

    The successful operation and economic viability of deuterium-tritium- (D-T-) fueled tokamak-type commercial power fusion reactors will depend to a large extent on the development of reliable tritium-containment and fuel-recycle systems. Of the many operating steps in the fuel recycle scheme, separation or enrichment of the isotropic species of hydrogen by cryogenic distillation is one of the most important. A parametric investigation was carried out to study the effects of the various operating conditions and the composition of the spent fuel on the degree of separation. A computer program was developed for the design and analysis of a system of interconnected distillation columns for isotopic separation such that the requirements of near-term D-T-fueled reactors are met. The analytical results show that a distillation cascade consisting of four columns is capable of reprocessing spent fuel varying over a wide range of compositions to yield reinjection-grade fuel with essentially unlimited D/T ratio

  19. Mejora de la inteligencia emocional a través de la responsabilidad social en Educación Primaria

    OpenAIRE

    Sancho Arranz, Verónica

    2014-01-01

    Se trata de un Trabajo de Fin de Grado en el que se realiza una revisión teórica acerca de los conceptos Responsabilidad Social, Inteligencia Emocional e Inteligencia Emocional-Social, que nos servirá como base para el desarrollo de una propuesta didáctica en el tercer ciclo de Educación Primaria. El objetivo general de dicho programa didáctico es fomentar la Inteligencia Emocional mediante la realización de actividades que desarrollen la Responsabilidad Social. Además, se incluye una propues...

  20. PROGRAMA PARA FOMENTAR EL DESARROLLO DE LA INTELIGENCIA EMOCIONAL EN EL ALUMNADO DE SEGUNDO CURSO DE EDUCACIÓN PRIMARIA

    OpenAIRE

    Cañás-Vidal, Mari Carmen

    2014-01-01

    El presente trabajo está dirigido a la creación de un programa para abordar el desarrollo de la Inteligencia Emocional en un grupo de segundo curso de Educación Primaria. En esta misma dirección, se investigará cómo influye el desarrollo de la inteligencia emocional en los otros tipos de inteligencia. Se plantean propuestas para que los alumnos expresen un adecuado comportamiento, asimilen las emociones positivas, autorregulen su conducta y sean capaces de proceder adecuadamente ante una s...

  1. Inteligencia emocional y desempeño laboral de los directivos del corporativo adventista del norte de México

    OpenAIRE

    Guardiola, Catalina; Universidad de Montemorelos, México; Basurto, Karla

    2014-01-01

    El objetivo principal de este estudio es conocer la autopercepción del nivel de inteligencia emocional como predictor del desempeño laboral. El cual deberá responder a las siguientes preguntas: ¿cuál es la autopercepción del nivel de inteligencia emocional de los directivos del corporativo adventista al norte del México y la relación que existe con su desempeño laboral? ¿Existe una relación significativa entre la autopercepción de la inteligencia emocional y los siguientes factores: años de s...

  2. Estimulación de la inteligencia corporal en niños de cinco años

    OpenAIRE

    Rubio, Nuria

    2012-01-01

    La teoría de las Inteligencias Múltiples, Howard Gardner, reconoce diferentes formas de enseñar y aprender, a través de procedimientos dinámicos de evaluación cognitiva. El objetivo del trabajo es el estudio de las Inteligencias Múltiples en una muestra de alumnos de 3º de educación Infantil. Para ello se ha pasado el cuestionario de Inteligencias múltiples a 20 alumnos de un colegio público de una localidad de Extremadura. Los resultados muestran puntuaciones significati...

  3. Perfil de las inteligencias múltiples de los niños del nivel inicial 2

    OpenAIRE

    Dumán Delgado, Viviana Alexandra

    2017-01-01

    La presente investigación es de corte transversal cuantitativo, con un alcance descriptivo, cuyo propósito fue conocer el perfil de las inteligencias múltiples en los niños del nivel inicial 2 en un momento dado. Es un estudio observacional que se basó en las percepciones por parte de los docentes sobre el nivel de desarrollo de las inteligencias múltiples en los niños de 4 a 5 años. Se utilizó el instrumento denominado “Escala de observación de inteligencias múltiples” Se trata de una ad...

  4. La Inteligencia y la seguridad emocional: el caso de la adaptación de los preadolescentes en la escuela

    OpenAIRE

    Pérez Escoda, Núria; Alegre Roselló, Albert

    2012-01-01

    Resumen Las investigaciones desarrolladas hasta ahora muestran que hay una relación entre la capacidad de las personas de rendir efectivamente y sus niveles de seguridad e inteligencia emocional. Los adolescentes deben adaptarse a la escuela, y su inteligencia y seguridad emocional pueden ser factores determinantes en su rendimiento. Por ello, este estudio investiga la relación entre la inteligencia emocional y la inseguridad de los preadolescentes, así como su relación con su adaptación a la...

  5. Aproximación a la inteligencia para la seguridad nacional/Approach to intelligence for national security

    OpenAIRE

    Luis Hurtado González (España)

    2009-01-01

    La inteligencia por ser una metodología en la que se desprenden valoración que permiten reconocer las amenazas que ponen en riesgo. Los Estados democrático requieren realizar dicha actividad, a fin de salvaguardar la seguridad nacional la producción de inteligencia se presenta como una tarea imperativa para todo estado, en especial en aquellos que muestran debilidades estructurales crónicas, este ya representa avance, ya que legitima el accionar de nuestros órganos de inteligencia. Existen al...

  6. Inteligencia fluida y cristalizada en el autismo de alto funcionamiento y el síndrome de Asperger

    OpenAIRE

    Pérez, P.F.

    2016-01-01

    La inteligencia en los trastornos del espectro autista, especialmente en el autismo de alto funcionamiento y el síndrome de Asperger, ha sido tema de numerosas investigaciones que pretenden establecer la capacidad intelectual que se observa en estos sujetos. Algunos de los resultados más sobresalientes señalan que la inteligencia fluida es uno de los aspectos de desempeño superior en esta población, en comparación con el desempeño en las pruebas que miden inteligencia cristalizada como la esc...

  7. Nuclear reactors; graphical symbols

    International Nuclear Information System (INIS)

    1987-11-01

    This standard contains graphical symbols that reveal the type of nuclear reactor and is used to design graphical and technical presentations. Distinguishing features for nuclear reactors are laid down in graphical symbols. (orig.) [de

  8. The theoretical possibility of reducing the doubling time in a fast-reactor by using heterogeneous configurations of various types of fuel

    International Nuclear Information System (INIS)

    Orlov, V.V.; Slesarev, I.S.; Zaritskij, S.M.; Subbotin, S.A.; Alekseev, P.N.; Zverkov, Yu.A.

    1980-01-01

    The authors have derived approximate expressions relating the doubling time of a fast reactor using various types of fuel simultaneously to the doubling time of traditional (homogeneous) reactors in which these types of fuel are used separately. These relationships afford a means of determining the conditions in which the use of various types of fuel can result in an improved doubling time. It was established that the use of heterogeneous compositions formed from assemblies of homogeneous systems gives a notable gain in doubling time over that of any of the original homogeneous systems if the doubling times were similar to each other. This gain is fairly large even in the case of BN reactors with high fuel volume fractions. The size of the gain depends on the degree of ''differentiation'' in the neutron and thermal properties of the components of the heterogeneous reactor. An optimum proportion has been found for the assemblies taken from the original homogeneous systems, governed primarily by the ratio of fuel densities. Estimates were made of the advantages of metallic oxide compositions over the traditional compositions used in large, fast reactors of the BN type. These estimates indicate that the former can be considered as alternative homogeneous compositions with carbide or nitride fuel as far as breeding characteristics are concerned. (author)

  9. Characterization of the biomass of a hybrid anaerobic reactor (HAR with two types of support material during the treatment of the coffee wastewater

    Directory of Open Access Journals (Sweden)

    Vivian Galdino da Silva

    2013-06-01

    Full Text Available This study investigated the microbiology of a hybrid anaerobic reactor (HAR in the removal of pollutant loads. This reactor had the same physical structure of an UASB reactor, however with minifilters inside containing two types of support material: expanded clay and gravel. Two hydraulic retention times (HRT of 24h and 18h were evaluated at steady-state conditions, resulting in organic loading rates (OLR of 0.032 and 0.018 kgDBO5m-3d-1 and biological organic loading rates (BOLR of 0,0015 and 0.001 kgDBO5kgSVT- 1d¹, respectively. The decrease in concentration of organic matter in the influent resulted an endogenous state of the biomass in the reactor. The expanded clay was the best support material for biofilm attachment.

  10. La inteligencia emocional en personas que viven con VIH

    Directory of Open Access Journals (Sweden)

    Dailys Suárez Iglesias

    2013-10-01

    Full Text Available ResumenLa investigación se desarrolló en el período de noviembre de 2006 a abril de 2007, con un grupo de personas que viven con VIH del municipio de Santa Clara, Cuba. La muestra de 40 personas fue dividida a la mitad, en dos grupos, uno con diagnóstico de debut y otro con diagnóstico de más de un año. Fue pareada siguiendo en la medida posible las variables sociodemográficas: sexo, rango de edad, estado civil, variante sexual y diagnóstico. La investigación intenta caracterizar la Inteligencia Emocional (IE en personas que viven con VIH. En función de los objetivos, se emplearon las técnicas: Trait Meta-Mood Scale-24, Beck Depresión Inventory, Spielber State Anxiety Questionnaire, Mental Health, Escala de Satisfacción Vital, White-Bear Supression Inventory. Los resultados se analizaron de forma cualitativa y cuantitativa. La valoración estadística se realizó mediante el paquete SPSS, versión 13.0, permitiendo indagar si existían diferencias significativas entre los subgrupos muestrales estudiados. Se hallaron diferencias significativas en la expresión de la inteligencia emocional entre ambos grupos, resultando más afectada en las personas del grupo con diagnóstico de debut. Se observó como hallazgo una correlación positiva y significativa en la puntuación del CD4 con el constructo que caracteriza la estructura de la IE. (Duazary 2009 I; 10-24AbstractThis research was developed in the period of November 2006 to April 2007, with a group of persons who are living with HIV in the municipality of Santa Clara in Cuba.The sample of 40 persons was divided into two groups, with a first group including a debut diagnosis and the other including a diagnosis for more than a year. It was realized following when possible the socio demographic characteristics: sex, range of age, marital status, sexual variant and diagnosis.Through this research we pretend to characterize the Emotional Intelligence (EI of people living with HIV. Taking

  11. La Inteligencia Emocional como predictora del Rendimiento Académico: el contexto pluricultural de Ceuta

    Directory of Open Access Journals (Sweden)

    Federico Pulido Acosta

    2015-12-01

    Full Text Available Este trabajo tiene como objetivo fundamental conocer los predictores dela Inteligencia Emocional (IE y el Rendimiento Académico (RA del alumnado de la ciudad de Ceuta, para lo que se contó con 1186 participantes, de 9 centros educativos distintos, que reflejan la pluriculturalidad de la ciudad; de los cuales, el 57.8% son mujeres y el 42.2% varones, y el 58.9% de cultura/religión musulmana y el 41.1% cristianos. Como instrumentos de evaluación se emplearon una adaptación propia del MSCEIT (Test de Inteligencia Emocional de Mayer, Salovey y Caruso, 2009 y las calificaciones de los alumnos. Los resultados obtenidos reflejan niveles medios de Rendimiento Académico, y medio-altos en IE, actuando como predictores del primero las variables sociodemográficas de edad, género, cultura/religión y estatus socio-económico-cultural. Los predictores de la Inteligencia Emocional son la etapa y el estatus. Por otra parte, muestran que existe relación entre Inteligencia Emocional y Rendimiento Académico, actuando cada una como principal predictor de la otra.

  12. Inteligencia emocional en las víctimas de acoso escolar y en los agresores

    Directory of Open Access Journals (Sweden)

    Maite Garaigordobil

    2010-12-01

    Full Text Available El estudio tuvo como principal objetivo analizar las relaciones existentes entre ser víctima de acoso escolar y ser agresor con parámetros asociados a la inteligencia emocional (emotividad, eficacia, pensamiento supersticioso, rigidez, pensamiento esotérico, ilusión. La muestra está constituida por 248 alumnos de 12 a 16 años, 144 varones (58.1% y 104 mujeres (41.9%. Para medir las variables se utilizaron 3 instrumentos de evaluación: el Inventario de Pensamiento Constructivo, la Lista de Chequeo mi vida en la escuela y el Cuestionario de Conductas Antisociales-Delictivas. Los resultados obtenidos confirmaron que: 1 los adolescentes que habían sufrido muchas conductas de intimidación o bullying, tuvieron bajo nivel de inteligencia emocional, baja emotividad, baja autoestima, baja tolerancia a la frustración, baja eficacia, y poca actividad; y 2 Los adolescentes que tenían un nivel alto de conductas antisociales-delictivas mostraban bajo nivel de inteligencia emocional, de eficacia, de actividad, de responsabilidad, y de tolerancia. La discusión gira en torno a la importancia de implementar programas para fomentar la inteligencia emocional con la finalidad de prevenir el acoso escolar.

  13. 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.

  14. Method of detecting fuel failure in FBR type reactor and method of estimating fuel failure position

    International Nuclear Information System (INIS)

    Sonoda, Yukio; Tamaoki, Tetsuo

    1989-01-01

    Noise components in a normal state contained in detection signals from delayed neutron monitors disposed to a coolant inlet, etc. of an intermediate heat exchanger are forecast by self-recurring model and eliminated, and resultant detection signals are monitored thereby detecting fuel failure high sensitivity. Subsequently, the reactor is controlled to a low power operation state and a new self-recurring model to the detection signals from the delayed neutron monitors are prepared. Then, noise components in this state are removed and control rods near the delayed neutron monitors are extracted in a short stroke successively to examine the change of response of the delayed neutron monitors. Accordingly, the failed position for each of the fuels can be estimated at a level of one fuel assembly or a level of several assemblies containing the above-mentioned fuel assembly. Since the fuel failure can be detected at a high sensitivity and the position can be estimated, diffusion of abnormality can be prevented and plant shutdown for fuel exchange can be minimized. (I.S.)

  15. Heat-transfer characteristics of flowing and stationary particle-bed-type fusion-reactor blankets

    Energy Technology Data Exchange (ETDEWEB)

    Nietert, R.E.

    1983-02-01

    The heat-transfer characteristics of flowing and stationary packed-particle beds have recently become of interest in connection with conceptual designs of fusion reactor blankets. A detailed literature survey has shown that the processes taking place in such beds are not fully understood despite their widespread use in the chemical industry and other engineering disciplines for more than five decades. In this study, two experimental investigations were pursued. In the first, a heat-transfer loop was constructed through which glass microspheres were allowed to flow by rgravity at controlled rates through an electrically heated stainless steel tubular test section. In the second, an annular packed bed was constructed in which heat was applied through the outer wall by electric heating of a stainless steel tube. Cooling occurred at the inner wall of the annular bed by flowing air through the central tube. A second air stream was allowed to flow through the voids of the packed bed. An error-minimization technique was utilized in order to obtain the two-dimensional one-parameter effective conductivity for the bed by comparing the experimental and theoretically predicted temperature profiles. Experiments were conducted for various modified Reynolds numbers less than ten.

  16. Designed and operational safety of nuclear power plants equipped with WWER and RMBK type reactors

    International Nuclear Information System (INIS)

    Antonov, B.V.

    1999-01-01

    Presented information demonstrates the actual status of activity on safety assurance at operating NPPs in Russia having WWER and RBMK reactors as well as directions of the Utility and of the supporting enterprises to improve safety of these NPPs. Nuclear power plays an important role in the country's economics, the share of electricity generated being approximately 13%, and in the European part of the country amounting up to 27%. NPPs operate in the base load mode and ensure stable and reliable functioning of the power system and industry as a whole. This is the main reason why Russia is interested in safe and reliable performance of NPPs. Statistics of unscheduled disconnections from the grid for emergency reasons, because of failures important for safety or radiation protection allows to evaluate operating safety as acceptable. Improvement of operation safety issues of Russian NPPs which is one of the outstanding permanent tasks. Cooperation with international organizations and foreign companies plays special role in improving safety of Russian NPPs

  17. Feedback control of a primary pump for safe and stable operation of a PIUS-type reactor

    International Nuclear Information System (INIS)

    Tasaka, K.; Imai, S.; Masaoka, H.; Tamaki, M.; Kukita, Y.

    1993-01-01

    A new automatic pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed for the PIUS-type reactor. This control system maintains the fluid temperature at the axial center of the lower density lock at the average of the fluid temperatures below and above the density lock in order to prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments such as start-up and power ramping tests for the stable normal operation and a loss-of-feedwater test for the safe shutdown in an accident condition, using a small scale atmospheric pressure test loop which simulated the PIUS principle. (orig.)

  18. Feedback control of primary pump using midplane temperature of lower density lock for a PIUS-type reactor

    International Nuclear Information System (INIS)

    Tasaka, Kanji; Haga, Katsuhiro; Tamaki, Masayoshi

    1993-01-01

    A new automatic pump speed control system, using a measurement of the temperature distribution in the lower density lock, is proposed for the PIUS-type reactor. This control system maintains the fluid temperature at the axial center of the lower density lock at the average of the fluid temperatures below and above the lower density lock in order to prevent the poison water from penetrating into the core during normal operation. In a startup test, the effectiveness of this control system to bring the system quickly to the stable state from a very small initial temperature difference between top and bottom of the lower density lock has been confirmed. The effectiveness of the primary pump trip at the limit speed in the control system to shutdown the core power safely in an accident such as a loss-of-feedwater accident with and without the primary loop isolation has also been proved

  19. Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR

    International Nuclear Information System (INIS)

    Sagara, A.; Imagawa, S.; Tanaka, T.; Muroga, T.; Kubota, Y.; Dolan, T.; Hashizume, H.; Kunugi, T.; Fukada, S.; Shimizu, A.; Terai, T.; Mitarai, O.

    2006-01-01

    In terms of engineering feasibility for long-life Flibe blanket in LHD-type reactor FFHR, the Spectral-shifter and Tritium breeder Blanket (STB) concept is evaluated by taking neutron irradiation effects into account under system integration such as Flibe cooling and components replacement. FEM calculations for the neutron wall loading of 1.5 MW/m 2 show that the temperature of the STB armor tile can be kept below 2000 K by optimizing the first metal wall thickness. The heat load experiment on the STB armor mockup confirms feasibility of the temperature control and mechanical joining. Degradation of STB armor tiles due to neutron irradiation requires replacement of them every few years by means of remote handling 'screw coasters' using helical winding, where the replaced tiles are low level wastes. Although the STB concept is feasible within nuclear and thermal properties, more detailed structural optimization is needed including the mechanical and chemical properties

  20. Preventive testing and leakage detection in pipe-lines of steam condensers and generators of a PWR type reactor

    International Nuclear Information System (INIS)

    Canalini, A.; Carvalho, N.C. de

    1985-01-01

    The non-destructive methods: Spum, Helium and Hydrostatic used in leakage detection in condenser pipelines for PWR type reactors are presented. The time, costs, sensitivity, resources necessary and personnel development factors are considered to choose adequated method, in function of nuclear power plant conditions. The leakage tests are applied in pressurized systems or vacuum. Eddy Current testing is used in condensers and steam generators aiming to avoid leakage in these equipments. The spume testing for leakage detection in condenser pipelines - which operation - and hydrostatic testing for leakage detection through reaming with shutdown - were most efficients. The Helium testing applied in pressurized systems or submitted to vacuum systems presented satisfactory results. The Eddy Current testing in condenser and steam generator pipelines reached desired objective, reducing leakage in the first and preserving the integrity in the second. (M.C.K.) [pt

  1. MCTP, a code for the thermo-mechanical analysis of a fuel rod of BWR type reactors (Neutron part)

    International Nuclear Information System (INIS)

    Hernandez L, H.; Ortiz V, J.

    2003-01-01

    In the National Institute of Nuclear Research of Mexico a code for the thermo-mechanical analysis of the fuel rods of the BWR type reactors of the Nucleo electric Central of Laguna Verde is developed. The code solves the diffusion equation in cylindrical coordinates with several energy groups. The code, likewise, calculates the temperature distribution and power distribution in those fuel rods. The code is denominated Multi groups With Temperatures and Power (MCTP). In the code, the energy with which the fission neutrons are emitted it is divided in six groups. They are also considered the produced perturbations by the changes in the temperatures of the materials that constitute the fuel rods, the content of fission products, the uranium consumption and in its case the gadolinium, as well as the plutonium production. In this work there are present preliminary results obtained with the code, using data of operation of the Nucleo electric Central of Laguna Verde. (Author)

  2. Long term immersion test of aluminum alloy AA 6061 used for fuel cladding in MTR type reactors

    International Nuclear Information System (INIS)

    Linardi, Evelina M.; Rodriguez, Sebastian; Haddad, Roberto; Lanzani, Liliana

    2009-01-01

    In this work we present the results of long term immersion tests performed in the aluminum alloy AA 6061, used for fuel cladding in MTR type reactors. The tests were performed at open circuit potential in high purity water (ρ = 18.2 MΩ.cm) and in 10 -3 M NaCl solution. Two kinds of assemblies were studied: simple sheets and artificial crevices, immersed during 6, 12 and 18 months at room temperature. In both media and both assemblies, the aluminum hydroxide phases crystalline bayerite and bohemite were identified. It was found that a kind of localized attack named alkaline attack occurs around the iron-rich intermetallics. These particles were confirmed to control the corrosion of the AA 6061 alloy in an aerated medium. Immersion times for up to 18 months did not increase the oxide growth or the alkaline attack on the AA 6061 alloy. (author)

  3. Steam drum level dynamics in a multiple loop natural circulation system of a pressure-tube type boiling water reactor

    International Nuclear Information System (INIS)

    Jain, Vikas; Kulkarni, P.P.; Nayak, A.K.; Vijayan, P.K.; Saha, D.; Sinha, R.K.

    2011-01-01

    Highlights: → We have highlighted the problem of drum level dynamics in a multiple loop type NC system using RELAP5 code. → The need of interconnections in steam and liquid spaces close to drum is established. → The steam space interconnections equalize pressure and liquid space interconnections equalize level. → With this scheme, the system can withstand anomalous conditions. → However, the controller is found to be inevitable for inventory balance. - Abstract: Advanced Heavy Water Reactor (AHWR) is a pressure tube type boiling water reactor employing natural circulation as the mode of heat removal under all the operating conditions. Main heat transport system (MHTS) of AHWR is essentially a multi-loop natural circulation system with all the loops connected to each other. Each loop of MHTS has a steam drum that provides for gravity based steam-water separation. Steam drum level is a very critical parameter especially in multi-loop natural circulation systems as large departures from the set point may lead to ineffective separation of steam-water or may affect the driving head. However, such a system is susceptible to steam drum level anomalies under postulated asymmetrical operating conditions among the different quadrants of the core like feedwater flow distribution anomaly among the steam drums or power anomaly among the core quadrants. Analyses were carried out to probe such scenarios and unravel the underlying dynamics of steam drum level using system code RELAP5/Mod3.2. In addition, a scheme to obviate such problem in a passive manner without dependence on level controller was examined. It was concluded that steam drums need to be connected in the liquid as well as steam space to make the system tolerant to asymmetrical operating conditions.

  4. Inteligencias múltiples y aprendizaje: Un enfoque comparativo en alumnos de conservatorio

    Directory of Open Access Journals (Sweden)

    Athanassopoulos, Néstor

    2017-01-01

    Full Text Available La Teoría de las inteligencias Múltiples defiende que la competencia cognitiva se describe mejor en términos de un conjunto de habilidades o capacidades mentales que todos poseemos y podemos desarrollar. Método: Este trabajo pretende comparar dos grupos de estudiantes, formados por alumnos que cursan estudios de danza y alumnos que no los cursan, en su nivel de desarrollo de las Inteligencias Múltiples. La muestra está compuesta por 175 personas. Para conocer el nivel de las Inteligencias múltiples se ha empleado el Cuestionario de Detección de las Inteligencias Múltiples para el Alumno de Secundaria (adaptación de McKenzie, 1999. Resultados: los análisis muestran que existe mayor desarrollo de la inteligencia musical por parte de los alumnos que estudian danza en un conservatorio (M=100.14 vs 76.59 p<.05, sin embargo la inteligencia viso-espacial se ve incrementada en los alumnos que no estudian en conservatorio en general (79.30 vs 96.22 . p<.05. Además se divide a la muestra en grupos más pequeños en función del curso. Se observa que en los cursos iniciales la inteligencia musical está más desarrollada en los alumnos de conservatorio y la lógico-matemática y viso-espacial en los alumnos que no acuden al conservatorio. En los cursos superiores, sólo hay diferencias favorables al grupo de danza en la físico-corporal. Conclusión: Se concluye que los estudios de conservatorio pueden influir positivamente en el desarrollo tanto de la inteligencia física y cinestésica como de la inteligencia musical, mientras que podría no incrementar de algún modo el desarrollo de la inteligencia viso-espacial. Abstract: The Theory of Multiple Intelligences argues that cognitive competence is best described in terms of a set of mental abilities or skills that everyone posesses and that can be developed. Method: The aim of this study is to compare the level of development of Multiple Intelligences in two groups of students, one studying

  5. Development of the radiation models of a BWR type reactor and it facility in the SUN-RAH; Desarrollo de modelos de radiacion de un reactor tipo BWR y su instalacion en el SUN-RAH

    Energy Technology Data Exchange (ETDEWEB)

    Barron A, I. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: isbarron@yahoo.com.mx

    2005-07-01

    This work about generation models, transport in processes and radioactive contamination of areas of a BWR central, is an amplification to the project developed in the UNAM to have a support tool in subjects or electric generation courses. It is planned about the implementation of models of radiation generation in a BWR type reactor for complement the functions developed in the University Simulator of Nucleo electric- Boiling water reactor (SUN-RAH) which it has been implemented in Simulink of MatLab and it has a model for the dynamics of one nucleo electric central that presents the main characteristics of the reactor vessel, the recirculation system, steam lines, turbines, generator, condensers and feeding water, defined by the main processes that intervene in the generation of energy of these plants. By this way the radiation monitoring systems for area and process, operate simultaneously with the processes of energy generation, with that is possible to observe the changes that present with respect to the operation conditions of the plant, and likewise to appreciate the radiation transport process through the components of the reactor, steam lines and turbines, for different operation conditions and possible faults that they could be presented during the reactor operation. (Author)

  6. Design analysis of the molten core confinement within the reactor vessel in the case of severe accidents at nuclear power plants equipped with a reactor of the VVER type

    Science.gov (United States)

    Zvonaryov, Yu. A.; Budaev, M. A.; Volchek, A. M.; Gorbaev, V. A.; Zagryazkin, V. N.; Kiselyov, N. P.; Kobzar', V. L.; Konobeev, A. V.; Tsurikov, D. F.

    2013-12-01

    The present paper reports the results of the preliminary design estimate of the behavior of the core melt in vessels of reactors of the VVER-600 and VVER-1300 types (a standard optimized and informative nuclear power unit based on VVER technology—VVER TOI) in the case of beyond-design-basis severe accidents. The basic processes determining the state of the core melt in the reactor vessel are analyzed. The concept of molten core confinement within the vessel based on the idea of outside cooling is discussed. Basic assumptions and models, as well as the results of calculation of the interaction between molten materials of the core and the wall of the reactor vessel performed by means of the SOCRAT severe accident code, are presented and discussed. On the basis of the data obtained, the requirements on the operation of the safety systems are determined, upon the fulfillment of which there will appear potential prerequisites for implementing the concept of the confinement of the core melt within the reactor in cases of severe accidents at nuclear power plants equipped with VVER reactors.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-07-01

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

  8. Relaciones entre afrontamiento del estrés cotidiano, autoconcepto, habilidades sociales e inteligencia emocional

    Directory of Open Access Journals (Sweden)

    Francisco Manuel Morales Rodríguez

    2017-12-01

    Full Text Available Existen menos estudios sobre estrategias de afrontamiento del estrés cotidiano y factores asociados como autoconcepto e inteligencia emocional en nuestro contexto. Este estudio analiza las relaciones entre estrategias de afrontamiento y los factores autoconcepto, habilidades sociales e inteligencia emocional. Se evaluaron las diferentes estrategias de afrontamiento del estrés cotidiano, autoconcepto, habilidades sociales e inteligencia emocional. La muestra se compuso de 154 estudiantes de Educación Secundaria Obligatoria (ESO y de diferentes ciclos formativos. Los resultados no indican diferencias estadísticamente significativas entre los estudiantes procedentes de ESO en comparación con los de ciclos formativos en ninguna de las variables del estudio. Los estudiantes con mayor empleo de las estrategias productivas de afrontamiento (solución activa, búsqueda de información y guía, y actitud positiva tienen mayor puntuación en las variables autoconcepto académico, habilidades sociales e inteligencia emocional. También se encuentran relaciones inversas entre el autoconcepto académico con la estrategia indiferencia; y entre la inteligencia emocional (reparación emocional con la conducta agresiva. Se encuentran efectos directos positivos de las habilidades sociales y algunas dimensiones del autoconcepto sobre estrategias productivas de afrontamiento como búsqueda de información y guía; y efectos directos negativos de las habilidades sociales y el autoconcepto sobre estrategias improductivas de afrontamiento (de las habilidades sociales sobre conducta agresiva y del autoconcepto físico sobre evitación conductual.

  9. Evaluation of the cracking by stress corrosion in nuclear reactor environments type BWR

    International Nuclear Information System (INIS)

    Arganis J, C. R.

    2010-01-01

    The stress corrosion cracking susceptibility was studied in sensitized, solution annealed 304 steel, and in 304-L welded with a heat treatment that simulated the radiation induced segregation, by the slow strain rate test technique, in a similar environment of a boiling water reactor (BWR), 288 C, 8 MPa, low conductivity and a electrochemical corrosion potential near 200 mV. vs. standard hydrogen electrode (She). The electrochemical noise technique was used for the detection of the initiation and propagation of the cracking. The steels were characterized by metallographic studies with optical and scanning electronic microscopy and by the electrochemical potentiodynamic reactivation of single loop and double loop. In all the cases, the steels present delta ferrite. The slow strain rate tests showed that the 304 steel in the solution annealed condition is susceptible to transgranular stress corrosion cracking (TGSCC), such as in a normalized condition showed granulated. In the sensitized condition the steel showed intergranular stress corrosion cracking, followed by a transition to TGSCC. The electrochemical noise time series showed that is possible associated different time sequences to different modes of cracking and that is possible detect sequentially cracking events, it is means, one after other, supported by the fractographic studies by scanning electron microscopy. The parameter that can distinguish between the different modes of cracking is the re passivation rate, obtained by the current decay rate -n- in the current transients. This is due that the re passivation rate is a function of the microstructure and the sensitization. Other statistic parameters like the localized index, Kurtosis, Skew, produce results that are related with mixed corrosion. (Author)

  10. Some physics aspects of the in-core fuel management analysis for CANDU-PHW type reactors

    International Nuclear Information System (INIS)

    Serghiuta, D.; Raica, V.; Gamulescu, D.; Nichita, E.

    1990-01-01

    The primary objective of the ''in-core fuel management'' studies for the CANDU core is to determine fuel loading and fuel replacement strategies which will result in minimum total unit energy cost while operating the reactor in a safe and reliable fashion. Two types of calculations are mainly required in fuel management analyses: a) those used to determine the nominal power and burnup distributions, and b) those used to determine instantaneous distributions which include the time varying fine structure of the power distribution. A method for equilibrium power and burnup distributions determination is presented for the first type of calculations, based on computing the macroscopic cross-sections from the bundle power and burnup history. The computation model presented was programmed into the SERA 3-D code, which was developed at INPR. A series of results for the second type of calculations are presented, which were obtained by applying the random age approximation and the autorefuel methods in determining the instantaneous power distributions. Some improvements are proposed for these models on the basis of the above mentioned results. For the sake of numerical illustration a CANDU slightly enriched uranium core configuration is presented, the physics parameters of which were evaluated on the basis of fuel management analyses. (author). 10 refs, 7 figs, 3 tabs

  11. Rail for inspection/maintenance device in TOKAMAK type container of a thermonuclear reactor

    International Nuclear Information System (INIS)

    Takahashi, Kenji.

    1996-01-01

    A circular rail divided into four arcuate parts for an inspection/maintenance device which runs in a TOKAMAK type container is disposed. Each of the divided rails is supported at the center of the outer surface rotatably by extendable rail supporting shafts. Each of the divided rail is constituted such that it can be contained between limiters disposed at the outer side of the TOKAMAK container when each of the rail support shafts is contracted. With such a constitution, each of the rail support shafts and arcuate rail is contracted and rotated from the outside of the TOKAMAK type container by an actuator. In order to form a circular rail, each of the rail support shafts is extended toward the center of the TOKAMAK type container, and then each of the arcuate rails is rotated into a horizontal state. Then, the joint portions of each of the arcuate rails are connected by using remote controllable locking rods. (I.S.)

  12. Air filtration plants of wall-type for separation of fission iodine in nuclear reactors

    International Nuclear Information System (INIS)

    Stiehl, H.H.; Neumann, M.; Sinhuber, D.

    1976-01-01

    The increasing density of nuclear power stations and increased safety requirements will lead in future to higher flow rates and longer residence times in the adsorption filter layer of the iodine sorption filter plants of nuclear power stations. The safety requirements in the Federal Republic of Germany have been complied with so far in the conventional way by means of duct-type filter constructions. For the higher flow rates and longer residence times necessary in future, we propose a filter construction of wall-type, which complies with the safety regulations of the Federal Republic of Germany. The economic and technical advantages are discussed

  13. Study, analysis, assess and compare the nuclear engineering systems of nuclear power plant with different reactor types VVER-1000, namely AES-91, AES-92 and AES-2006

    International Nuclear Information System (INIS)

    Le Van Hong; Tran Chi Thanh; Hoang Minh Giang; Le Dai Dien; Nguyen Nhi Dien; Nguyen Minh Tuan

    2015-01-01

    On November 25, 2009, in Hanoi, the National Assembly had been approved the resolution about policy for investment of nuclear power project in Ninh Thuan province which include two sites, each site has two units with power around 1000 MWe. For the nuclear power project at Ninh Thuan 1, Vietnam Government signed the Joint-Governmental Agreement with Russian Government for building the nuclear power plant with reactor type VVER. At present time, the Russian Consultant proposed four reactor technologies can be used for Ninh Thuan 1 project, namely: AES-91, AES-92, AES-2006/V491 and AES-2006/V392M. This report presents the main reactor engineering systems of nuclear power plants with VVER-1000/1200. The results from analysis, comparison and assessment between the designs of AES-91, AES-92 and AES-2006 are also presented. The obtained results show that the type AES-2006 is appropriate selection for Vietnam. (author)

  14. Comparison of two different flow types on CO removal along a two-stage hydrogen permselective membrane reactor for methanol synthesis

    International Nuclear Information System (INIS)

    Rahimpour, M.R.; Mazinani, S.; Vaferi, B.; Baktash, M.S.

    2011-01-01

    Carbon monoxide (CO) is a gaseous pollutant with adverse effects on human health and the environment. Industrial chemical processes contribute significantly to CO accumulation in the atmosphere. One of the most important processes for controlling carbon monoxide emissions is the conversion of CO to methanol by catalytic hydrogenation. In this study, the effects of two different flow types on the rate of CO removal along a two-stage hydrogen permselective membrane reactor have been investigated. In the first configuration, fresh synthesis gas flows in the tube side of the membrane reactor co-currently with reacting material in the shell side, so that more hydrogen is provided in the first sections of the reactor. In the second configuration, fresh synthesis gas flows in the tube side of the membrane reactor counter-currently with reacting material in the shell side, so that more hydrogen is provided in the last sections of the reactor. For this membrane system, a one-dimensional dynamic plug flow model in the presence of catalyst deactivation was developed. Comparison between co-current and counter-current configurations shows that the reactor operates with higher conversion of CO and hydrogen permeation rate in the counter-current mode whereas; longer catalyst life is achieved in the co-current configuration. Enhancement of CO removal in the counter-current mode versus the co-current configuration results in an ultimate reduction in CO emissions into the atmosphere.

  15. Retos del liderazgo inteligente y la educación del siglo XXI. Enfoque de las inteligencias multiples

    OpenAIRE

    Zilda Díaz de Plmacher

    2004-01-01

    Hoy el Líder necesita diseñar estrategias innovadoras para desarrollar las inteligencias múltiples en sus seguidores, de manera que pueda solucionar problemas estableciendo relaciones óptimas; es importante adoptar un liderazgo que responda a las exigencias del momento, como proceso intelectual, cognoscitivo y emocional. Las Inteligencias Múltiples es un enfoque que marca pautas en las organizaciones. Representando un modelo de aprendizaje, y desarrollo personal/profesional, que aporta herram...

  16. Sensitivity Study on Thermal Hydraulic Parameters of Research Reactor with Plate Type Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Chae, Hee Taek; Park, Jong Hark; Park, Cheol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2009-05-15

    This paper presents the preliminary core thermal hydraulic characteristics and safety margins for various core flow rates, core pressures, core inlet temperatures and fuel channel powers for a plate type fuel core with 47 MW power. These sensitivity studies were performed to determine the design values for the thermal hydraulic parameters.

  17. Evaluation of plate type fuel options for small power reactors; Avaliacao de alternativas de combustivel tipo placa para reatores de pequeno porte

    Energy Technology Data Exchange (ETDEWEB)

    Andrzejewski, Claudio de Sa

    2005-07-01

    Plate type fuels are generally used in research reactor. The utilization of this kind of configuration improves significantly the overall performance fuel. The conception of new fuels for small power reactors based in plate-type configuration needs a complete review of the safety criteria originally used to conduce power and research reactor projects. In this work, a group of safety criteria is established for the utilization of plate-type fuels in small power reactors taking into consideration the characteristics of power and research reactors. The performance characteristics of fuel elements are strongly supported by its materials properties and the adopted configuration for its fissile particles. The present work makes an orientated bibliographic investigation searching the best material properties (structural materials and fuel compounds) related to the performance fuel. Looking for good parafermionic characteristics and manufacturing exequibility associated to existing facilities in national research centres, this work proposes several alternatives of plate type fuels, considering its utilization in small power reactors: dispersions of UO{sub 2} in stainless steel, of UO{sub 2} in zircaloy, and of U-Mo alloy in zircaloy, and monolithic plates of U-Mo cladded with zircaloy. Given the strong dependency of radiation damage with temperature increase, the safety criteria related to heat transfer were verified for all the alternatives, namely the DNBR; coolant temperature lower than saturation temperature; peak meat temperature to avoid swelling; peak fuel temperature to avoid meat-matrix reaction. It was found that all alternatives meet the safety criteria including the 0.5 mm monolithic U-Mo plate cladded with zircaloy. (author)

  18. Propulsion reactors

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    A nuclear reactor equips the recently constructed French aircraft- carrier Charles-De-Gaulle, in a few months the second nuclear submarine (SNLE) of new generation will be operational. In last october the government launched the program Barracuda which consists of 6 submarines (SNA) whose series head will be operational in 2010. The main asset of nuclear propulsion is to allow an almost unlimited autonomy: soft water, air are produced inside the submarine and the maximum time spent underwater is only limited by human capacity to cope with confinement. CEA has 3 missions concerning country defence. First the designing, the fabrication and the maintenance of weapons, secondly the supplying of fissile materials and thirdly the nuclear propulsion. A new generation of propulsion reactors is being studied and a ground installation involving a test reactor equivalent to that on board is being built. This test reactor (RES) will simulate any type of on-board reactors by adjusting temperature, pressure, flowrate and even equipment such as steam generator. This reactor will validate the technological choices for the Barracuda program. (A.C.)

  19. Assessment of susceptibility of Type 304 stainless steel to intergranular stress corrosion cracking in simulated Savannah River Reactor environments

    International Nuclear Information System (INIS)

    Ondrejcin, R.S.; Caskey, C.R. Jr.

    1989-01-01

    Intergranular stress corrosion cracking (IGSCC) of Type 304 stainless steel rate tests (CERT) of specimens machined was evaluated by constant extension from Savannah River Plant (SRP) decontaminated process water piping. Results from 12 preliminary CERT tests verified that IGSCC occurred over a wide range of simulated SRP envirorments. 73 specimens were tested in two statistical experimental designs of the central composite class. In one design, testing was done in environments containing hydrogen peroxide; in the other design, hydrogen peroxide was omitted but oxygen was added to the environment. Prediction equations relating IGSCC to temperature and environmental variables were formulated. Temperature was the most important independent variable. IGSCC was severe at 100 to 120C and a threshold temperature between 40C and 55C was identified below which IGSCC did not occur. In environments containing hydrogen peroxide, as in SRP operation, a reduction in chloride concentration from 30 to 2 ppB also significantly reduced IGSCC. Reduction in sulfate concentration from 50 to 7 ppB was effective in reducing IGSCC provided the chloride concentration was 30 ppB or less and temperature was 95C or higher. Presence of hydrogen peroxide in the environment increased IGSCC except when chloride concentration was 11 ppB or less. Actual concentrations of hydrogen peroxide, oxygen and carbon dioxide did not affect IGSCC. Large positive ECP values (+450 to +750 mV Standard Hydrogen Electrode (SHE)) in simulated SRP environments containing hydrogen peroxide and were good agreement with ECP measurements made in SRP reactors, indicating that the simulated environments are representative of SRP reactor environments. Overall CERT results suggest that the most effective method to reduce IGSCC is to reduce chloride and sulfate concentrations

  20. Un cambio de actitud a partir del aprendizaje autónomo para potenciar el desarrollo de la inteligencia

    Directory of Open Access Journals (Sweden)

    Ever Mejía L

    2015-10-01

    Full Text Available Al tratar de definir los conceptos de inteligencia, actitudes y aprendizaje autónomo no logramos unanimidad para ninguno de los tres conceptos, pero observamos una relación mutua de influencia entre inteligencia y actitud ya que si organizamos unas creencias y cogniciones a favor de un objeto definido que para el caso es el desarrollo de la inteligencia, podremos obtener una actividad mental de mayor eficiencia y viceversa y si para esta relación se despliega un proceso de aprendizaje autónomo que acentúe la intencionalidad de generar actitudes propicias al desarrollo de la inteligencia el resultado esperado es que se rompa el techo existente en cuanto al desarrollo medio de la inteligencia y se logre un incremento significativo en la inteligencia de los aprendientes.AbstractIn seeking to define the concepts of intelligence, attitudes and self-learning there is not unanimous for any of the three concepts, but we observe a mutual relationship of influence between intelligence and attitude, because, if we organize beliefs and cognitions for a defined purpose that in this case is the development of intelligence, we can get a more efficient mental activity and vice versa, and if for this relationship is displayed a self-learning process that emphasizes the intentionality of auspicious attitudes to the development of intelligence, we can expect that the existing ceiling in developing means of intelligence and achieve a significant increase in the intelligence of the learners.