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Sample records for rez lr-0 reactor

  1. The review of the reactor physics experiments carried out on the LR-0 research reactor NRI Rez plc for reactors of the VVER type

    International Nuclear Information System (INIS)

    Hudec, Frantisek; Jansky, Bohumil; Juricek, Vlastimil; Mikus, Jan; Novak, Evzen; Osmera, Bohumil; Posta, Severin; Rypar, Vojtech; Svadlenkova, Marie

    2010-01-01

    LR-0 is an experimental zero power reactor mainly used for the determination of the neutron-physical characteristics of WWER and PWR type reactor lattices and shielding with UO2 or MOX fuel. Its major assets include capability to design and operate multizone cores, i.e. substituted cores, with an inner inserted part in hexagonal or square geometry (driven by LR-0 standard assemblies); Standard and special supporting plates for mock-up experiments; special supporting plates, which enables the triangular symmetrical assembly arrangement with an arbitrary pitch; Modeling neutron field parameters of power reactors; Wide range benchmarking possibilities, with high reproducibility of the benchmark design parameters; Wide range of measurement techniques including equipment and experienced personal; Flexible rearrangements of the core. The main experiments included: Pin wise flux distribution measurements; VVER-440 and VVER-1000 mock-ups; compact spent fuel storage; space kinetics experiment; core parameters experimental determination; experiment with new design fuel assembly; WWER-440 control assembly influence; and burnable absorber study. International research projects are also described. (P.A.)

  2. Accident dynamics of LR-0 reactor

    International Nuclear Information System (INIS)

    Vorisek, M.; Tinka, I.

    1981-01-01

    The results are given of calculating the accident dynamics of the LR-0 light water experimental zero power reactor. Calculations of the time dependence of power, the total released energy, the temperature of fuel and its cladding were made using program FATRAP for different values of the total inserted reactivity. Using the results, an analysis is made of hypothetic accident states of the LR-0 reactor. The results are shown graphically. (J.B.)

  3. WWER safety investigations on LR-0 reactor

    International Nuclear Information System (INIS)

    Mikus, J.

    2001-01-01

    A set of the measurement needed for the WWER-440 and WWER-1000 reactor lifetime assessment, verification of the methods, codes and input cross section libraries for the WWER reactor pressure vessel exposure evaluation has been performed on the LR-0 experimental reactor. The WWER Mock-ups (engineering benchmarks) has been carried out on the reactor, with the aim to investigate differential neutron spectra for reactor dosimetry purposes. Critical experiments have also been performed to determine the perturbation of the fission density distribution caused by the WWER-440 control assembly. Such assembly, partially inserted in the core, has significant influence on the space power distribution. A wide research program for sub-criticality investigations of the spent nuclear fuel storage has been realized on the LR-0 reactor. A benchmark experiment is realized on the reactor in corresponding geometry for CASTOR 440/84 container for storage and transportation of spent fuel. Critical experiments with new fuel assemblies including various burnable absorbers and different enrichments are performed. A set of critical experiments is performed using the fuel assemblies with 3,6% and 4,4% enrichment, arranged in the WWER-440 type cores with various lattice pitch. The critical high of the moderator level and the moderator level coefficient of reactivity are measured and the effect of the fuel assembly, placed in a hexagonal tube of stainless steel containing boron absorber (ATABOR - STANDARD) is investigated. The obtained results are used for the validation of the codes (MCNP, KENO and SCALE) in the frame of the contract 'Burn-up credit implementation for the storage and transport containers of the spent fuel'. Combined neutron-gamma spectra measurements in the WWER-1000 Mock-up are carried out during 2001

  4. Perturbation measurements in reactor LR-0 and their evaluation

    International Nuclear Information System (INIS)

    Rypar, W.; Faehrmann, K.H.

    1988-07-01

    To investigate space-dependent kinetic effects in reactors of the WWER-1000 type, two central and one eccentric perturbation measurements were performed in the zero power reactor LR-0 of the UJV Rez (CSSR) by trapeze-form movements of an absorber cluster. The measurements were based ona computer aided CAMAC system for the simultaneous data acquisition of 20 spatially distributed neutron detectors and for cluster movement control. The measurements were followed by a detailed evaluation in the ZfK Rossendorf (GDR) with respect to the calculation results of flux response obtained by nodal code HEXDYN3D, the aim of which was to demostrate the limits of the point reactor model and to account for space-dependent effects by approximative methods. A sensitive check of the calculation methods was made possible especially by the eccentric perturbation where the space dependent effects,due to a larger distance of cluster movement, were most significant. (author). 17 figs., 9 refs

  5. WWER-440 control assembly local power peaking investigation on LR-0 reactor

    International Nuclear Information System (INIS)

    Mikus, J.

    2002-01-01

    This paper presents information concerning the local power peaking problem induced by the WWER-440 control assembly and the investigation possibilities on the light water, zero power reactor LR-0 at the Nuclear Research Institute (NRI) Rez plc. A brief description is given about the disposable control assembly model, experimental arrangement and conditions on the LR-0 reactor with regard to the earlier performed investigations as well as to the relevant measurements to be realized in the near future.(abstract)

  6. Rod drop in the LR-0 reactor core comprising 55 fuel assemblies

    International Nuclear Information System (INIS)

    Hadek, J.; Grundmann, U.

    1989-09-01

    Data from the third stage of kinetic measurements on the LR-0 reactor, performed in 1988, were employed for additional calculations using the 3-dimensional neutron kinetics code HEXDYN3D. The reactor consists of subassemblies similar to those in the WWER-1000 (PWR) reactor. The theoretical and experimental results are compared for the time behavior of the neutron flux caused by drop of the control rod cluster in various subassemblies of the reactor. The results demonstrate that the HEXDYN3D code is well suited to the treatment of the space-time behavior of the neutron flux. (author). 21 figs., 2 tabs., 16 refs

  7. Evaluation of activation detectors for the SPHINX project at the LR-0 experimental reactor

    International Nuclear Information System (INIS)

    Lahodova, Zdena; Viererbl, Ladislav; Novak, Evzen; Svadlenkova, Marie; Rypar, Vojtech

    2008-01-01

    This article summarizes the measurements of neutron fluence distributions carried out at the LR-0 research reactor (Czech Republic) in the frame of the SPHINX project. The influence of fluoride-salts or graphite filling in the SR-0 modules on neutron spectrum was studied using activation detectors. The activation detectors (Mn, Ni, In and Au) were evaluated to determine the changes in neutron field. The In and Au detectors were also irradiated with a cadmium cover. Five different configurations of reactor core (EROS) were realized. (authors)

  8. Evaluation of activation detectors for the SPHINX project at the LR-0 experimental reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lahodova, Zdena; Viererbl, Ladislav [Research Center Rez Ltd (Czech Republic); Novak, Evzen; Svadlenkova, Marie; Rypar, Vojtech [Nuclear Power and Safety Division, Nuclear Research Institute Rez plc (Czech Republic)

    2008-07-01

    This article summarizes the measurements of neutron fluence distributions carried out at the LR-0 research reactor (Czech Republic) in the frame of the SPHINX project. The influence of fluoride-salts or graphite filling in the SR-0 modules on neutron spectrum was studied using activation detectors. The activation detectors (Mn, Ni, In and Au) were evaluated to determine the changes in neutron field. The In and Au detectors were also irradiated with a cadmium cover. Five different configurations of reactor core (EROS) were realized. (authors)

  9. Development of measuring system with self-powered neutron detectors for the LR-0 reactor

    International Nuclear Information System (INIS)

    Erben, O.; Horinek, K.; Szasz, Z.

    1989-01-01

    A measuring channel with self-powered detectors was developed for measuring neutron fluxs density in the reactor core. The measuring channel consists of a measuring probe with standard self-powered detectors of Soviet make, a signal pathway, a current/voltage converter and a measuring and recording unit. Neutron flux density in the LR-0 reactor core reaches a maximum of 10 13 m -2 s -1 . Experiments using the channel were carried out both in steady-state operation and after emergency shutdown of the reactor, this from power levels of 2,096 W and 1,830 W. The results of the experiments are tabulated and briefly analyzed. (Z.M.). 4 figs., 3 tabs., 5 refs

  10. WWER-440 local power peaking experiment with/without Hf inserts in the LR-0 reactor

    International Nuclear Information System (INIS)

    Josek, R.; Hudec, F.; Rypar, V.

    2006-01-01

    One of the known issues of the WWER-440 reactors is the control rod coupler induced power peaking in the neighbouring fuel assemblies. The effect has been discovered some years ago and is believed to be the cause of several fuel failures during operation in WWER-440 reactors. The effect itself is due to over-moderation and small absorption in the region of control rod coupler, leading to increase in thermal neutron flux and hence to power flare-up in the neighbouring fuel pins. The fuel vendor tackled the problem by attaching hafnium inserts on the inside of the control assembly box. The experiment performed in the LR-0 reactor was focused on the axial and radial power profiles in the vicinity of the control assembly with and without the hafnium inserts. The results of measurements with zero boron concentration are presented. The hafnium insert causes a decrease in peaking factor of about 30% in selected pins close to the control assembly. The measurements are compared with calculations performed with the MCNP-4C code. The compared variables are: the axial fission density distributions; peking factors and peaking factor decrease due to Hf insert. The MCNP results are accurate with respect to the experimental results. A series of benchmarks is being prepared on the basis of these measurements

  11. Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor

    International Nuclear Information System (INIS)

    Košťál, Michal; Rypar, Vojtěch; Milčák, Ján; Juříček, Vlastimil; Losa, Evžen; Forget, Benoit; Harper, Sterling

    2016-01-01

    Highlights: • A light water critical facility for graphite reactivity worth measurements. • Comparison of calculated and measured k eff . • Effect of graphite description on k eff . - Abstract: Graphite is an often-used moderating material on the basis of its good moderating power and very low absorption cross section. This small absorption cross section permits the use of natural or low-enriched uranium in graphite moderated reactors. Graphite is now being considered as the moderator for Fluoride-salt-cooled High Temperature Reactors (FHR). The critical moderator level was measured for various graphite block configurations in an experimental dry assembly of the LR-0 reactor. Comparisons with experiments were performed between Monte Carlo simulation tools for which satisfactory agreement was obtained with the exception of some systematic discrepancies. The larger discrepancies were observed when using the ENDF/B-VII.0 library. To decrease the uncertainties, based on conservative assumptions, relative comparisons were done. The results provided by the different nuclear data libraries are within 3 sigma interval of experimental uncertainties. It has been determined that differences between the results of calculations are caused by variations in the (n,n), (n,n′), (n,g) reactions and also by various angular distributions, while the (n,g) cross section variations play only a minor role for these configurations.

  12. Determination of power density in VVER-1000 Mock-Up in LR-0 reactor

    Directory of Open Access Journals (Sweden)

    Košál Michal

    2017-01-01

    Full Text Available The pin power density is an important quantity which has to be monitored during the reactor operation, for two main reasons. Firstly, it is part of the limits and conditions of safe operation and, secondly, it is source term in neutron transport calculations used for the adequate assessing of the state of core structures and pressure vessel material. It is often calculated using deterministic codes which may have problems with an adequate definition of boundary conditions in subcritical regions. This may lead to overestimation of real situation, and therefore the validation of the utility codes contributes not only to better fuel utilization, but also to more precise description of radiation situation in structural components of core. Current paper presents methods developed at LR-0 reactor, as well as selected results for pin power density measurement in peripheral regions of VVER-1000 mock-up. The presented data show that the results of a utility diffusion code at core boundary overestimate the measurement. This situation, however satisfactory safe, may lead to unduly conservative approach in the determination of radiation damage of core structures.

  13. Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

    International Nuclear Information System (INIS)

    Brown, Nicholas R.; Mueller, Donald E.; Patton, Bruce W.; Powers, Jeffrey J.

    2016-01-01

    Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 "7LiF-BeF_2) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.

  14. Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Mueller, Donald E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Patton, Bruce W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Powers, Jeffrey J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division

    2016-08-31

    Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 7LiF-BeF2) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.

  15. Complete Sensitivity/Uncertainty Analysis of LR-0 Reactor Experiments with MSRE FLiBe Salt and Perform Comparison with Molten Salt Cooled and Molten Salt Fueled Reactor Models

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Powers, Jeffrey J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mueller, Don [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Patton, Bruce W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-12-01

    In September 2016, reactor physics measurements were conducted at Research Centre Rez (RC Rez) using the FLiBe (2 7LiF + BeF2) salt from the Molten Salt Reactor Experiment (MSRE) in the LR-0 low power nuclear reactor. These experiments were intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems using FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL), in collaboration with RC Rez, performed sensitivity/uncertainty (S/U) analyses of these experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objectives of these analyses were (1) to identify potential sources of bias in fluoride salt-cooled and salt-fueled reactor simulations resulting from cross section uncertainties, and (2) to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a final report on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. In the future, these S/U analyses could be used to inform the design of additional FLiBe-based experiments using the salt from MSRE. The key finding of this work is that, for both solid and liquid fueled fluoride salt reactors, radiative capture in 7Li is the most significant contributor to potential bias in neutronics calculations within the FLiBe salt.

  16. Measurement of 89Y(n,2n) spectral averaged cross section in LR-0 special core reactor spectrum

    Science.gov (United States)

    Košťál, Michal; Losa, Evžen; Baroň, Petr; Šolc, Jaroslav; Švadlenková, Marie; Koleška, Michal; Mareček, Martin; Uhlíř, Jan

    2017-12-01

    The present paper describes reaction rate measurement of 89Y(n,2n)88Y in a well-defined reactor spectrum of a special core assembled in the LR-0 reactor and compares this value with results of simulation. The reaction rate is derived from the measurement of activity of 88Y using gamma-ray spectrometry of irradiated Y2O3 sample. The resulting cross section value averaged in spectrum is 43.9 ± 1.5 μb, averaged in the 235U spectrum is 0.172 ± 0.006 mb. This cross-section is important as it is used as high energy neutron monitor and is therefore included in the International Reactor Dosimetry and Fusion File. Calculations of reaction rates were performed with the MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010, CENDL-3.1 and IRDFF nuclear data libraries. The agreement with uranium description by CIELO library is very good, while in ENDF/B-VII.0 description of uranium, underprediction about 10% in average can be observed.

  17. Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0

    International Nuclear Information System (INIS)

    Košťál, Michal; Švadlenková, Marie; Baroň, Petr; Rypar, Vojtěch; Milčák, Ján

    2016-01-01

    Highlights: • Fission density in partly flooded compact core. • Calculation of fission density axial profile. • Significant calculational under prediction of experimental axial profile. - Abstract: Measurement and calculation of the axial power profile near the boundary of a moderated and non-moderated core is used to analyze the suitability of the neutron-physical process description, mainly the angular cross-section of a water-moderated uranium system. This is also an important issue because it affects the radiation situation above the partly flooded core of a water-moderated reactor. Axial power profiles of various fuel pins irradiated on reactor LR-0 were measured and the results were compared with MCNP6 code calculations using the ENDF/B-VII.0 nuclear data library. The calculated power profile in positions above the moderator level significantly underestimates experimental results. This might be caused by an improper description of the angular distribution of scattered neutrons in a water-moderated uranium system.

  18. Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor

    Directory of Open Access Journals (Sweden)

    Košťál Michal

    2016-01-01

    Full Text Available A set of benchmark experiments was carried out in the full scale VVER-1000 mock-up on the reactor LR-0 in order to validate neutron transport calculation methodologies and to perform the optimization of the shape and locations of neutron flux operation monitors channels inside the shielding of the new VVER-1000 type reactors. Compared with previous experiments on the VVER-1000 mock-up on the reactor LR-0, the fast neutron spectra were measured in the extended neutron energy interval (0.1–10 MeV and new calculations were carried out with the MCNPX code using various nuclear data libraries (ENDF/B VII.0, JEFF 3.1, JENDL 3.3, JENDL 4, ROSFOND 2009, and CENDL 3.1. Measurements and calculations were carried out at different points in the mock-up. The calculation and experimental data are compared.

  19. Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor

    International Nuclear Information System (INIS)

    Košťál, Michal; Veškrna, Martin; Cvachovec, František; Jánský, Bohumil; Novák, Evžen; Rypar, Vojtěch; Milčák, Ján; Losa, Evžen; Mravec, Filip; Matěj, Zdeněk; Rejchrt, Jiří; Forget, Benoit; Harper, Sterling

    2015-01-01

    Highlights: • Neutron spectra measured in graphite and LiF + NaF. • Comparison of calculated and measured neutron spectra. • Effect of 19F on variation between various library calculated spectra. - Abstract: The present paper aims to compare the calculated and measured spectra after insertion of candidate materials for the Molten salt reactor/Fluoride cooled high temperature reactor system concept into the LR-0 reactor. The calculation is realized with MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Additionally, comparisons between the slowing down power of each media were performed. The slowing down properties are important parameters affecting the thickness of moderator media in a reactor

  20. Calculations of fission rate distribution in the core of WWER-1000 mock-up on the LR-0 reactor using alternative methods and comparison with results of measurements

    International Nuclear Information System (INIS)

    Zaritskiy, S.; Kovalishin, A.; Tsvetkov, T.; Rypar, V.; Svadlenkova, M.

    2011-01-01

    General review of experimental and calculation researches on WWER-440 and WWER-1000 mock-ups on the reactor LR-0 was introduced on the twentieth Symposium AER. The experimental core fission rate distribution was obtained by means of gamma-scanning of the fuel pins - 140La single peak (1596 keV) measurements and wide energy range (approximately 600-900 keV) measurements. Altogether from 260 to 500 fuel pins were scanned in different experiments. The measurements were arranged in the middle of the fuel (the active part of pin). Pin-to-pin calculations of the WWER-1000 mock-up core fission rate distribution were performed with several codes: Monte Carlo codes MCU-REA/2 and MCNPX with different nuclear data libraries, diffusion code RADAR (63 energy groups library) and code SVL based on Surface Harmonics Method (69 energy groups). Calculated data are compared with experimental ones. The obtained results allow developing the benchmark for core calculations methodologies, evaluating and validating source reliability for the out-of-core (inside and outside pressure vessel) neutron transport calculations. (Authors)

  1. Research reactors spent fuel management in the Nuclear Research Institute Rez

    International Nuclear Information System (INIS)

    Rychecky, J.

    2001-01-01

    In Czech Republic 3 research and testing nuclear reactors are operated at present time, with the biggest one being the Nuclear Research Institute (NRI) reactor LVR-15, operated with maximum power 10 MW. This reactor serves as a radiation source for material testing, producing of ionizing radiation sources, theoretical studies, and, most recently, for boron neutron capture therapy. Another NRI reactor LR-0 is a reactor of zero power used mainly for the studies of WWER 1000 spent fuel criticality. For training of students the reactor called VRABEC (VR-1), operated also with very low power, serves since 1990 at the Faculty of Nuclear Engineering, of Czech Technical University. The similar testing type reactor (SR-0), already decommissioned, was also used since 1974 to 1989 in Skoda, Nuclear Machinery, Plzen. This contribution summarizes the present state of the spent fuel (SF) management of these nuclear reactors. As the SF management is different for very low or zero power reactors and power reactors, the first type will be only briefly discussed, and then the main attention will be devoted to SF management of the NRI experimental reactor LVR-15

  2. Research reactors spent fuel management in the Nuclear Research Institute Rez

    Energy Technology Data Exchange (ETDEWEB)

    Rychecky, J. [Nuclear Research Institute, 25068 Rez (Czech Republic)

    2001-07-01

    In Czech Republic 3 research and testing nuclear reactors are operated at present time, with the biggest one being the Nuclear Research Institute (NRI) reactor LVR-15, operated with maximum power 10 MW. This reactor serves as a radiation source for material testing, producing of ionizing radiation sources, theoretical studies, and, most recently, for boron neutron capture therapy. Another NRI reactor LR-0 is a reactor of zero power used mainly for the studies of WWER 1000 spent fuel criticality. For training of students the reactor called VRABEC (VR-1), operated also with very low power, serves since 1990 at the Faculty of Nuclear Engineering, of Czech Technical University. The similar testing type reactor (SR-0), already decommissioned, was also used since 1974 to 1989 in Skoda, Nuclear Machinery, Plzen. This contribution summarizes the present state of the spent fuel (SF) management of these nuclear reactors. As the SF management is different for very low or zero power reactors and power reactors, the first type will be only briefly discussed, and then the main attention will be devoted to SF management of the NRI experimental reactor LVR-15.

  3. The research of materials and water chemistry for supercritical water-cooled reactors in Research Centre Rez

    International Nuclear Information System (INIS)

    Zychova, Marketa; Fukac, Rostislav; Vsolak, Rudolf; Vojacek, Ales; Ruzickova, Mariana; Vonkova, Katerina

    2012-09-01

    Research Centre Rez (CVR) is R and D company based in the Czech Republic. It was established as the subsidiary of the Nuclear Research Institute Rez plc. One of the main activities of CVR is the research of materials and chemistry for the generation IV reactor systems - especially the supercritical water-cooled one. For these experiments is CVR equipped by a supercritical water loop (SCWL) and a supercritical water autoclave (SCWA) serving for research of material and Supercritical Water-cooled Reactor (SCWR) environment compatibility experiments. SCWL is a research facility designed to material, water chemistry, radiolysis and other testing in SCWR environment, SCWA serves for complementary and supporting experiments. SCWL consists of auxiliary circuits (ensuring the required parameters as temperature, pressure and chemical conditions in the irradiation channel, purification and measurements) and irradiation channel (where specimens are exposed to the SCWR environment). The design of the loop is based on many years of experience with loop design for various types of corrosion/water chemistry experiments. Designed conditions in the test area of SCWL are 600 deg. C and 25 MPa. SCWL was designed in 2008 within the High Performance Light Water Reactor Phase 2 project and built during 2008 and 2009. The trial operations were performed in 2010 and 2011 and were divided into three phases - the first phase to verify the functionality of auxiliary circuits of the loop, the second phase to verify the complete facility (auxiliary circuits and functional irradiation channel internals) and the third phase to verify the feasibility of corrosion tests with the complete equipment and specimens. All three trial operations were very successful - designed conditions and parameters were reached. (authors)

  4. Calculation with MCNP of capture photon flux in VVER-1000 experimental reactor.

    Science.gov (United States)

    Töre, Candan; Ortego, Pedro

    2005-01-01

    The aim of this study is to obtain by Monte Carlo method the high energy photon flux due to neutron capture in the internals and vessel layers of the experimental reactor LR-0 located in REZ, Czech Republic, and loaded with VVER-1000 fuel. The calclated neutron, photon and photon to neutron flux ratio are compared with experimental measurements performed with a multi-parameter stilbene detector. The results show clear underestimation of photon flux in downcomer and some overestimation at vessel surface and 1/4 thickness but a good fitting for deeper points in vessel.

  5. Safety operation of training reactor VR-1

    International Nuclear Information System (INIS)

    Matejka, K.

    2001-01-01

    There are three nuclear research reactors in the Czech Republic in operation now: light water reactor LVR-15, maximum reactor power 10 MW t , owner and operator Nuclear Research Institute Rez; light water zero power reactor LR-0, maximum reactor power 5 kW t , owner and operator Nuclear Research Institute Rez and training reactor VR-1 Sparrow, maximum reactor power 5 kW t , owner and operate Faculty of Nuclear Sciences and Physical Engineering, CTU in Prague. The training reactor VR-1 Vrabec 'Sparrow', operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly it is designed for training the students of Czech universities, preparing the experts for the Czech nuclear programme, as well as for certain research work, and for information programmes in the nuclear programme, as well as for certain research work, and for information programmes in sphere of using the nuclear energy (public relations). (author)

  6. VVER-440 and VVER-1000 reactor dosimetry benchmark - BUGLE-96 versus ALPAN VII.0

    International Nuclear Information System (INIS)

    Duo, J. I.

    2011-01-01

    Document available in abstract form only, full text of document follows: Analytical results of the vodo-vodyanoi energetichesky reactor-(VVER-) 440 and VVER-1000 reactor dosimetry benchmarks developed from engineering mockups at the Nuclear Research Inst. Rez LR-0 reactor are discussed. These benchmarks provide accurate determination of radiation field parameters in the vicinity and over the thickness of the reactor pressure vessel. Measurements are compared to calculated results with two sets of tools: TORT discrete ordinates code and BUGLE-96 cross-section library versus the newly Westinghouse-developed RAPTOR-M3G and ALPAN VII.0. The parallel code RAPTOR-M3G enables detailed neutron distributions in energy and space in reduced computational time. ALPAN VII.0 cross-section library is based on ENDF/B-VII.0 and is designed for reactor dosimetry applications. It uses a unique broad group structure to enhance resolution in thermal-neutron-energy range compared to other analogous libraries. The comparison of fast neutron (E > 0.5 MeV) results shows good agreement (within 10%) between BUGLE-96 and ALPAN VII.O libraries. Furthermore, the results compare well with analogous results of participants of the REDOS program (2005). Finally, the analytical results for fast neutrons agree within 15% with the measurements, for most locations in all three mockups. In general, however, the analytical results underestimate the attenuation through the reactor pressure vessel thickness compared to the measurements. (authors)

  7. Santiago Pérez Triana

    Directory of Open Access Journals (Sweden)

    Sergio Elías Ortíz

    1958-09-01

    Full Text Available El nombre de Santiago Pérez Triana, aunque suena en el ambiente colombiano, algunas veces confundido con el de su ilustre padre, como el de un escritor notable y hasta como un orador de fama internacional, no se lo conoce, a nuestro juicio, en todo lo que vale y pesa, no digamos en el dominio de las letras castellanas, pero ni siquiera en su propia patria de origen, excepto en pequeño círculo intelectuales capacitado para valorar a conciencia los quilates de pensador de este hombre prodigioso que paseó su inteligencia sobre temas, diversos , con capacidad múltiple, e ilustración inagotable.

  8. Renewable Energy Zone (REZ) Transmission Planning Process

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Nathan [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-03-08

    A REZ is a geographical area that enables the development of profitable, cost-effective, grid-connected renewable energy (RE). The REZ Transmission Planning Process is a proactive approach to plan, approve, and build transmission infrastructure connecting REZs to the power system which helps to increase the share of solar, wind and other RE resources in the power system while maintaining reliability and economics, and focuses on large-scale wind and solar resources that can be developed in sufficient quantities to warrant transmission system expansion and upgrades.

  9. New developments in instrumentation for strain scanning in NPI Rez

    CERN Document Server

    Vrána, M; Lukás, P; Dubsky, J; Wagner, V

    2000-01-01

    Two high-resolution neutron diffractometers dedicated to strain /stress investigations in polycrystalline materials are routinely operated at the medium-power reactor LVR-15 in Rez and are also opened for external users. Good luminosity of the diffractometers and a sufficiently high-resolution (FWHM of the instrumental Delta d/d - profile can be less than 2*10/sup -3/ at d/sub hkl/=0.2 nm) permit investigations of both the macro- and microstrains in the sample gauge volumes of several cubic millimetres. Excellent properties and abilities of the neutron diffraction strain scanners are documented by some results of experimental measurements. (11 refs).

  10. Santiago Pérez: el dramaturgo

    Directory of Open Access Journals (Sweden)

    Marina Lamus Obregón

    2001-09-01

    Full Text Available La vida de Santiago Pérez como escritor de poemas y dramas fue muy corta y pertenece a sus años de juventud. En la edad madura esta incursión la consideró un pecado que lo hacía ruborizar: por ello compraba los libros editados por la generosidad de Lorenzo María Lleras y los quemaba. Y es que el "señorito" Santiago Pérez, alumno aventajado del colegio del Espíritu Santo y después profesor de literatura y filosofía, recibió también de su maestro, don Lorenzo María Lleras, influencia política, literaria y teatral.

  11. El genio maligno de Suárez: Suárez y Descartes

    OpenAIRE

    Baciero Ruiz, Francisco Tadeo

    2007-01-01

    [ES] Tradicionalmente se ha considerado la filosofía cartesiana como un comienzo casi absoluto en la historia de la Filosofía. Sin embargo, las conocidas hipótesis del “genio maligno” y del “Dios engañador”, parte fundamental del artificio de la “duda metódica” en las Meditaciones metafísicas, se encuentran en la Disputación metafísica 9 de Suárez (la única mención de Suárez en todo Descartes, precisamente en las “Respuestas” a las Meditaciones). Parece claro, a partir de la correspondencia d...

  12. y Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    Socorro Arzaluz Solano

    2006-01-01

    Full Text Available El artículo aborda la aplicación del Programa Hábitat, diseñado por el Gobierno de Vicente Fox en 2002, en dos ciudades fronterizas: Nogales, Sonora, y Ciudad Juárez, Chihuahua. Se analiza la implantación del programa atendiendo sus particularidades, entre otros aspectos, se señalan los diferentes agentes que intervinieron en la ejecución de Hábitat, que pese a la claridad de las reglas, fueron diferentes en cada caso. También, las forma s de participación ciudadana promovidas por los gobiernos locales en ambos casos. Se presentan una reflexión final sobre el desarrollo de Hábitat en la frontera norte, y algunas recomendaciones.

  13. Fernando Cassinello Pérez, polyhedral architect

    Directory of Open Access Journals (Sweden)

    M. Centellas Soler

    2017-03-01

    Full Text Available The work of architect Fernando Cassinello Pérez (Almería, 1928-Madrid, 1975 rests on three pillars: architectural production focused on the design and construction of housing and hotel establishments, academic activity as Professor of Construction at the Escuela de Arquitectura de Madrid, and research concern developed in the IETcc of which he became director, and exercised as an author of books and research papers, as disseminator lecturer, speaker at major conferences or as an active member of international associations linked to construction with concrete. This article will review his prolific activity as polyhedral architect and will find interesting works that designed and built by relying on extensive contemporary and international architectural culture.

  14. Introduction of hot cell facility in research center Rez - Poster

    International Nuclear Information System (INIS)

    Petrickova, A.; Srba, O.; Miklos, M.; Svoboda, P.

    2015-01-01

    This poster presents the hot cell facility which is being constructed as part of the SUSEN project at the Rez research center (Czech Republic). Within this project a new complex of 10 hot cells and one semi-hot cell will be built. There will be 8 gamma hot cells and 2 alpha hot cells. In each hot cell a hermetic, removable box made of stainless steel will home different type of devices. The hot cells and semi hot cell will be equipped with devices for processing samples (cutting, welding, drilling, machining) as well as equipment for testing (sample preparation area, stress testing machine, fatigue machine, electromechanical creep machine, high frequency resonance pulsator...) and equipment for studying material microstructure (nano-indenter with nano-scratch tester and scanning electron microscope). An autoclave with water loop, installed in a cell will allow mechanical testing in control environment of water, pressure and temperature. A scheme shows the equipment of each cell. This hot laboratory will be able to cover all the process to study radioactive materials: receiving the material, the preparation of the samples, mechanical testing and microstructure observation. Our hot cells will be close to the research nuclear reactor LVR-15 and new irradiation facility (high irradiation by cobalt source) is planned to be built within the SUSEN project

  15. Suárez on the Lower External Senses

    Czech Academy of Sciences Publication Activity Database

    Heider, Daniel

    2016-01-01

    Roč. 64, Suppl. (2016), s. 81-102 ISSN 0015-1831 Institutional support: RVO:67985955 Keywords : Suárez * Aristotle * the lower external senses * sensible species Subject RIV: AA - Philosophy ; Religion

  16. Consideraciones sobre Infortunios de Alonso Ramírez

    Directory of Open Access Journals (Sweden)

    Leonor Taiano

    2010-12-01

    Full Text Available This article attempts to provide new perspectives for approaching the study of Infortunios de Alonso Ramírez. Several researches about the text have given to Sigüenza y Góngora a character of strangeness to it, which would reduce him to the role of mere amanuensis, indicating that the discursive elaboration belongs to Ramirez. In view of that, I have performed a textual analysis, supported on the book's title and the final passage of the account, that I consider important elements that can offer a new perception on this issue. I base my research, additionally, on the study of its context of publication under the patronage of the New Spain viceroy, as well as the similarities of Infortunios de Alonso Ramírez with other contemporary texts.

  17. Vitoria y Suárez: el Derecho Internacional

    Directory of Open Access Journals (Sweden)

    Adolfo J. Sánchez Hidalgo

    2017-09-01

    Full Text Available Este artículo pretende mostrar la convivencia de dos estructuras de pensamiento en la escolástica española y, especialmente, en Suárez. Vitoria presenta una visión comunitaria del orden internacional y sus enseñanzas serán transmitidas a Suárez, quien, al contrario, presenta una visión societaria del orden internacional. Esta diferencia no es una casualidad, sino un auténtico cambio de paradigma en el sabio granadino, que hace de él un autor más próximo a la modernidad que a la tradición escolástica. Gracias a un estudio comparado mostraremos el punto de inflexión que supone Suárez en el tránsito hacia la modernidad y su idea de un orden mundial fundado en una sociedad de Estados.

  18. Conversando sobre sexualidades Entrevista a Gloria Careaga Pérez

    OpenAIRE

    Fernández Carvajal, Doris

    2015-01-01

    Gloria Careaga Pérez: cuenta con una Maestría en Psicología Social, en la Universidad Nacional Autónoma de México (UNAM) y Licenciatura en Psicología, en el Instituto Tecnológico de Estudios Superiores de Occidente. Se desempeña como profesora de la Facultad de Psicología de Universidad Nacional Autónoma de México (UNAM). Es activista feminista, con una amplia participación en foros y conferencias internacionales en defensa de los derechos humanos de las personas sexualmente diversas. Integra...

  19. Pablo Rodríguez Pérez (1976 - 2016)

    CERN Multimedia

    2016-01-01

    It is with great sadness that we announce the sudden loss of Pablo Rodríguez Pérez, a physicist on the LHCb Experiment, who died in Manchester on 1st July 2016.   Pablo Rodríguez Pérez. Pablo obtained his Bachelor of Science in Physics at the Universidade de Santiago de Compostela (USC) in 2003, specialising in electronics before going on to work in industry. He joined the LHCb experiment in 2007, undertaking his Master of Science at USC on the optimisation of readout electronics for the Inner Tracker. He then continued his studies with a PhD, becoming the principal author for the experiment control system of the Silicon Tracker. After the commissioning of the LHCb experiment he moved his attention to the LHCb upgrade, performing the first investigation of prototypes for the upgrade of the vertex locator (VELO). Following his PhD from USC, Cum Laude, he joined the University of Manchester in 2013 to work further on the VELO Upgrade. Pablo took ...

  20. La potestad tributaria en Francisco Suárez

    Directory of Open Access Journals (Sweden)

    Luis Carlos Amezúa Amezúa

    2017-09-01

    Full Text Available Francisco Suárez es el teólogo más relevante de la escuela española de derecho natural o Escuela de Salamanca en sentido amplio. Según piensa, el derecho de imponer tributos justos reside en exclusiva en la autoridad suprema, sin necesitar el consentimiento de las Cortes. El Estado tiene ese poder de establecer leyes tributarias para asegurar la paz, el orden y el buen gobierno de la comunidad. Es el poder más importante entre todas las facultades propias de la soberanía, pero debe respetar las exigencias de un impuesto justo: además de la autoridad legítima, una causa justa y distribución proporcional. En este artículo, desarrollaremos la doctrina de Suárez, su interpretación acerca de la duda probable sobre la injusticia del impuesto, y su aceptación de los impuestos sobre el consumo. Todos estos razonamientos iban dirigidos a fortalecer al gobernante, que debe actuar dentro de un marco ético respetuoso con el bien común.

  1. Technical Potential Assessment for the Renewable Energy Zone (REZ) Process: A GIS-Based Approach

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Nathan [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Roberts, Billy J [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-04-05

    Geographic Information Systems (GIS)-based energy resource and technical potential assessments identify areas capable of supporting high levels of renewable energy (RE) development as part of a Renewable Energy Zone (REZ) Transmission Planning process. This document expands on the REZ Process to aid practitioners in conducting GIS-based RE resource and technical potential assessments. The REZ process is an approach to plan, approve, and build transmission infrastructure that connects REZs - geographic areas that have high-quality RE resources, suitable topography and land-use designations, and demonstrated developer interest - to the power system. The REZ process helps to increase the share of solar photovoltaic (PV), wind, and other resources while also maintaining reliability and economics.

  2. Decommissioning of evaporation technology for processing liquid radioactive waste in UJV Rez, a. s

    International Nuclear Information System (INIS)

    Tous, M.; Otcovsky, T.; Podlaha, J.

    2015-01-01

    The UJV Rez, a. s. is the main leader in processing institutional radioactive waste (RAW) in the Czech Republic and the Waste Management Department has been established since the research reactor VVR-S (now LVR-15) was put in operation. Due to the large activities in nuclear research and engineering in the past, a big capacity of waste management technologies was needed. The low pressure compactor for volume reduction of solid RAW, as well as chemical pre-treatment technology of liquid RAW were installed and later the evaporation technology for effective processing the liquid RAW with the cementation and bituminization unit for final conditioning of concentrated liquid RAW were used. During the years of research reactor operation and research activities in UJV Rez, a. s. there were two installed evaporation technologies in row. After the latest evaporator lifetime, changes in liquid RAW production and together with higher decontamination factor requirements, this technology was decided to be decommissioned. The decommissioned evaporation technology was installed and put in operation in 1991. This technology was used for processing liquid aqueous RAW produced from internal research activities and of course for external producers and institutions (e.g. universities, medicine, research institutes, industry). The approved decommissioning plan was prepared and the licence for immediate decommissioning was obtained in 2012. Then the decommissioning project started. The preparing stages as dosimetric survey, expected material balance and of course initial decontamination activities were performed. Evaporation technology dismantling and processing the arising RAW were done by the internal staff of Waste Management Department. The total volume of produced RAW was 49,5 m 3 of RAW. The secondary liquid RAW (from decontamination) of amount 1,4 m 3 , contaminated sludge of amount 0,5 m 3 , solid RAW (construction steel) of amount 39,1 m 3 , solid compressible RAW (protective

  3. 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.)

  4. 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.)

  5. System of institutional radioactive waste management in the Nuclear Research Institute Rez plc

    International Nuclear Information System (INIS)

    Podlaha, J.; Burian, P.

    2005-01-01

    The Nuclear Research Institute Rez plc (NRI) is a leading institution in the area of nuclear Research and Development in the Czech Republic. The NRI has had a dominant position in the nuclear programme since it was established in 1955 as a state-owned research organization and it has developed to its current status. In December 1992 the NRI has been transformed into a joint-stock company. The NRI's activity encompasses nuclear physics, chemistry, nuclear power, experiments at the research reactor and many other topics. Main issues addressed in the NRI in the past decades were concentrated on research, development and services provided to the nuclear power plants operating WWER reactors, development of chemical technologies for fuel cycle and irradiation services to research and development in the industrial sector, agriculture, food processing and medicine. At present the research activities are mainly targeted to assist the State Office for Nuclear Safety -the nuclear safety regulating body, power plant operator and nuclear facilities contractors. Significant attention is also paid to the use of nuclear technology outside the nuclear power sector, providing a wide range of services to industry , medicine and the preparation of radiopharmaceuticals. NRI operates two research nuclear reactors and another facilities such as a hot cell facility , research laboratories, technology for radioactive waste (RAW) management, 60 Co irradiators, an electron accelerator, etc. In this paper the Centre of RAW management, system of RAW management, facilities for RAW management as well as decontamination and decommissioning activities of the NRI are presented. The NRI provides complex services in the area of RAW management and has gained many experience and full qualification not only in this area but also in the area of decontamination and decommissioning and spent fuel management. The NRI guarantees safe RAW and spent fuel management. (authors)

  6. LALR(1) : LL(1) = LR(0) : LL(0)

    NARCIS (Netherlands)

    Kruseman Aretz, F.E.J.; Emde Boas, van P.; Hemker, P.W.; Hoffman, W.; Houwen, van der P.J.; Pfluger, P.R.

    1992-01-01

    It is shown that LL(l) and LALR(l) acceptors can be obtained by restricting the action tables of the corresponding LL(O) and LR(O) acceptors to those entries that are accessed in at least one accepting sequence (of a sentence from the language). It follows that a number of properties that are easily

  7. Académico Fernando Serpa Flórez

    Directory of Open Access Journals (Sweden)

    José Felix Patiño Restrepo

    2001-12-01

    Full Text Available

    Brillante, generoso, noble, escritor prolífico, un completo caballero, Fernando Serpa Flórez fue el prototipo del médico intelectual, humanista y humanitario. Su vocación por la salud pública lo llevó a ocupar altos cargos en el ramo: Secretario General del Ministerio de Salud, Secretario de Salud de Bogotá, Director del Instituto Nacional de Salud, Director del Ministerio de Salud y Ministro Encargado de Salud. Como Asesor de la Organización Mundial de la Salud, trabajó en Afganistán en el programa de erradicación de la viruela.
    Fue médico, jefe de Ecopetrol. Desde su elevada posición como Magistrado del Tribunal Nacional de Etica Médica, y con el ejemplo de su vida personal, como uno de los miembros más distinguidos de la Academia Nacional de Medicina, Fernando Serpa Flórez ocupa un lugar de particular distinción en la historia
    contemporánea de la medicina colombiana.

    Tuve el privilegio de su amistad por más de medio siglo, como condiscípulo en la Facultad de Medicina de la Universidad Nacional y luego a través de los años compartiendo afectos e intereses. Me acompaño con talento, lealtad y dedicación como Director del Ministerio cuando ocupé el cargo de Ministro en el Gobierno del eximio Presidente Guillermo León Valencia. Para quienes lo conocimos de cerca, este vástago de
    una brillante familia de médicos, sobrevivirá en nuestra memoria y en sus obras...

  8. Remediation of old environmental liabilities in the Nuclear Research Institute Rez plc

    International Nuclear Information System (INIS)

    Svoboda, Karel; Podlaha, Josef

    2011-01-01

    The Nuclear Research Institute Rez plc (NRI) after 55 years of activities in the nuclear field produced some environmental liabilities that shall be remedied. There are three areas of remediation: (1) decommissioning of old obsolete facilities (e.g. decay tanks, RAW treatment technology, special sewage system), (2) processing of RAW from operation and dismantling of nuclear facilities, and (3) elimination of spent fuel from research nuclear reactors operated by the NRI. The goal is to remedy the environmental liabilities and eliminate the potential negative impact on the environment. Remediation of the environmental liabilities started in 2003 and will be finished in 2014. The character of the environmental liabilities is very specific and requires special remediation procedures. Special technologies are being developed with assistance of external subcontractors. The NRI has gained many experiences in the field of RAW management and decommissioning of nuclear facilities and will use its facilities, experienced staff and all relevant data needed for the successful realization of the remediation. The most significant items of environmental liabilities are described in the paper together with information about the history, the current state, the progress, and the future activities in the field of remediation of environmental liabilities in the NRI. (author)

  9. Research and development of pyrochemical technologies for ADTT systems in NRI Rez plc

    International Nuclear Information System (INIS)

    Uhlir, J.

    1999-01-01

    The activities within the Czech national Partitioning and Transmutation program are oriented mainly toward the following areas: (i) ADS flowsheeting working out a proposal for a suitable technological flowsheet for treating spent fuel into a form fitted for transmutation reactor, including separation procedures before transmutation (Front-end) and separation processes after passage of fuel through the transmutor (Back-end). (ii) Technological research into the uranium component separation from spent fuel by the Fluoride Volatility Method semi-pilot-plant technological research based on the application of experience from spent fuel fluoride reprocessing. (iii) Laboratory research into electro-separation methods for the separation of fission products, plutonium and minor actinides from the fluoride melt. Selection of a suitable matrix composition of fluoride melts based on studies of their physicochemical properties and design of laboratory electro-separation facility. (iv) Development of materials and equipment for molten fluoride salts based ADS technologies, i.e. construction materials development, research into the corrosion resistance and development of equipment for molten fluoride salts technologies. The NRI Rez plc cooperates in this area with the SKODA Nuclear Machinery company

  10. Renewable Energy Zone (REZ) Transmission Planning Process: A Guidebook for Practitioners

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Nathan [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Flores-Espino, Francisco [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Hurlbut, David J. [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2017-09-05

    Achieving clean energy goals may require new investments in transmission, especially if planners anticipate economic growth and increased demand for electricity. The renewable energy zone (REZ) transmission planning process can help policymakers ensure their infrastructure investments achieve national goals in the most economical manner. Policymakers, planners, and system operators around the world have used variations of the REZ process to chart the expansion of their transmission networks and overcome the barriers of traditional transmission planning. This guidebook seeks to help power system planners, key decision makers, and stakeholders understand and use the REZ transmission planning process to integrate transmission expansion planning and renewable energy generation planning.

  11. El doctor Moreno Pérez y el anopheles crucians

    Directory of Open Access Journals (Sweden)

    Facultad de Medicina Revista

    1943-03-01

    Full Text Available En el año de 1933, con ocasión del conflicto del Amazonas, el doctor Ignacio Moreno·Pérez trabajó como médico de sanidad en la hoya del río Caquetá. Prosiguiendo sus estudios sobre paludismo y mosquitos transmisores a que dedicó gran parte de su meritoria vida, practicó una inspección entomológica de las cercanías de Florencia, capital de la comisaria del Caquetá, y encontró una raza en aguas salobres de Anopheles crucians. El hallazgo comunicado por él en el informe de 1934 de la comisión de paludismo del valle del Magdalena, (Estudios de Paludismo en el Valle del Magdalena, Departamento Nacional de Higiene, Sección de Sanidad Rural, Bogotá editorial de "Cromos", 1934, despertó mucho interés y fué objeto de controversias, porque conforme a los estudios de Howard, Dyar y Knab (1917, la localización del Anopheles crucians era casi hiperbórea, por encima del paralelo 25 en la América del Norte y solamente se había logrado ver además en Cuba y Jamaica.

  12. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

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

  13. 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.)

  14. The language of human law in the thought of Francisco Suárez

    Directory of Open Access Journals (Sweden)

    Fernando Centenera Sánchez-Seco

    2018-05-01

    Full Text Available The subject of this article is the language of human law in the thought of Francisco Suárez. Its chief focus is on the Treatise on Laws and on God the Lawgiver and its views on the prescriptive nature of legislative language, written and spoken language, the lexical-semantic level, and linguistic clarity from the viewpoints of convenience, the essence of the law and justice. The issues Suárez deals with in relation to these points have continued to attract attention up to the present day, and a reading of the Treatise confirms the impression that some of them are still valid. Accordingly, as well as setting out, describing and offering a guide to understanding Suárez ideas, the article offers a comparative and contemplative analysis of them, without forgetting that their author belonged to the early modern period.

  15. Remediation of the old environmental liabilities in the Nuclear Research Institute Rez. Situation at the end of 2008

    Energy Technology Data Exchange (ETDEWEB)

    Kovarik, Petr; Svoboda, Karel; Podlaha, Josef [Nuclear Research Institute Rez (Czech Republic)

    2010-10-15

    The Nuclear Research Institute Rez (NRI) has been a leading institution in the area of R and D (Research and Development) in the Czech Republic. The NRI has had a dominant position in the nuclear programme of the former Czechoslovakia since it was established in 1955. In December 1992 the NRI has been transformed into a joint-stock company. The Institute's activity encompasses nuclear physics, radiochemistry, experiments at the research reactor and many other topics. Main issues addressed in the NRI in the past decades were concentrated on research, development and services provided to the VVER reactors, development of chemical technologies for fuel cycle and irradiation services. Currently, the research activities are mainly targeted to assist the State Office for Nuclear Safety. Significant attention is also paid to the use of nuclear technology outside the nuclear power sector, providing a wide range of services to industry, medicine and the preparation of radiopharmaceuticals. NRI operates 2 research nuclear reactors, hot cell facility, research laboratories, and technology for radioactive waste management, radionuclide irradiators, an electron accelerator and others. After 50 years of activities in the nuclear field, there have been many environmental liabilities that are being remedied in the NRI. There are 3 areas of these remediation activities: - decommissioning of old obsolete facilities, - processing of RAW resulting from operation and dismantling of nuclear facilities, and - elimination of spent fuel from research nuclear reactors. The goal is to remedy the environmental liabilities and eliminate the potential negative impact on the environment. Remediation of the environmental liabilities started in 2003 and should be finished in 2014. (orig.)

  16. SIMÓN TALAVERA SUÁREZ [Material gráfico

    OpenAIRE

    Anonymous

    2002-01-01

    RETRATO DE SIMÓN TALAVERA SUÁREZ CON UN ENJAMBRE DE ABEJAS, EN CORRALILLOS. SIMÓN TALAVERA SUÁREZ LLEVA DESDE LOS 7 AÑOS EN EL OFICIO DE APICULTOR, SE TRATA DE UNA TRADICIÓN FAMILIAR. LA APICULTURA O EL CULTIVO DE ABEJAS ES UNA ACTIVIDAD AGROPECUARIA ORIENTADA A LA CRIANZA ABEJAS Y A PRESTARLES LOS CUIDADOS NECESARIOS CON EL OBJETO DE OBTENER LOS PRODUCTOS QUE SON CAPACES DE ELABORAR Y RECOLECTAR. Copia digital. Madrid : Ministerio de Educación, Cultura y Deporte. Subdirección Gener...

  17. Sindicatos en Ciudad Juárez: Historia y debilidad sindical

    Directory of Open Access Journals (Sweden)

    Cirila Quintero Ramírez

    1996-01-01

    Full Text Available This work analyzes the evolution of the labor unions in Ciudad Juárez for three decades of the maquiladora industry. Postulates as a main idea, the existence of a weakening of the labor unions in the rnaquiladoras as a consequence of two central factors: the absence of a labor union trajectory in the region, and the persistence of economical activities in Ciudad Juárez that depend on the American economy, and the existence of a factionalism inter and intralabor union in the main workers associations in the city, that has permitted the defeal of not onIy the official movements, but the independent ones too. The weakening ol the labor union. has also conducted to a policy ol apathy, conformity, and ol high colaboration with the investors, that has tumed the labor unions in Ciudad Juárez into an expression of subordinated labor unions, that legitimates their perrnanency in the rnaquiladoras are mostly to their link with investors than with their members. This article allows us to see two future sceneries in the city ol Ciudad Juárez: the accentuation of this kind of behavior in labor unions, or the disappearance ol labor unions in the maquiladoras.

  18. Validation of the reactor dynamics code HEXTRAN

    International Nuclear Information System (INIS)

    Kyrki-Rajamaeki, R.

    1994-05-01

    HEXTRAN is a new three-dimensional, hexagonal reactor dynamics code developed in the Technical Research Centre of Finland (VTT) for VVER type reactors. This report describes the validation work of HEXTRAN. The work has been made with the financing of the Finnish Centre for Radiation and Nuclear Safety (STUK). HEXTRAN is particularly intended for calculation of such accidents, in which radially asymmetric phenomena are included and both good neutron dynamics and two-phase thermal hydraulics are important. HEXTRAN is based on already validated codes. The models of these codes have been shown to function correctly also within the HEXTRAN code. The main new model of HEXTRAN, the spatial neutron kinetics model has been successfully validated against LR-0 test reactor and Loviisa plant measurements. Connected with SMABRE, HEXTRAN can be reliably used for calculation of transients including effects of the whole cooling system of VVERs. Further validation plans are also introduced in the report. (orig.). (23 refs., 16 figs., 2 tabs.)

  19. AER Working Group D on VVER safety analysis minutes of the meeting in Rez, Czech Republic 18-20 May 1998

    International Nuclear Information System (INIS)

    Siltanen, P.

    1998-01-01

    AER Working Group D on VVER reactor safety analysis held its seventh meeting in Hotel Vltava in Rez near Prague during the period 18-20 May 1998. There were altogether 11 participants from 8 member organisations. The coordinator for the working group, Mr. P. Siltanen (IVO) served as chairman. In addition to the general information exchange on recent activities, the topics of the meeting included: First review of solutions to the 3-dimensional AER Dynamic Benchmark Problem No. 5 on a steam line break accident. This benchmark involves a break of the main steam header. Safety analysis of reactivity events. Recent code development work and fuel behaviour. Coolant mixing calculations and experiments related to diluted slugs. A list of participants and a list of handouts distributed at the meeting are attached to the minutes. (author)

  20. Upgrade for the epithermal neutron beam at NRI Rez

    International Nuclear Information System (INIS)

    Marek, M.; Flibor, S.; Viererbl, L.; Burian, J.; Rejchrt, J.; Klupak, V.; Gambarini, G.; Vanossi, E.

    2006-01-01

    The epithermal neutron beam facility designed for pre-clinical neutron capture therapy research has been operated at LVR-15 reactor for more than ten years. The construction of the beam filter has been recently modified especially for the shielding quality of the beam shutter to be improved. The parameters of the upgraded beam were calculated with the MCNP code and a new source term for the NCTPLAN treatment planning software was evaluated. The calculated source term was consequently scaled according to the results of measurements in the free beam and in the 50x50x25 cm 3 water phantom. (author)

  1. Mirzam C. Pérez, The Comedia of Virginity: Mary and the Politics of Seventeenth-Century Spanish Theater

    Directory of Open Access Journals (Sweden)

    Natalia Fernández

    2016-01-01

    Full Text Available Reseña de Mirzam C. Pérez, The Comedia of Virginity: Mary and the Politics of Seventeenth-Century Spanish Theater, Waco (Texas, Baylor University Press, 2012, 173 pp. ISBN: 9781602586451.

  2. Natural Law in Francisco Suárez: Passion for Freedom

    Directory of Open Access Journals (Sweden)

    Manuel López Casquete de Prado

    2018-05-01

    Full Text Available The Suaretian formulation on the natural law offers one of the most brilliant and accomplished elaborations of the ius-naturalistic tradition. In this article we analyze the keys from which Suárez formulates his proposal, that finds in the concept of freedom its starting point. From the radical and inalienable call to the human being to the exercise of his freedom, Suárez reveals the essence of its elaboration, one of whose consequences would end by decanting —later on— the concept of subjective right. We also pay special attention to the epistemological aspects of its system, which we consider essential to approach a correct understanding of the Suaretian ius-naturalistic proposal. For this purpose, we offer a close comparison between the Suaretian system and the Thomistic epistemology of the natural law.

  3. In-pile cladding tests at NRI Rez and PIE capabilities and experience

    International Nuclear Information System (INIS)

    Zmitko, M.

    2002-01-01

    In-pile cladding corrosion test facilities and relevant post-irradiation capabilities at NRI Rez plc are overviewed. Basic information about the research rector LVR-15 and in-pile water loops is given. An experience in the field of Zr-alloy cladding corrosion testing and investigation of cladding corrosion behaviour is demonstrated for two experimental programmes conducted at NRI Rez in the past period. The first example describes results obtained at studying of corrosion behaviour of advanced Zr-alloys under PWR conditions with a special concern to a high lithium content and subcooled surface boiling. The second example informs about completion of the experimental programme supported by the IAEA which is focused on investigation of Zircaloy-4 cladding behaviour under VVER water chemistry, thermal-hydraulic and irradiation conditions with the main to obtain experimental data for an assessment of the Zircaloy-4 cladding compatibility with VVER conditions. (author)

  4. [Epilepsy in the Spanish Renaissance. The work of Pérez Cascales of Alcalá].

    Science.gov (United States)

    García-Albea, E

    During the Renaissance, the University of Alcalá de Henares represented the most best of Spanish medical humanism. A return to the classics after mediaeval religious obscurantism meant a 'modern' spirit of reconsideration of the major neurological disorders. In 1611 Francisco Pérez Cascales, trained at this university, wrote the first great Spanish treatise on paediatrics, Liber de affectionibus puerorum, which included a long chapter on epilepsy (alferecía). The author, considered to be a 'Hippocratic galenist' critically reviewed, with data from empirical observations, the Greek theory of humours. Following the Galenic tradition, he distinguished three types of epilepsy: primary or originating in the brain, and by 'consensus' (originating in another region but with secondary cerebral involvement) either of the stomach or other parts of the body. The work of Pérez Cascales is one of the most complete contributions to the under understanding of epilepsy at his time.

  5. MONUMENTO A PEDRO PÉREZ RODRÍGUEZ [Material gráfico

    OpenAIRE

    Anonymous

    1980-01-01

    ANEXO SELLO DE LA COMISIÓN DEL PATRIMONIO HISTÓRICO ARTÍSTICO DE GÁLDAR. MONUMENTO LEVANTADO POR LA PARROQUIA DE SAN JOSÉ DE LOS CAIDEROS A SU PRIMER PÁRROCO, EL SACERDOTE MAJORERO, DON PEDRO PÉREZ RODRÍGUEZ. SE ENCUENTRA EL BUSTO EN LA GLORIETA LATERAL DEL CENTRO. Copia digital. Madrid : Ministerio de Educación, Cultura y Deporte. Subdirección General de Coordinación Bibliotecaria, 2015

  6. Nostalgia of the Encomienda. Rereading Juan Suárez de Peralta's Tratado del descubrimiento (1589

    Directory of Open Access Journals (Sweden)

    Enrique González González

    2009-10-01

    Full Text Available The work Tratado del descubrimiento de las Yndias y su conquista, written  by the New Spain Creole Juan Suárez de Peralta around 1589, has traditionally been read as just another Conquest chronicle, scarcely interesting in its first chapters, but fully vivid in its “second” part, where the author  tells of the so-called conspiracy of Martín Cortés,  Second Marquis of the Valley of Oaxaca. This paper, however, suggests that the Tratado, in keeping with its title, must be read as a treatise in which Suárez de Peralta pleads for the legitimacy of the encomienda and offers an account of the fateful —as he sees them— consequences  brought about by the Crown's rulings to suppress it. Therefore, the Tratado must be considered within the great debates of the time on how conquered peoples, conquerors and their descendants  should be treated. Although not a professional lawyer, Suárez de Peralta turns out to be a resourceful and convincing writer. Far from offering a linear account  of a series of events, he takes advantage of ambiguity in order  to argue, from different  viewpoints,  on several issues. Sensing that he defends a lost cause, his allegation oozes irony, disillusion, and nostalgia.

  7. Nuclear Research Institute Rez: Its past and present and future challenges

    International Nuclear Information System (INIS)

    Pazdera, F.

    2001-01-01

    The paper gives an overview of the history of the Nuclear Research Institute Rez development over forty years of its existence. Its present activities are discussed in some detail. These historical and present activities represent the basis for discussing: challenges faced by the NRI; interactions of NRI with their environment; collaboration and co-operation. Nuclear research centres would continue to be the main source of expertise for power plant operation, radiation and isotope applications, regulatory practices and waste management. Future developments should ensure viability of these centres. (author)

  8. JORGE RAMÍREZ ESPINO, PRODUCTOR DE FLORES ARTIFICIALES [Material gráfico

    OpenAIRE

    Suárez García, Carlos Félix

    1980-01-01

    JORGE RAMÍREZ ESPINO, ARTESANO TRADICIONAL DE LAS PALMAS DE GRAN CANARIA DEDICADO A LA PRODUCCIÓN DE FLORES ARTIFICIALES CON TIRAS DE PLATANERA, HOJAS DE DRAGO, CAMISA DE MILLO Y LA PIÑA DE LA FLOR DE LA PLATANERA NACIÓ EN LAS PALMAS DE GRAN CANARIA EN EL AÑO 1942. COMIENZA SU ANDADURA DE MANERA AUTODIDACTA, CONFECCIONANDO FLORES, EN EL AÑO 1992, AL TIEMPO QUE REALIZA COLLARES PARA CABRAS CON ANTONIO PERERA HASTA EL AÑO 1995, EN QUE COMIENZA A VENDER SUS PRIMEROS PRODUCTOS DEL CARA AL PÚBL...

  9. Mentira y Verdad en tres Novelas de Sergio Ramírez: Algunos Procedimientos de Verosimilitud

    OpenAIRE

    Rodríguez Sancho, Javier

    2013-01-01

    Con base en la narrativa del nicaragüense Sergio Ramírez, se efectúa un análisis sobre algunos procedimientos de verosimilitud utilizados por el escritor en tres de sus novelas: Tiempo de fulgor (1970); ¿Te dio miedo la sangre? (1977) y Un baile de máscaras (1995). La evaluación de los textos busca comprender los niveles en que el escritor hace uso de ciertos procedimientos de verosimilitud para contarnos algunas mentiras verdaderas como él mismo lo ha llamado, en su ensayo: Mentiras verdader...

  10. Exploring the efficacy of an environmental health intervention in Ciudad Juárez, Mexico.

    Science.gov (United States)

    Hernández, Alma A; Grineski, Sara E

    2010-01-01

    This study explores the efficacy of an environmental health intervention in several poor colonias in Ciudad Juárez (Mexico). Parents of children with respiratory problems were given environment-friendly products intended to replace hazardous products used in the home, as well as information about environmental health. Parents were surveyed before and after to measure the effectiveness of the intervention and to gauge perceptions. There was a significant reduction in hazardous chemical use (eg, cleaning products and pesticides) and breathing problems. While the intervention focused on changing in-home behaviors, open-ended responses revealed that parents were most concerned about outdoor environmental conditions over which they had less control.

  11. La risa en Francisco Suárez. El paso de la Edad Media al Barroco

    Directory of Open Access Journals (Sweden)

    Manuel Lázaro Pulido

    2012-07-01

    Full Text Available El estudio muestra la relación entre la tradición medieval presente en la segunda escolástica y las consecuencias en el Barroco del humanismo renancentista, a partir de la referencia que hace Suárez a la risa en el Comentario al De anima. Aparece un desarrollo de la temática clásica y medieval sobre la risa, donde se tiene en cuenta la esfera intelectual del Humanismo científico y se señalan algunas temáticas que se tendrán presente en el Barroco moderno.

  12. Institutional radioactive waste management in the Nuclear Research Institute Rez plc

    International Nuclear Information System (INIS)

    Kovarik, P.; Svoboda, K.; Podlaha, J.

    2008-01-01

    Nuclear research institute Rez, plc. (mentioned below as NRI) has had a dominant position in the area of the nuclear research and development in the Czech Republic, the Central and the Eastern Europe. Naturally, the radioactive waste management is an integral part of the nuclear industry, research and development. For that reason, there is Centre of the radioactive waste management (mentioned below as Centre) in the NRI. This Centre is engaged in the radioactive waste treatment, decontamination, characterisation, decommissioning and other relevant activities. This paper describes the system of technology and other information about institutional radioactive waste management in the NRI. (authors)

  13. Levels of surface contamination with radioactive materials at workplaces of nuclear research centre at Rez

    International Nuclear Information System (INIS)

    Hoelgye, Z.; Nemcova, I.; Kasikova, M.; Popper, J.; Chysky, J.

    1983-01-01

    A hygiene supervision unit at workplaces of the nuclear Research Institute in Rez monitored on a long-term basis surface contamination with radioactive substances. Surface contamination was found at workplaces with open sources. Of the 4343 monitored places action levels were only exceeded in 13 cases. The obtained data were used for typifying workplaces with the highest level of surface contamination, to determine in certain instances the mechanism of the escape of radioactive substances from insulating facilities and to determine the rate of the spread of the radioactive substance into adjacent non-active workplaces. (author)

  14. El espacio y el tiempo en W. F. Flórez

    OpenAIRE

    Mandianes Castro, Manuel

    1990-01-01

    En las novelas de W. F. Flórez, como en la vida real de las aldeas gallegas, el espacio tiene muchos niveles: "lareira", aldea, parroquia, ciudad, Castilla, América, "fraga" y el subterráneo maravilloso, y el tiempo tiene cualidades: olor, sabor. Una lectura atenta de estas dos novelas demuestra que la oralidad forma parte importante de la narración; que el autor es, por lo mismo, en buena medida, un auténtico trasmisor de la tradición y que, por lo tanto, los etnólogos y antropólogos han de ...

  15. Ginés Pérez y su O Crux

    Directory of Open Access Journals (Sweden)

    Climent, José

    2002-12-01

    Full Text Available The exact names attributed to Ginés Pérez were never at all clear. His first appointment to the Cathedral in Valencia complicated matters even more when he was referred to with the Christian name of what appeared to be "Juan", which only added to the confusion as it lead us to believe that he was the only candidate to apply for that position. Today, however, we now know his true and full names: he was called Ginés Pérez de la Parra. We also know, for the first time, the exact date of his death. The quality of his compositions not only contributed to their popularity but gave rise to the works of other composers being attributed to him. The authorship of the majority of his compositions are considered anonymous, though they can be located in diverse archives. Even so, we cannot find a single copy of the O Crux attributed to his name, despite the numerous copies and their variants that abound in Region of Valencia.El nombre de Ginés Pérez nunca ha tenido la claridad de debía. Su primer nombramiento en la catedral de Valencia ya lo confunde añadiéndole el “Juan” lo que ya siembra confusión, además de sugerirnos que, posiblemente, fue llamado para ocupar el puesto sin oposición. Hoy conocemos toda su filiación: Ginés Pérez de la Parra, así como la fecha de su muerte, totalmente equivocada hasta ahora. La valía de sus composiciones motivó, además de la difusión de su obra, la atribución de composiciones de otros autores. La mayor parte de sus composiciones constan como "anónimos", si bien pueden encontrarse en distintos archivos. Del presente O crux, sin embargo, no hemos podido encontrar ninguna copia con su nombre, pese a las múltiples copias, con sus variantes, existentes en la Comunidad Valenciana.

  16. Transfrontera Crimes: Representations of the Juárez Femicides in Recent Fictional and Non-Fictional Accounts

    Directory of Open Access Journals (Sweden)

    Marietta Messmer

    2012-05-01

    Full Text Available In her article, Marrietta Messmer discusses the representation of the Juárez femicides and their traumatizing effects on the Juárez/El Paso community in four recently published accounts: Teresa Rodriguez's journalistic account The Daughters of Juarez (2007, the documentary Señorita Extraviada (2001 directed by Lourdes Portillo, the feature film Bordertown (2006, directed by Gregory Nava, and Alicia Gaspar de Alba's mystery novel Desert Blood: The Juárez Murders (2005. More specifically, she analyzes the degree to which these sources regard the femicides not merely as a Mexican problem but as a structural and highly significant transborder issue that has its roots in the region's current political and economic developments, as well as its pervasive social and cultural changes.

  17. Identificación de Chlamydophila abortus en un aborto ovino en Almoloya de Juárez, México

    OpenAIRE

    Edgardo Soriano-Vargas; Celene Salgado-Miranda; Juan Manuel Jiménez-Estrada; Marcela López-Hurtado; Fernando M. Guerra-Infante; Marcos R. Escobedo-Guerra

    2011-01-01

    ResumenSe identificó la presencia de Chlamydophila abortus en un aborto ovino procedente de Almoloya de Juárez, México.SummaryChlamydophila abortus was identified in an ovine aborted fetus from Almoloya de Juárez, México

  18. An Overlooked Contributor to a Unique Colombian Periodical. Enrique Pérez and the revista Hispania (1912-1916

    Directory of Open Access Journals (Sweden)

    Jane M. Rausch

    2018-04-01

    Full Text Available Hispania, a cultural periodical published in London between 1912 and 1916, was an important Colombian endeavor that reflected widely-shared Latin American concerns before and during the outbreak of the First World War. After a brief review of the role of literary periodicals in Colombian humanities, this essay analyzes the numerous contributions published by Enrique Pérez Lleras in Hispania. It concludes that Pérez believed Hispanic America could have avoided the threat of United States and/or European imperialism by spurning despotic rule, educating a governing elite, developing a trained civil service, and establishing strict controls over foreign investment and immigration.

  19. Avatares y desafíos del Instituto Juárez de Tabasco

    Directory of Open Access Journals (Sweden)

    Judith Pérez Castro

    2015-01-01

    Full Text Available El propósito de este trabajo es hacer un análisis de las circunstancias que rodearon la fundación y el desarrollo del Instituto Juárez de Tabasco. El artículo intenta mostrar la compleja situación que enfrentó este establecimiento educativo desde su creación en 1879 hasta las primeras décadas del siglo XX y el impacto que esto tuvo tanto en su oferta educativa como en su planta académica. Las principales variables que contextualizaron el desarrollo institucional fueron la difícil situación financiera, el cierre y apertura de sus carreras, la insuficiencia de matrícula, la débil organización de su cuerpo de profesores y la inestabilidad política estatal. A pesar de esto, el Instituto Juárez logra mantenerse y consolidarse como la principal opción educativa a nivel preparatoria y profesional en la entidad, hecho que aunado a un nuevo proceso de reforma hacen posible su ascenso como universidad hacia finales de los años cincuenta.

  20. Fundamentos teológicos de la censura en Francisco Suárez

    Directory of Open Access Journals (Sweden)

    Manuel Lázaro Pulido

    2017-09-01

    Full Text Available La censura es un acto recogido dentro del Código de Derecho Canónico. La teología subyacente se inscribe dentro de la historia de la salvación propia del concilio Vaticano II. Varios siglos antes, el maestro jesuita Francisco Suárez reflexionó sobre la censura en un voluminoso tratado (Disputationum de censuris…, en el que anticipa los elementos pertenecientes a la censura que aparecen en el actual CDC. Suárez realiza una lectura teológica en el que destaca el carácter medicinal de la censura, a partir de la lectura sacramental de la pena y desde un antropología de la voluntad, que supone una apuesta por la prevención del hombre y su salvación, antes que por su carácter penal, o si se quiere por dotar a la ley penal de un carácter salvífico.

  1. los caminos globales de Ciudad Juárez, Chihuahua-El Paso,Texas

    Directory of Open Access Journals (Sweden)

    Kathleen Staudt

    2006-01-01

    Full Text Available En este artículo se abordan temas selectos de políticas públicas, que dividen y unen a las mujeres en la frontera México-Estados Unidos, concentrados en el área metropolitana de Ciudad Juárez-El Paso, que conforma una "economía interdependiente", con una población superior a dos millones de personas, cuya mayoría comparte una herencia mexicana. De esta forma, se analiza una perspectiva compleja: la economía global en la que las maquiladoras de Ciudad Juárez están a la vanguardia; los cambios ideológicos de derecha en los gobiernos de México y Estados Unidos; con gobiernos divididos en filiación partidista así como en materia del federalismo, éste practicado en forma diferente por ambos, y en los cuales las voces de las mujeres tienen poca notoriedad. Sin embargo, ellas se organizan en grupos que representan sus intereses, aunque sus voces han sido marginadas en la sociedad y en la acción legislativa. Existen pocas organizaciones binacionales de mujeres, con algunas excepciones en los aspectos de salud y violencia.

  2. Tipos de tirano y resistencia en Francisco Suárez

    Directory of Open Access Journals (Sweden)

    Pablo Font Oporto

    2017-09-01

    Full Text Available El presente artículo pretende analizar la discusión que Francisco Suárez mantiene con las tesis contrarias a la distinción entre tipos de tirano en la cuestión del tiranicidio (Defensio fidei, Libro VI, capítulo IV, números 10-13. Para esta visión no le es lícito a una persona privada matar a ninguno de los dos tipos de tirano; sólo es posible darles muerte en legítima defensa, porque se entiende que en tal caso se actúa en ejercicio de autoridad pública. Suárez acaba admitiendo esta tesis en el número 13, lo que parece contradecirse con lo sostenido en el número 7, donde se aceptaba la muerte del usurpador por cualquier particular. Sin embargo, en el fondo mantiene la diferencia entre ambos tipos de tirano, por cuanto que en el caso del usurpador sostiene que siempre se dan las condiciones para alegar legítima defensa. Queda sin aclarar qué ocurre en tal caso con las condiciones dispuestas en los números 8 y 9.

  3. Diversas obras de Maricarmen Sánchez de Ramírez, en Venezuela

    Directory of Open Access Journals (Sweden)

    Editorial, Equipo Editorial

    1981-02-01

    Full Text Available This paper deals with three important works of the Madrid born Venezuelan architect, Mari Carmen Sánchez de Ramírez. The first, and the only one completed at present, are seven onefamily dwellings grouped together in one volumetric and structural unit. The second is a tall office building, triangular in shape and composed of a thirty-two story tower, a ground floor public area and a ten floor mechanically operated parking garage. Third and last is the Multi-purpose Complex, located on the coast. It is made up of commercial areas, residential areas, offices, parking facilities and public areas.

    En este trabajo se recogen tres interesantes obras de la arquitecto venezolana, nacida en Madrid, Maricarmen Sánchez de Ramírez. La primera, única realizada hasta la fecha, trata de la agrupación de siete viviendas unifamiliares en una misma unidad volumétrica y estructural. La segunda corresponde a un alto edificio de oficinas, de sección triangular, y compuesto por una torre de 32 niveles, un cuerpo bajo de espacios públicos y un estacionamiento mecánico de 10 plantas de altura. La tercera y última comprende un complejo multiuso, situado en la costa, formado por zonas comerciales, áreas de vivienda, oficinas, estacionamiento y espacios públicos.

  4. El cine de Pérez Arroyo y los proyectores de juguete de posguerra / The Cinema of Pérez Arroyo and the Postwar Toy Projectors

    Directory of Open Access Journals (Sweden)

    Raúl González-Monaj

    2016-08-01

    Full Text Available La historia de la animación de posguerra en nuestro país, conocida como «la edad dorada», siempre ha resultado fascinante por el contexto en que se desarrolló y por ello se ha convertido en objeto de estudio, pero todavía quedan algunos episodios menores por ultimar. El presente trabajo pretende completar una de esas lagunas, la referente a la obra de Joaquín Pérez Arroyo y su posterior relación con el cine doméstico de juguete y su entorno. A través de esta investigación profundizaremos en las películas de este animador, apenas conocido, y en su decisiva participación en dos de los ejemplos más populares del cine de juguete nacional: Payá y Jefe. Casos que estuvieron conectados gracias a él y que se mueven entre el cine de papel y los 35 mm, entre el salón comedor y la sala de cine, entre Mikito y Quinito.Palabras clave: cortometraje de animación, CIFESA, proyector de juguete, Payá, Saludes, Jefe, Quinito. AbstractThe story of the postwar animation in Spain, known as the « Golden Age», has always been fascinating due to the context where it happened and so, it became object of study. Nevertheless, there are still some episodes to be finished. This study aims to complete one of these gaps as the one related to Joaquín Pérez Arroyo's work and his later connection to home cinema as a toy and its context. All through this research, we'll analyze films of this barely known author and his decisive participation in two of the most popular toy cinema examples in Spain: Payá and Jefe. Thanks to him, these two cases became connected, two worlds that coexist within the paper film and the 35 mm, between the living room and the movie theatre, between Mikito and Quinito.Keywords: animation short film, CIFESA, toy projector, Payá, Saludes, Jefe, Quinito.

  5. El discurso político de Adolfo Suárez durante la Transición. Aplicaciones metodológicas / The political discourse of Adolfo Suárez in the process of Democratic Transition. Methodological applications

    Directory of Open Access Journals (Sweden)

    Antonio Pantoja Chaves

    2009-06-01

    Full Text Available Resumen: El presente artículo se centra, como primera toma de contacto , en el análisis del discurso político de Adolfo Suárez y de su componente ideológico durante la Transición, dentro del conjunto de las diferentes fuerzas políticas que más protagonismo tuvieron a lo largo de todo el proceso. La coalición de personalidades políticas que se reunieron en torno a la formación de la Unión de Centro Democrático, con la figura destacada del joven presidente Adolfo Suárez, presenta, no ya sólo para aquella época sino en la actualidad, un interés constante como objeto de estudio a partir de nuestro particular análisis metodológico. Summary: The present article concentrates, as an introduction, in the analysis of the political discourse of Adolfo Suárez and his ideological component during the Transition, within the set of the most outstanding political forces throughout the whole process. The coalition of political personalities that gathered in the formation of the Unión de Centro Democrático, with the prominent figure of young president Adolfo Suárez, is, not only for that one time but at present, a constant interest as object of study from our particular methodological analysis.

  6. Reactor physical experimental program EROS in the frame of the molten salt applying reactor concepts development

    International Nuclear Information System (INIS)

    Hron, Miloslav; Kyncl, Jan; Mikisek, Miroslav

    2009-01-01

    After the relatively broad program of experimental activities, which have been involved in the complex R and D program for the Molten Salt Reactor (MSR) - SPHINX (SPent Hot fuel Incinerator by Neutron fluX) concept development in the Czech Republic, there has been a next stage (namely large-scale experimental verification of design inputs by use of MSR-type inserted zones into the existing light water moderated experimental reactor LR-0 called EROS project) started, which will be focused to the experimental verification of the rector physical or neutronic properties of other types of reactor concepts applying molten salts in the role of liquid fuel and/or coolant. This tendency is based on the recently accepted decision of the MSR SSC of GIF to consider for further period of its activity two baseline concepts- fast neutron molten salt reactor non-moderated (FMSR-NM) as a long-term alternative to solid fuelled fast neutron reactors and simultaneously, advanced high temperature reactor (AHTR) with pebble bed type solid fuel cooled by liquid salts. There will be a brief description of the prepared and performed experimental programs in these directions (as well as the preliminary results obtained so far) introduced in the paper. (author)

  7. 75 FR 4879 - Juan E. Pérez Monté, M.D.; Confirmatory Order Modifying License (Effective Immediately)

    Science.gov (United States)

    2010-01-29

    ... the Health Physics Society, and the Journal of Nuclear Medicine; and, 2. Dr. P[eacute]rez will also... national meetings of the Health Physics Society and the Society of Nuclear Medicine. If the request to make... following: Galenus (Puerto Rico), the Journal of the Health Physics Society, and the Journal of Nuclear...

  8. El concepto de ser en Suárez. ?Unívoco o análogo?

    Czech Academy of Sciences Publication Activity Database

    Heider, Daniel

    2017-01-01

    Roč. 20, č. 40 (2017), s. 99-120 ISSN 0329-8930 Institutional support: RVO:67985955 Keywords : Suárez * concept of being * analogy * univocity Subject RIV: AA - Philosophy ; Religion OBOR OECD: Philosophy, History and Philosophy of science and technology http://studium.unsta.edu.ar/ojs/index.php/Studium/article/view/141/120

  9. Infermeria Medicoquirúrgica II. Temari corresponent al Professor Francisco Pérez Dolz. Curs 2017-2018

    OpenAIRE

    Pérez Dolz, Francisco

    2017-01-01

    El document forma part dels materials docents programats mitjançant l'ajut del Servei de Política Lingüística de la Universitat de València. Temari corresponent al professor Francisco Pérez Dolz

  10. Infermeria Médico-Quirúrgica II. Temari corresponent al Professor Francisco Pérez Dolz. Curs 2017-2018

    OpenAIRE

    Pérez Dolz, Francisco

    2017-01-01

    El document forma part dels materials docents programats mitjançant l'ajut del Servei de Política Lingüística de la Universitat de València Infermeria Médico-Quirúrgica II. Temari corresponent al Professor Francisco Pérez Dolz. Curs 2017-2018.

  11. En femenino: Apuntes sobre la obra de Esperanza Barroso y Raquel Ramírez

    Directory of Open Access Journals (Sweden)

    Andrés Leonardo Caballero Piza

    2016-03-01

    Full Text Available El siguiente artículo proporciona algunas coordenadas de interpretación para la obra de las artistas santandereanas Esperanza Barroso y Raquel Ramírez, desde los conceptos de currículo oculto y micropolítica, y desde diversas fuentes documentales de carácter historiográfico (catálogos, folletos, recortes de prensa y entrevistas. Mediante el concepto de currículo oculto se reconstruye de forma general el ámbito en que fueron educadas ambas artistas, mientras que con el de micropolítica se inscriben sus obras en las preocupaciones del arte colombiano de los setentas, que giraron en torno de los modos de representación del cuerpo desde el deseo individual, la emancipación subjetiva y las restricciones jurídicas del Estado.

  12. Impactos de la maquila en el medio ambiente de Ciudad Juárez

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    Centro de Estudios Regionales y Comunicación Alternativa (CERCA

    2009-01-01

    Full Text Available En el presente trabajo analizamos, de manera general, los cambios que ha generado el proyecto maquilador en Ciudad Juárez. Primero observamos su efecto sobre el crecimiento de la mancha urbana, la dotación de servicios, etcétera, su repercusión en el medio ambiente y las condiciones de vida de la población juarense. Nos planteamos, además, ubicar los principales problemas causados por el desarrollo de la industria maquiladora, particularmente en lo relativo a los desechos tóxicos y nucleares, así como apuntar la tendencia del proyecto económico-urbano que ésta ha impuesto en nuestra ciudad, para concluir con una breve presentación de las reacciones populares y algunas propuestas ante el problema. Asimismo, exponemos los problemas de contaminación que resultan de otras actividades no vinculadas a la industria maquiladora.

  13. Social acceptability urban form and sustainability in urban neighborhoods in Ciudad Juárez, Chihuahua

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    Claudia Gabriela Vargas Fernández

    2016-11-01

    Full Text Available In the field of urban planning, questioning around sustainability and the possibility of sustainable urban planning has led to a new set of approaches and discussions that impact studies on urban form and sustainable livelihoods. This approach characterized the work presented by Mike Jenks and Colin Jones (2010, Dimensions of the Sustainable City, where a set of variables are presented about urban sustainability from the neighbourhood level of analysis. In that sense, this article proposes the analysis of three social housing neighborhoods in Ciudad Juárez, Chihuahua, México, integrating aspects of urban form and social acceptability, in order to understand the relationship between the physical and sociocultural dimensions of the concept of urban sustainability.

  14. Street Art at the Border: Representations of Violence and Death in Ciudad Juárez

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    Diana Alejandra SILVA LONDOÑO

    2016-01-01

    Full Text Available El objetivo de este artículo es realizar una lectura interpretativa de las tramas de sentido de la violencia y la muerte violenta en Ciudad Juárez, a partir de su representación en el arte urbano. Por medio de entrevistas en profundidad, observación participante, recorridos urbanos y regis - tro fotográf ico de la producción artística de los colectivos de arte urbano fronterizo se explora cómo las/os jóvenes se conciben a sí mismas/os, perciben su experiencia biográf ica y cuáles son sus márgenes de agencia desde las prácticas artísticas en contextos de violencia.

  15. Ciudad Juárez en los sesenta: la estructura urbana en transición

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    Luis Enrique Gutiérrez Casas

    2009-01-01

    Full Text Available El presente trabajo está estructurado de tal forma que puedan cubrirse, de manera general, los distintos aspectos que consideramos explican el problema de la vivienda en Ciudad Juárez. En la primera parte planteamos el problema de la vivienda desde varios aspectos, déficit, bajos salarios y pérdida del poder adquisitivo de los trabajadores, fluctuación del mercado inmobiliario, crecimiento poblacional, cambios en la composición del mercado laboral, flujos migratorios, políticas económicas y de vivienda. En la segunda parte centramos nuestro análisis en los AHI. Sus rasgos principales son las formas irregulares de apropiación del suelo urbano, la autoconstrucción y la introducción ilegal de servicios públicos, entre otros.

  16. residenciales de madres sin cónyuge en Ciudad Juárez

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    Claudia Zamorano Villarreal

    2006-01-01

    Full Text Available Se abordarán los itinerarios y las prácticas residenciales de madres sin cónyuge en Ciudad Juárez, ese punto de convergencia de inmigrantes nacionales y capitales internacionales y ahora, una de las más importantes ciudades maquiladoras del país. A partir de 51 historias de vida con trabajadoras de esta industria, se comparan los itinerarios residenciales de familias monoparentales con los de familias biparentales. Esta comparación permite ver las desventajas de las primeras para ingresar al mercado de la vivienda, que no se explican únicamente por factores de orden económico, sino también moral y práctico.

  17. Homicidio masculino en Ciudad Juárez. Costos de las masculinidades subordinadas

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    Salvador Cruz

    2011-01-01

    Full Text Available El homicidio masculino agudizado en Ciudad Juárez en los años 2008 y 2009, con casi cuatro mil asesinatos, constituye la expresión más evidente de la violencia urbana. Dicha violencia ha tomado rostro en hombres, en su mayoría jóvenes y marginados. Los datos muestran un comportamiento del homicidio doloso asimilado a significados relacionados con la masculinidad más tradicional, cuyo costo recae en la vida misma. Se observa a través de los escenarios, los horarios en que ocurren los eventos y las formas de ejecución, que esta práctica delictiva puede ser comprendida como una actividad masculina que explota una subjetividad proclive a la violencia y que reproduce las asimetrías de género y significados asociados a la dicotomía masculino-femenino.

  18. Misery, Hope and Humanity in Benito Pérez Galdós's Misericordia (1897

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    María Isabel Rovira Martínez de Contrasta

    2014-10-01

    Full Text Available Amidst the great turmoil, appalling conditions and ineffable hardships of impoverished nineteenth-century Spain, the realist writer Benito Pérez Galdós brilliantly weaves a tale of humanity and friendship in Misericordia, a story about the compassion, unfaltering loyalty and devotion of the main character, Benina, towards her neighbors. The plot revolves strategically around the lowest and most economically deprived social group, the beggars, thus separating Galdós's Misericordia from the work of his contemporaries. In this fictional work, the lower class is given great social visibility via Benina, who constitutes the embodiment of all the values, ideology and principles the writer seeks to praise and emphasize in the story.

  19. El Multiculturalismo Canadiense ante el Arte y los Testimonios de Constanza Camelo Suárez

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    Alexandre Beaudoin Duquette

    2017-04-01

    Full Text Available Resumen Constanza Camelo Suárez es una artista visual de origen colombiano que vive en la provincia de Quebec, en Canadá.  En el año 2008, realizó un performance en una importante estación del metro de la ciudad de Montreal, que llevaba por título Dilatar o contraer el universo.  En el marco de esta intervención, un grupo de inmigrantes guiados por perros lazarillo caminaban con los ojos vendados por los pasaportes de sus países de origen y llevaban puesto en su cintura unos aparatos de los cuales emanaban de manera aleatoria las notas de los himnos nacionales de sus países respectivos, así como las del himno canadiense.  Su acción nos brinda varios elementos que nos permiten cuestionar, romper o relativizar los estereotipos del discurso propagandístico de las instituciones migratorias canadienses.  En el presente trabajo, se trata precisamente de entablar una relación disonante entre el performance y fragmentos de testimonios de Constanza Camelo Suárez y una “historia de éxito” que fue publicada en el sitio Internet del Ministerio de Ciudadanía e Inmigración canadiense en el año 2011 y que lleva por título María Aragón: una joven canadiense de 10 años que causa sensación en YouTube.  Lo anterior se lleva a cabo analizando las siguientes fuentes de disonancia, entendida como la relación entre elementos de información incompatibles: multiculturalismo/transculturalidad, consenso/accidentes situacionales, ocupación del espacio público/espacio masivo ocupado, demostración de fuerza/demostración de vulnerabilidad. Palabras-claves: Arte latinoamericano, diáspora latinoamericana, diáspora colombiana, migración a Canadá, multiculturalismo canadiense, propaganda migratoria.   Canadian Multiculturalism face the Art and Testimonies of Constanza Camelo Suárez Abstract  Constanza Camelo Suárez is a visual artist of Colombian origin living in the province of Quebec, Canada. In 2008, she performed at an important

  20. Paul E. Kahle and Federico Pérez Castro: The Origins of the Madrid School of Biblical Text Criticism

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    Fernández Tejero, Emilia

    2008-06-01

    Full Text Available We have frequently been asked about the origins of the Madrid School of Biblical Text Criticism. We have limited the content of this paper to Masoretic studies. Research into the files of the former Instituto Arias Montano of the CSIC disclosed a series of unedited letters between Professors Kahle and Pérez Castro; a paper by F. Pérez Castro and F. Cantera Burgos on “Prof. Paul E. Kahle y los estudios de crítica textual bíblica en España,” and a description by F. Pérez Castro of the first project to edit the Cairo Codex of the Prophets. Through these materials we can trace the main steps of the relationship between these two relevant scholars and the role that such a relationship played in the origin and late development of these studies in Madrid.

    A menudo se nos ha preguntado por los orígenes de la escuela de crítica textual bíblica de Madrid. Hemos limitado el contenido de este artículo a los estudios masoréticos. Investigando en los archivos del antiguo Instituto Arias Montano del CSIC hemos encontrado una colección de cartas inéditas entre los Profesores Kahle y Pérez Castro; un artículo escrito por F. Pérez Castro y F. Cantera Burgos titulado «Prof. Paul E. Kahle y los estudios de crítica textual bíblica en España», y la descripción hecha por Pérez Castro del primer proyecto para editar el Códice de Profetas de El Cairo. Gracias a estos testimonios hemos podido documentar las principales fases de la relación entre estos dos eminentes profesores y el papel que tal relación desempeñó en el origen y posterior desarrollo de estos estudios en Madrid.

  1. El léxico de parentesco quechua según Juan Pérez Bocanegra (Cuzco, siglo XVII

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    Raúl Bendezú-Araujo

    2015-01-01

    Full Text Available ResumenEn el marco de los estudios andinos coloniales, la figura de Juan Pérez Bocanegra, párroco de Andahuaylillas (Cuzco, goza de gran prestigio y su obra es frecuentemente citada como una fuente muy digna de crédito. El aporte más significativo de este clérigo a nuestro conocimiento del pasado andino lo constituye, muy probablemente, su detallada descripción del sistema de parentesco quechua. Ahora bien, sin intentar desmerecer el valor general de la obra de Pérez Bocanegra, la presente nota busca ofrecer una perspectiva lingüístico-filológica de los datos que esta presenta respectodel léxico de parentesco del quechua de inicios del siglo XVII. En ese sentido, intentaremos fundamentar la hipótesis de que, en relación con este aspecto particular, los datos de Pérez Bocanegra no son del todo fiables, pues obedecen a un proyecto evangelizador particular, que deja rastros en la selección y presentación de los lexemas que componen el campo léxico en cuestión.Palabras clave: filología andina, términos de parentesco, Juan Pérez Bocanegra, quechua colonial AbstractWithin the framework of colonial Andean studies, the image of Juan Perez Bocanegra, parish priest of Andahuaylillas (Cuzco, is highly regarded, and his work is often cited as a very reliable source. The most significant contribution of this cleric to our knowledge of the Andean past lies in its detailed description of the Quechua kinship system. However, without trying dismiss the overall value of the work of Pérez Bocanegra, this article seeks to provide a linguistic-philological perspective of the data he provides regarding the Quechua kinship lexicon from the early seventeenth century. In this respect, I will try to support the hypothesis that, on this particular aspect, this author’s data is not entirely reliable, for it obeys a particular evangelizer project that leaves traces in the selection and presentation of the lexemes that compose the lexical field in

  2. Ciudad, espacio y ceguera en ciudad Juárez México / City, Space, and Blindness Juárez, México

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    Maria Esther Vega-Ocampo

    2015-05-01

    Full Text Available Normal 0 false false false EN-US JA X-NONE /* Style Definitions */ table.MsoNormalTable {mso-style-name:"Table Normal"; mso-tstyle-rowband-size:0; mso-tstyle-colband-size:0; mso-style-noshow:yes; mso-style-priority:99; mso-style-parent:""; mso-padding-alt:0in 5.4pt 0in 5.4pt; mso-para-margin:0in; mso-para-margin-bottom:.0001pt; mso-pagination:widow-orphan; font-size:10.0pt; font-family:Cambria;} Resumen. La comunidad ciega en ciudad Juárez Mexico en frontera con Estados Unidos, mantiene en nuestros días una ausencia participativa en lo cotidiano, la estructura urbana de poca inclusión, los lleva crear alternativas para su movilidad. El objetivo  de este estudio es comprender y analizar cómo es la interacción social y espacial del ciego en una ciudad deshabilitada para su movilidad. Se utilizo un enfoque cualitativo que permitiese una observación cercana al grupo mediante entrevistas semi estructurada y observación participante, se escogió a un grupo de jóvenes ciegos que asisten a la Escuela para Ciegos Luis Braille. Se encontró que la ciudad  muestra un reflejo marginal que genera restricciones en su traslado, movilidad y aprendizaje espacial manteniendo una difícil autonomía.   Abstract: The community of visually impaired persons in Ciudad Juarez, Mexico, sitting astride the United States border, is practically absent from the city's day-to-day life. Providing negligible accommodations, Ciudad Juarez is not an inclusive environment and thus the visually impaired must auto-construct their own means of mobility to get out into the broader community they inhabit. The objective of this study is to analyze and understand the social and spacial interaction of the visually impaired in a northern Mexican border city entirely unequipped for them. The study focuses on a group of students at the Luis Braille School for the Blind in Ciudad Juarez, who were interviewed and observed during a prolonged period of time, and concludes that

  3. Synthesis of an A'B' Precursor to Angelmicin B: Product Diversification in the Suárez Lactol Fragmentation.

    Science.gov (United States)

    Li, Jialiang; Todaro, Louis; Mootoo, David R

    2011-11-01

    We describe a synthetic strategy for the angelimicin family of anthraquinoid natural products that involves converting a central highly oxygenated decalin intermediate to the AB and A'B' subunits. Herein, we report the synthesis of the bicyclic A'B' subunit that complements our earlier route to the tricyclic AB framework. The differentiating tact in the two syntheses focused on controlling the Suárez radical fragmentation of lactol precursors by modulating the substrate's structural rigidity. A more flexible lactol gave the tricyclic AB framework, whereas a more rigid substrate led to the bicyclic A'B' precursor, presumably through divergent pathways from the radical produced in the initial fragmentation step. These results establish a versatile advanced synthetic precursor for the angelimicins, and on a more general note, illustrate strategies for applying the Suárez fragmentation to diverse and complex molecular frameworks.

  4. Turismo industrial: oportunidades y retos dentro del sector de manu- factura en Ciudad Juárez

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    Francisco Arturo Bribiescas Silva

    2015-01-01

    Full Text Available Turismo Industrial, tema relevante dentro de la región fronteriza Ciudad Juá-rez-El Paso, donde la Industria de manufactura tiene gran dinamismo eco-nómico, y se visualizan expectativas y propuestas innovadoras a este sector. Este trabajo es una exploración de las oportunidades y retos de la industria manufacturera instalada en Ciudad Juárez para desarrollar actividades de turismo industrial en sus instalaciones. La información se obtuvo a través de entrevistas a profundidad con 15 gerentes de las empresas más importantes de esta región. Dentro de los resultados se puede observar que las actividades del turismo industrial son percibidas por los gerentes entrevistados como benéficas y consideradas como una actividad alterna a la manufactura.

  5. [Epidemiology of gunshot wounds at Ciudad Juárez, Chihuahua General Hospital].

    Science.gov (United States)

    Moye-Elizalde, G A; Ruiz-Martínez, F; Suarez-Santamaría, J J; Ruiz-Ramírez, M; Reyes-Gallardo, A; Díaz-Apodaca, B A

    2013-01-01

    Since 2007, Ciudad Juárez, Chihuahua has been considered as one of the most violent cities in the world. The General Hospital in this city is the main facility where patients with gunshot wounds are taken. The increased number of admissions of patients with these injuries to many hospitals in the country deserves special attention, as it has an impact on hospital resources and management protocols. To disseminate the epidemiology of fractures caused by gunshot wounds and the hospital care of these patients. A retrospective, observational cohort study was conducted of patients admitted to the Traumatology and Orthopedics Service, Cd. Juárez General Hospital, in Chihuahua, Mexico, from January 2008 to December 2010. All of them sustained fractures resulting from gunshot wounds. A total of 1281 patients with a diagnosis of gunshot wounds were admitted to the hospital; 402 of them were included in this study with 559 fractures; 329 were males and 73 females. Of the 559 fractures, 257 involved the upper limb, 294 the lower limb, and 8 the pelvis. Gunshot wounds-related fractures were classified according to the Gustilo classification. Seventy-nine patients had grade I fractures, 302 grade III, and 21 patients had both grades. Conservative treatment was used in 44.3% of fractures and osteosynthesis in 55%. One patient underwent amputation upon admission. The most widely used osteosynthesis methods were external fixator (37%), straight plates (21%) and intramedullary nail (17%). Five patients (1.3%) underwent amputation: two with femur fracture and 3 with humeral fracture. There were 27 deep infections (6%); one of them resulted in late amputation of the pelvic limb. The most common associated injuries included: chest injuries in 20 patients and abdominal injuries in 17. The range of hospital stay was 1-18 days, with a mean stay of 11 days. The overall mortality rate considering the total number of patients admitted (1,281) was 99 patients (7.72%). From 2006 to 2010 the

  6. Reflexions al voltant de la proposta lingüística de Josep Nebot i Pérez

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    Joan Rafael Ramos

    2015-10-01

    Full Text Available This article tries to outline the general background of grammatical studies in Catalan by the end of the 19th century and beginnings of the 20th century, while phocusing on the work of the Valencian grammarian Josep Nebot i Pérez, his linguistic ideology and his interesting proposal of producing two different set of grammars: a popular one, and another addressed to the more cultivated reader.

  7. The Rise and Development of Physics in Cuba: An Interview with Hugo Pérez Rojas in May 2009

    Science.gov (United States)

    Baracca, Angelo

    Hugo Celso Pérez Rojas was born in 1938, and works as a senior researcher at the Institute of Cybernetics, Mathematics and Physics, at the Ministry of Science and Technology, Cuba. Pérez Rojas is emeritus member of the Academy of Sciences of Cuba, member of the Latin American Academy of Sciences and Fellow TWAS since 1994. He was one of the founders of the School of Physics in the University of Havana in 1962, and moved in 1971 to the Cuban Academy of Sciences. His national awards include the Rafael Maria Mendive and Carlos J. Finlay Medals. He was awarded in 2011 the National Prize in Physics from the Cuban Physical Society. His interests include quantum field theory and its applications to finite temperature problems in high-energy physics and condensed matter. Among these, Pérez Rojas has devoted special attention to quantum electrodynamics in matter and in vacuum in the presence of external fields, phase transitions in electroweak theory, relativistic quantum Hall effect, Bose-Einstein condensation in magnetic fields, and applications of physics to social sciences. He is interviewed here by Angelo Baracca in May 2009.

  8. El impuesto predial en Ciudad Juárez desde una perspectiva de equidad

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    Sergio Peña-Medina

    2016-01-01

    Full Text Available El aspecto de equidad en el impuesto predial es un tema relevante que se aborda en este artículo. Ésta se diferencia entre vertical y horizontal; la primera se refiere a un enfoque progresivo en donde aquellas propiedades que valen más pagan una tasa superior a las de menor valor; la equidad horizontal apunta a un tema de valuación y, en ella, las propiedades comparables pagan la misma tasa. El artículo tiene como objetivo poner a prueba la hipótesis de regresividad del impuesto predial; se argumenta que ésta es inequitativa dado que en términos proporcionales las propiedades de menor valor pagan una tasa superior a las de mayor valor. Los resultados en esta investigación soportan la hipótesis de que existe un efecto de regresividad en el impuesto predial en Ciudad Juárez; consecuentemente es importante reflexionar sobre la estructura actual del sistema catastral.

  9. Historias de dictadura. Primeros cuentos de Sergio Ramírez

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    María del Pilar Ríos

    2017-07-01

    Full Text Available Los primeros textos del escritor nicaragüense Sergio Ramírez presentan algunos elementos que conforman, a manera de mosaico, los principales rasgos de la vida individual y social durante la larga dictadura somocista (1936 – 1979. Poder, violencia, dependencia política, social y económica son algunas de las problemáticas que asoman y su tratamiento se acentúa o modifica entre una publicación y otra más allá del orden de aparición. Asimismo, en el marco de las luchas por la liberación encabezadas por el Frente Sandinista de Liberación Nacional (FSLN, se cuestiona la función del arte y del intelectual. Propongo una serie de cuentos incluidos en Cuentos (1963, Nuevos Cuentos (1969 y Charles Atlas también muere (1976 en la que reviso, en primera instancia, la postura en torno al arte y al intelectual que exponen mediante la autofiguración del autor. Luego, exploro algunos elementos que conforman esos mundos narrativos y que funcionan como denuncia político-social al mismo tiempo que imaginan y reivindican una nueva nación en sintonía con los postulados presentes en las luchas revolucionarias.

  10. Nuevas otras de Jenaro Pérez Villaamil y Carlos de Haes

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    Arias Anglés, Enrique

    2004-06-01

    Full Text Available La intención del presente trabajo es dar a conocer y catalogar algunas obras, aparecidas últimamente, de estos dos grandes maestros del paisajismo español del siglo XIX. Unas tienen el interés de aportamos, o ampliamos, la visión de una etapa determinada del artista de la que tenemos escaso conocimiento; otras meramente contribuyen a aumentar el catálogo conocido de las obras de estos pintores y, aunque nada nuevo aporten al juicio que de su pintura poseemos en general, ya eso mismo siempre resulta de por sí un valor añadido a su producción, y más si se trata de algún buen cuadro; y, por último, también tenemos el caso de la obra que ha podido ser identificada gracias a sernos conocido previamente su dibujo preparatorio. Comenzaremos por las que nos amplían la visión de una etapa pictórica poco conocida del paisajista romántico español Jenaro Pérez Villaamil…

  11. La cultura del feminicidio en Ciudad Juárez, 1993-1999

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    Julia Estela Fragoso Monárrez

    2000-01-01

    Full Text Available El proposito de esta investigación es analizar los asesinatos cometidos contra niñas y mujeres de Ciudad Juárez en los años de 1993 a 1999, a través de la categoría analítica del feminicidio. Diferenciar las distintas clases de feminicidios y delinear los perfiles sociodemográficos de vulnerabilidad de las niñas y las mujeres asesinadas. Finalmente clasificar la relación de parentesco entre la víctima y el victimario. Los datos se recolectaron de fuentes secundarias y oficiales para 162 víctimas. Los resultados arrojan un perfil preliminar sociodemográfico de las víctimas y confirman la existencia de varios tipos de feminicidios en algunos casos en relación a la ocupación de las víctimas. En cuanto a la noción de un asesino serial o una epidemia de machismo que repite patrones de exterminio, ambas categorías se encuentran presentes. Los resultados también confirman una relación de parentesco o desconocimiento entre las víctimas y el victimario

  12. La transformación transatlántica de la Monja Alférez .

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    Chloe Rutter- Jensen

    2007-12-01

    Full Text Available Catalina de Erauso's story, La historia de la monja alférez escrita por ella misma / Catalina de Erauso recounts her adventures as a man, her later confession of being a woman and virgin, her pension from the king, and even the Pope's legitimization of her dressing as a man. The author examines this text in terms of its contribution and resistance to the construction of gender in Spain and the Spanish American colonies in the early 17th century. The transatlantic voyages open a space in which the figure of Catalina de Erauso transits from one gender category to another. With an emphasis on the prefix 'trans', reading the text through the lens of the 'transsexual' narrative creates new borders and limits, and accentuates the text as a site of struggle over gender identity. The 'transsexual' narrative can help us see the text not only as a site of transition and combination of social categories, but also for interrupting the binary structure of sex and gender that appears so natural today.

  13. Carbon monoxide exposure in households in Ciudad Juárez, México.

    Science.gov (United States)

    Montoya, Teresa; Gurian, Patrick L; Velázquez-Angulo, Gilberto; Corella-Barud, Verónica; Rojo, Analila; Graham, Jay P

    2008-03-01

    This study assessed exposure to carbon monoxide from gas and wood heater emissions in a sample of 64 households in peri-urban residential areas in Ciudad Juárez, Chihuahua, México. Indoor and outdoor carbon monoxide concentrations and temperatures were monitored for a continuous period of 1 week at 1 and 6-min intervals, respectively. The moving average carbon monoxide concentrations were compared to the World Health Organization (WHO) standards for carbon monoxide. Sixty-seven percent of households with gas heaters and 60% of households with wood heaters exceeded a health-based standard at some point during the monitoring. The difference between indoor and outdoor temperatures was modestly correlated with average carbon monoxide exposure (r=0.35, p-value h standard of 9ppm (odds ratio=5.1, p-value=0.031). These results highlight the need for further efforts to identify and mitigate potentially hazardous carbon monoxide exposures, particularly in moderate-income countries with cooler climates.

  14. Marine biodiversity at the end of the world: Cape Horn and Diego Ramírez islands

    Science.gov (United States)

    Ballesteros, Enric; Bell, Tom W.; Giddens, Jonatha; Henning, Brad; Hüne, Mathias; Muñoz, Alex; Salinas-de-León, Pelayo; Sala, Enric

    2018-01-01

    The vast and complex coast of the Magellan Region of extreme southern Chile possesses a diversity of habitats including fjords, deep channels, and extensive kelp forests, with a unique mix of temperate and sub-Antarctic species. The Cape Horn and Diego Ramírez archipelagos are the most southerly locations in the Americas, with the southernmost kelp forests, and some of the least explored places on earth. The giant kelp Macrocystis pyrifera plays a key role in structuring the ecological communities of the entire region, with the large brown seaweed Lessonia spp. forming dense understories. Kelp densities were highest around Cape Horn, followed by Diego Ramírez, and lowest within the fjord region of Francisco Coloane Marine Park (mean canopy densities of 2.51 kg m-2, 2.29 kg m-2, and 2.14 kg m-2, respectively). There were clear differences in marine communities among these sub-regions, with the lowest diversity in the fjords. We observed 18 species of nearshore fishes, with average species richness nearly 50% higher at Diego Ramírez compared with Cape Horn and Francisco Coloane. The number of individual fishes was nearly 10 times higher at Diego Ramírez and 4 times higher at Cape Horn compared with the fjords. Dropcam surveys of mesophotic depths (53–105 m) identified 30 taxa from 25 families, 15 classes, and 7 phyla. While much of these deeper habitats consisted of soft sediment and cobble, in rocky habitats, echinoderms, mollusks, bryozoans, and sponges were common. The southern hagfish (Myxine australis) was the most frequently encountered of the deep-sea fishes (50% of deployments), and while the Fueguian sprat (Sprattus fuegensis) was the most abundant fish species, its distribution was patchy. The Cape Horn and Diego Ramírez archipelagos represent some of the last intact sub-Antarctic ecosystems remaining and a recently declared large protected area will help ensure the health of this unique region. PMID:29364902

  15. Violencias en el Norte de México: el caso de Ciudad Juárez

    Directory of Open Access Journals (Sweden)

    Alberto Aziz Nassif

    2014-06-01

    Full Text Available En este trabajo se hace un análisis de los diferentes tipos de violencia que se generan en la crisis de una ciudad que fue abatida por las bandas del narcotráfico en la frontera de México con Estados Unidos. Hay efecto combinado de guerra entre cárteles por el control de la plaza, que se mezcla con la mala estrategia de enfrentamiento y la penetración de los cuerpos policíacos, lo que da como resultado una amplia destrucción de personas, familias y espacios. Las violencias se construyen porque hay causas estructurales, como el modelo de ciudad, porque hay una deficiente presencia del Estado y por una estrategia de guerra entre cárteles. Todo esto produce la crisis de violencia que se vive en Ciudad Juárez.   Abstract   This paper provides an analysis of the different types of violence that are generated in the crisis of a city that was shot down by drug gangs in Mexico’s border with the United States. The combined effects of the war between cartels for control of the square, mixed with the bad strategy of confrontation and the penetration of the police forces give as a result extensive destruction of individuals, families and spaces. Violence is built because there are structural causes such as the city’s model, because there is a weak State presence and war strategy between cartels. All this results in the violence crisis that exists in Ciudad Juarez.

  16. El Club Dumas de Arturo Pérez-Reverte como paradigma de la narrativa posmoderna española

    OpenAIRE

    Isaac Gómez Laguna

    2015-01-01

    El presente artículo ofrece un análisis de los diferentes rasgos posmodernistas que aparecen de manera explícita en El Club Dumas, novela insignia de la narrativa posmoderna en España, en torno a tres ejes centrales: a) género de la obra e intertextualidad, b) indeterminación e irrealidad, y c) individuo y sociedad. Mediante esta reflexión pretendemos evidenciar que su autor, Arturo Pérez-Reverte, no solo crea una novela puramente posmoderna, sino que su obra le sirve para teorizar acerca del...

  17. El Club Dumas de Arturo Pérez-Reverte como paradigma de la narrativa posmoderna española

    Directory of Open Access Journals (Sweden)

    Isaac Gómez Laguna

    2015-06-01

    Full Text Available El presente artículo ofrece un análisis de los diferentes rasgos posmodernistas que aparecen de manera explícita en El Club Dumas, novela insignia de la narrativa posmoderna en España, en torno a tres ejes centrales: a género de la obra e intertextualidad, b indeterminación e irrealidad, y c individuo y sociedad. Mediante esta reflexión pretendemos evidenciar que su autor, Arturo Pérez-Reverte, no solo crea una novela puramente posmoderna, sino que su obra le sirve para teorizar acerca del posmodernismo.

  18. Factores asociados con el uso inconsistente de condón en hombres que tienen sexo con hombres de ciudad juárez

    OpenAIRE

    Mendoza-Pérez, Juan C.; Ortiz-Hernández, Luis

    2012-01-01

    Objetivo Analizar los factores asociados con el uso inconsistente de condón en hombres que tienen sexo con hombres (HSH) de Ciudad Juárez, Chihuahua. Material y métodos Se realizó un estudio observacional, transversal y analítico con una muestra por conveniencia (n=186) de HSH de Ciudad Juárez. Las variables independientes fueron: nivel socioeconómico, actitudes hacia del uso del condón, uso de drogas, consumo de alcohol, identidad por orientación sexual y la discrimina­ción por orientación s...

  19. Double Exposure and the Climate Gap: Changing demographics and extreme heat in Ciudad Juárez, Mexico

    Science.gov (United States)

    Collins, Timothy W.; McDonald, Yolanda J.; Aldouri, Raed; Aboargob, Faraj; Eldeb, Abdelatif; Aguilar, María de Lourdes Romo; Velázquez-Angulo, Juárez Gilberto

    2013-01-01

    Scholars have recognized a climate gap, wherein poor communities face disproportionate impacts of climate change. Others have noted that climate change and economic globalization may mutually affect a region or social group, leading to double exposure. This paper investigates how current and changing patterns of neighborhood demographics are associated with extreme heat in the border city of Juárez, Mexico. Many Juárez neighborhoods are at-risk to triple exposures, in which residents suffer due to the conjoined effects of the global recession, drug war violence, and extreme heat. Due to impacts of the recession on maquiladora employment and the explosion of drug violence (since 2008), over 75% of neighborhoods experienced decreasing population density between 2000 and 2010 and the average neighborhood saw a 40% increase in the proportion of older adults. Neighborhoods with greater drops in population density and increases in the proportion of older residents over the decade are at significantly higher risk to extreme heat, as are neighborhoods with lower population density and lower levels of education. In this context, triple exposures are associated with a climate gap that most endangers lower socioeconomic status and increasingly older aged populations remaining in neighborhoods from which high proportions of residents have departed. PMID:25642135

  20. Capacitación de líderes comunitarios como gestores sociales en Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    Carmen Álvarez

    2015-01-01

    Full Text Available El trabajo consiste en describir el desarrollo de un esquema de capacitación de líderes co - munitarios. El enfoque de la formación está dirigido a la gestión de proyectos de incidencia en las comunidades, basándose en diagnósticos participativos. El taller de formación de líderes comunitarios fue desarrollado por la Comisión Nacional para Prevenir y Erradicar la Violencia contra las Mujeres (Conavim en conjunto con la Universidad Autónoma de Ciudad Juárez y la Fundación del Empresariado Chihuahuense (Fechac y se diseñó tomando en consideración el ambiente de crisis social y de seguridad por la que atravesó Ciudad Juárez, así como en las necesidades de capacitación de promotores sociales expresadas en el programa “Todos somos Juárez”.

  1. O direito da guerra em Francisco Suárez: o projeto civilizador da Escolástica Espanhola

    Directory of Open Access Journals (Sweden)

    Paulo Emílio Borges de Macedo

    2013-03-01

    Full Text Available O presente texto analisa o direito da guerra em Francisco Suárez. Menos uma explanação sobre um ramo do direito internacional, neste trabalho, busca investigar-se a origem deste direito, sob uma ótica bastante particular. Trata-se de reconstruir o intento de um dos maiores expositores da Escolástica Espanhola para salvar uma tradição cristã muito antiga da sua destruição. A doutrina da guerra justa, embora de origem cristã, corresponde a um dos maiores esforços da humanidade como um todo para limitar a violência da guerra, mesmo antes da existência de um direito internacional. Para manter a validade das proposições da teoria da guerra justa – e minimizar os efeitos da guerra –, Suárez precisou alterar-lhe o fundamento: de doutrina religiosa, ela se tornou jurídica.

  2. Suárez, el derecho natural y la crítica contemporánea

    Directory of Open Access Journals (Sweden)

    Sebastián Contreras

    2017-07-01

    Full Text Available Los actuales defensores de la teoría de la ley natural, en su mayoría, sindican a Suárez como el responsable de introducir una interpretación fisicalista de santo Tomás. Por fisicalismo entienden la doctrina moral según la cual las acciones son buenas o malas por comparación a la naturaleza. Se trata, entonces, de la identificación de la ley natural con la naturaleza racional. Suárez, sin embargo, rechaza esta posición, argumentando que la naturaleza no es una regla moral sino el fundamento de los principios naturales. El trabajo, pues, consiste en una revisión de la filosofía suarista sobre la ley natural, con un énfasis especial en la crítica que hacen de ella los autores de la filosofía contemporánea.

  3. Un texto inédito de Wenceslao Fernández Flórez. "¡S.O.S.! ¡Aquí Europa!"

    Directory of Open Access Journals (Sweden)

    María Teresa BARBADILLO

    2009-11-01

    Full Text Available Publicamos aquí un texto inédito de Wenceslao Fernández Flórez contenido en 23 cuartillas escritas de su puño y letra, que me fueron confiadas generosamente por sus sobrinos Wenceslao y Antonio Fernández Flórez. El manuscrito no lleva fecha alguna, y el sobre que lo contenía sólo reproduce el título, con la indicación «Charla radiofónica». Don Antonio Fernández Flórez tiene idea de que data de 1934 ó 35, posiblemente del mes de octubre. No obstante, ni en la prensa de esos años, ni en los archivos del Servicio de Documentación escrita de Radio Nacional de España —en donde nos atendieron con suma amabilidad— queda constancia de esta intervención de Fernández Flórez a través de las ondas.

  4. Book Review / Reseña:GUBERN, R., MONTERDE, J. E., PÉREZ PERUCHA, J., RIAMBAU, E. y TORREIRO, C., Historia del cine español

    Directory of Open Access Journals (Sweden)

    Jesús F. Pascual Molina

    2009-07-01

    Full Text Available Reseña del libro: GUBERN, R., MONTERDE, J. E., PÉREZ PERUCHA, J., RIAMBAU, E. y TORREIRO, C., Historia del cine español, Madrid, Ediciones Cátedra, 2009. 652 pp. ISBN: 978-84-376-2561-4.

  5. Review of Arciaga, Juárez y Mendoza (Coords. (2013. Introducción a la Psicología Social

    Directory of Open Access Journals (Sweden)

    Ali Lara

    2014-11-01

    Full Text Available Reseña del libro: Salvador Arciaga Bernal, Juana Juárez Romero y Jorge Mendoza Garcia  (coord. (2013. Introducción a la Psicología Social. México: UAM-MAPorrúa. ISBN 978-607-28-0109-7

  6. El oficio de docente en las novelas de Pérez Galdós / The teacher labour in the novels of Pérez Galdós

    Directory of Open Access Journals (Sweden)

    Ana-María Montero_Pedrera

    2017-01-01

    Full Text Available Resumen Este artículo analiza el oficio de docente en las novelas contemporáneas de Pérez Galdós. En ellas describe innumerables temas y personajes, entre ellos los maestros y maestras, con los que ejemplifica diversos tipos humanos con características bien definidas. Se ha usado el método histórico-educativo para el estudio y en los modelos hallados hay docentes bondadosos, con reminiscencias krausistas, como Máximo Manso en El amigo Manso; ramplones y faltos de vocación como José Ido en Tormento. Sublimes maestras como Atenaida, en La razón de la sinrazón; o doña Lupe, avara e impostora, en Fortunata y Jacinta. Pero, hemos hallado valores en el Magisterio; noble profesión, maltratada tradicionalmente por la sociedad y por los poderes públicos. Abstract This article discusses the teaching profession in Pérez Galdós’ contemporary novels. It describes many topics and characters, including teachers, with who exemplifies various human types with defined characteristics. The historicaleducational method is been used for the analysis. In the models found there are caring teachers, with Krausists reminiscences as Máximo Manso in El amigo Manso; Simples and with a lack of vocation as José Ido in Torment. Sublime teachers as Atenaida, in La razón de la sinrazón; or Dona Lupe, greedy and impostor, in Fortunata y Jacinta. But we have in the Magisterium values; noble profession, traditionally mistreated by society and by the government.

  7. The city that makes the Maquila: The case of Ciudad Juárez (México)

    OpenAIRE

    Rodríguez Álvarez, Olga Lucía

    2007-01-01

    La configuración del espacio urbano de las ciudades depende en alto grado de los diversos momentos de las actividades productivas y es a partir de ellos que se dan las transformaciones en el espacio urbano. En el caso de Ciudad Juárez, México la inserción de la industria maquiladora de exportación como la "mano invisible" que llevara el desarrollo y progreso a través de la transición de una economía primaria a una secundaria, le imprimió una nueva dinámica y configuración espacial. A casi tre...

  8. Raising Children in a Violent Context: An intersectionality approach to understanding parents' experiences in Ciudad Juárez.

    Science.gov (United States)

    Grineski, Sara E; Hernández, Alma A; Ramos, Vicky

    2013-01-01

    Children and parents' daily lives are rarely highlighted in coverage of drug wars. Using 16 interviews with parents in the Mexican border city of Juárez in 2010, we examine how drug violence impacts families with a focus on intersections of gender and social class. Related to mobility (the first emergent theme), fathers had increased mobility as compared to mothers, which caused different stresses. Material hardships heightened mothers' isolation within the home, and mothers more often had to enforce children's mobility restrictions, which children resisted. Related to employment (the second emergent theme), fathers took on dangerous jobs to provide for the family while mothers had fewer options for informal employment due to violence. In sum, men and women faced different challenges, which were intensified due to class-based material disadvantages. Conformity with traditional gender expectations for behavior was common for men and women, illustrating the normalization of gender inequality within this context.

  9. Castigo divino, de Sergio Ramírez, novela policial, folletinesca, satírica y autorreflexiva

    Directory of Open Access Journals (Sweden)

    Gisela Kozak Rovero

    2014-06-01

    Full Text Available La historia de Castigo divino, del nicaragüense Sergio Ramírez (1942, podría figurar perfectamente en las páginas de cualquier periódico amarillista. Sexo, dinero, poder, muerte y equívoco son los ingredientes perfectos de un suceso estremecedor capaz de despertar el morbo colectivo: un triple asesinato con estricnina, perpetrado por un joven abogado de veinticinco años en las personas de su propia esposa, una posible amante y el padre de ésta. La novela se construye a modo de expediente del caso, combinando registros diversos y divergentes, propios de la industria cultural y de discursos “no literarios”, como se evidencia sin problemas con un simple repaso de los títulos de las partes y capítulos del texto.

  10. Participación ciudadana en las colonias sin agua potable y alcantarillado de Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    Gustavo Córdova Bojórquez

    2007-01-01

    Full Text Available En este artículo se presenta un análisis de la participación ciudadana en la gestión del agua en 14 colonias que carecen del servicio de agua potable y alcantarillado en Ciudad Juárez, Chihuahua. La metodología consistió en analizar y relacionar las influencias externas e internas de los ciudadanos resultando una participación ciudadana muy baja en la gestión del agua determinada en gran medida por el poco conocimiento sobre el tema, la poca confianza en las instituciones públicas, la mínima disposición de participar en proyectos comunitarios y por la gran influencia que tiene el sistema político en la gestión del servicio.

  11. El primer volumen de Notas de un reporter de Alejandro Pérez Lugín

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    Julia María Labrador Ben

    2006-12-01

    Full Text Available Alejandro María de las Mercedes Pedro Pérez García Lugín nació el 22 de febrero de 1870 en Madrid. Era hijo de Antonio Pérez Serrano, natural de Cabra (Córdoba, y de María  Josefa  del  Carmen  García  Lugín  y  Castro,  natural  de  Santa  María  del  Camino (Santiago de Compostela2. En 1883 se trasladó con su familia a Santiago de Compostela, donde sus padres instalarían una céntrica y lujosa camisería llamada «El Buen Gusto», nombre que se convertiría en el apodo por el que Alejandro era conocido entre sus compañeros de estudios y amigos3. Ingresó en la Universidad de Santiago de Compostela para estudiar la carrera de Derecho y alcanzó la Licenciatura en 1891. Cuando tenía tan solo dieciocho años falleció su madre4. Esa etapa fue decisiva para su posterior actividad tanto  periodística  como  literaria. Todas  sus  vivencias  estudiantiles  constituirán  mucho más tarde la base de su primera novela, La Casa de la Troya (1915, a la que le corres- ponde el mérito de ser la novela española con mayor número de ediciones después de El Quijote y que aún hoy se sigue reeditando.

  12. MSR - SPHINX concept program Eros (Experimental zero power Salt reactor SR-0) - The proposed experimental program as a basis for validation of reactor physics methods

    Energy Technology Data Exchange (ETDEWEB)

    Hron, M.; Juricek, V.; Kyncl, J.; Mikisek, M.; Rypar, V. [Nuclear Research Institute Rez plc, Rez (Czech Republic)

    2007-07-01

    The Molten Salt Reactor (MSR) - SPHINX (SPent Hot fuel Incinerator by Neutron fluX) concept solves this principal problem of spent fuel treatment by means of so-called nuclear incineration. It means the burning of fissionable part of its inventory and transmutation of other problematic radionuclides by use of nuclear reactions with neutrons in a MSR-SPHINX system. This reactor system is an actinide burner (most in resonance neutron spectrum) and a radionuclide transmuter in a well-thermalized neutron spectrum. In the frame of the physical part, there are computational analyses and experimental activities. The experimental program has been focused, in its first stage, on a short-term irradiation of small size samples of molten-salt systems as well as structural materials proposed for the MSR blanket in the field of high neutron flux of research reactors. The proposed next stage of the program will focus on a large-scale experimental verification of design inputs by use of MSR-type inserting zones into the existing light water moderated experimental reactor LR-0, which may allow us to modify it into the experimental zero power salt reactor SR-0. There will be a detail description of the proposed program given in the paper together with the so far performed experiments and their first results. These realized experiments help us also to verify computational codes used, and to recognize some anomalies related to molten fluorides utilization. (authors)

  13. 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

  14. Las culpas del Rey y de su Favorito. El proceso a Alonso Ramírez de Prado (1607-1608

    Directory of Open Access Journals (Sweden)

    Giuseppe MROZEK ELISZEZYNSKI

    2013-01-01

    Full Text Available El enorme poder alcanzado por el letrado Alonso Ramírez de Prado en los primeros ocho años (1598-1606 del reinado de Felipe III fue resultado directodel dominio que su patrón, el duque de Lerma, ejerció sobre la corte y el joven rey. El 26 diciembre de 1606, su repentina detención puso fin a una rutilante carrera política y empezó un proceso, descuidado por mucho tiempo por los historiadores, junto al conde de Villalonga, don Pedro Franqueza. A través del análisis de la documentación oficial relativa a la causa de Ramírez de Prado, el presente trabajo pretende ilustrar las diferentes razones de la acusación y,sobre todo, los argumentos de la defensa, encargada al hijo del acusado, don Lorenzo Ramírez de Prado. El veredicto de culpabilidad emitido al final del proceso parecía anular cualquier argumento de la defensa. Sin embargo, el debate sobre la responsabilidad del soberano con respecto al poder de susfavoritos continuó a lo largo de las décadas siguientes.The huge power achieved by the jurist Alonso Ramírez de Prado in the firsteight years (1598-1606 of the reign of Philip III was a direct result of the supremacy of his patron, the Duke of Lerma, over the whole court and theyoung king. On December 26, 1606, his sudden arrest brought his brilliantcareer in politics to an end and started a trial, overlooked for a long time by historians in favor of the concurrent one against the Earl of Villalonga, PedroFranqueza. Through the analysis of the official documentation about the case of Ramírez de Prado, the article aims to illustrate the many reasons of the prosecution and, above all, the arguments of the defence, entrusted to his son, Lorenzo Ramírez de Prado. The verdict of guilty returned at the end of the process seemed to erase any argument of the defence. However, the debateabout the responsibilities of the sovereign in relation to the power of his favourites was destined to continue in the following decades

  15. H Reactor

    Data.gov (United States)

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

  16. Pulmonary effects of active smoking and secondhand smoke exposure among adolescent students in Juárez, Mexico

    Directory of Open Access Journals (Sweden)

    Bird Y

    2016-06-01

    Full Text Available Yelena Bird,1 Hugo Staines-Orozco2 1School of Public Health, University of Saskatchewan, Saskatoon, SK, Canada; 2Institute of Biomedical Sciences, Universidad Autónoma de Ciudad Juárez, Anillo Envolvente del PRONAF y Calle Estocolmo, Ciudad Juárez, Chihuahua, Mexico Background: Youth smoking trends among Latin American countries, including Mexico, are on the rise. Notably, although the high prevalence of smoking in teens has been well documented in the literature, few studies have evaluated the impact of smoking and secondhand smoke (SHS exposure on their respiratory system.  Objective: To investigate the effects of smoking and SHS exposure on the respiratory health and lung function among eighth-grade students in Juárez, Mexico. Methods: A cross-sectional study was undertaken on a sample of convenience. The study outcomes centered on evaluating 300 students’ lung function by spirometry (forced expiratory volume in 1 second [FEV1], forced expiratory volume in 1 second/forced vital capacity ratio [FEV1/FVC], and forced mid-expiratory flow rate [FEF25%–75%] and their respiratory health (smoking behavior and SHS exposure by their self-reported responses to a standardized respiratory questionnaire. The study outcomes were compared among three distinct groups: 1 nonsmokers/nonexposed to SHS; 2 nonsmokers/exposed to SHS; and 3 smokers. Results: The majority of the study participants were 14 years old (85%, females (54%, who attended eighth grade in a public school setting (56%. Approximately, half reported being of low socioeconomic status (49% and nonsmokers/exposed to SHS (49%. The lung function parameters of smokers were found to be lower (FEV1 =62.88±10.25; FEV1/FVC =83.50±14.15; and FEF25%–75% =66.35±12.55 than those recorded for the nonsmokers/exposed to SHS (FEV1 =69.41±11.35; FEV1/FVC =88.75±15.75; and FEF25%–75% =78.90±14.65 and significantly reduced when compared to the nonsmokers/nonexposed to SHS (FEV1 =79.14±13

  17. Influencia de aspectos bioéticos en la planificación familiar en Santos Suárez

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    Marianela de la C Prendes Labrada

    1999-01-01

    Full Text Available Se realizó un estudio descriptivo de corte transversal en 151 pacientes de la consulta de Planificación Familiar en el Policlínico Santos Suárez entre abril y junio de 1997, con el objetivo de mostrar cómo influyen algunos aspectos bioéticos en la selección, así como en la continuidad del uso de los métodos anticonceptivos y en la satisfacción de las necesidades del individuo. Se aplicó una encuesta y se siguió a los pacientes durante un año. Los datos se procesaron según el cálculo porcentual. Se concluyó que la adecuada capacitación técnica del equipo multidisciplinario, la selección informada, asesoramiento adecuado y respeto de las creencias individuales, socioculturales y de los principios morales, influyeron en los resultados positivos de la selección y continuidad del uso de los métodos anticonceptivos y en la satisfacción de las necesidades del individuo en la consulta de Planificación Familiar.A descriptive cross-sectional study of 151 patients from the Family Planning Department of the "Santos Suárez" Polyclinic was conducted between April and June, 1997, aimed at showing how some bioethical aspects influence on the selection, and continuity of the use of contraceptive methods, and on the satisfaction of the individual’s needs. A survey was done and patients were followed up for a year. Data were processed by percent calculation. It was concluded that the adequate technical training of the multidisciplinary team, the reported selection, the appropiate counseling, and the respect of the individual and sociocultural beliefs, and of the moral principles influenced on the positive results of the selection and continuity of the utilization of the contraceptive methods as well as on the satisfaction of the patients’ needs at the Family Planning Department.

  18. Pesquisaje de cáncer de mama en la comunidad de Santos Suárez

    Directory of Open Access Journals (Sweden)

    Marianela Prendes Labrada

    1998-04-01

    Full Text Available Se realiza un estudio descriptivo en 3 consultorios del área del Policlínico "Santos Suárez" en el año 1996 con el objetivo de determinar la incidencia de cáncer de mama y la utilización de métodos de detección precoz. Se informa que la muestra estuvo constituida por 600 mujeres mayores de 20 años seleccionadas al azar a las cuales se les hizo el pesquisaje y se les aplicó una encuesta. Se encuentra que la incidencia de cáncer mamario fue del 3 %. El 22,5 % de las mujeres se clasificaron como de alto riesgo de padecer el cáncer y el 83,3 % de los cánceres mamarios se detectaron en mujeres con alto riesgo y más de 50 años. Se señala que el 58,2 % de la muestra no conoce el autoexamen de mama y el 64 % no lo practica. Al 45,1 % de las mujeres nunca se le había realizado el examen clínico de las mamasA descriptive study of 3 physicians'offices from Santos Suárez polyclinic was carried out in 1996 aimed at determining the incidence of breast cancer and the use of early diagnosis methods. It is stressed that 600 randomly chosen women over 20 were included in the sample, who were screened and applied a survey. The breast cancer incidence rate was 3 %. 22.5 % of sampled women was clasified as high breast cancer risk subjects whereas 83.3 % of detected breast cancer was found in high risk women over 50. 58.2 % of them has no idea about the breast self-examination and 64 % does not put it into practice. 45.1 % of women has never been breast-screened before

  19. First record and description of male Rhopalione sinensis Markham, 1990, from China, with remarks on genus Rhopalione Pérez, 1920 (Crustacea: Isopoda: Bopyridae)

    Science.gov (United States)

    An, Jianmei; Niu, Xiaoqian; Markham, John C.; Jiang, Wei

    2014-05-01

    The bopyrid isopod species Rhopalione sinensis Markham, 1990, is recorded for only the second time, from a new locality in China outside Hong Kong, the type-locality. This is also the first finding of the male R. sinensis, which is herein described. Its host, Arcotheres sinensis (Shen, 1932) is a new record. A review of the four known species of Rhopalione Pérez, 1920, an updated diagnosis of the genus and a key to species are provided.

  20. Algunas novelas de Darío Fernández-Flórez: de Zarabanda (1944 a Alta Costura (1954. Temas escabrosos en tiempos de restricciones moralistas

    Directory of Open Access Journals (Sweden)

    Montejo Gurruchaga, Lucía

    2008-06-01

    Full Text Available Dario Fernández-Flórez begins in 1944 with Zarabanda a narrative style of intellectual eroticism and inmoral atmosphere which attracted no attention. Six years later he published Lola, espejo oscuro the recollections of a high prostitute. The novel was an scandal and an immediate success. Although the topic and its treatment were odd at the time because the strict moral values which mantained Franco´s regime were ignored, the novel was published with no cuts at all. Censorship was deaf to all the voices that warned of its dangers. This had an explanation: Darío Fernández-Flórez held an important post in the Propaganda National Service. After his dismissal censors were less lenient.Darío Fernández-Flórez inicia en 1944 con Zarabanda una narrativa de erotismo intelectualizado y ambiente amoral que no tuvo ningún eco. Seis años después publicará Lola, espejo oscuro, las memorias de una prostituta de alto copete. La novela suscitó un gran escándalo y su éxito fue inmediato. Aunque el tema y su tratamiento eran inusitados en aquellos momentos porque la obra daba al traste con los estrictos valores morales que sustentaban el régimen franquista, la novela fue publicada sin recortes; la censura hizo oídos sordos a todas las voces que alertaban de su peligro. Este hecho tiene una explicación: Darío Fernández-Flórez ocupaba un cargo importante en el Servicio Nacional de Propaganda. Tras su cese, los censores serán menos benevolentes.

  1. Photon spectrum behind biological shielding of the LVR-15 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Klupak, V.; Viererbl, L.; Lahodova, Z.; Marek, M.; Vins, M. [Research Centre Rez Ltd., Husinec-Rez 130 (Czech Republic)

    2011-07-01

    The LVR-15 reactor is a light water research reactor situated at the Research Centre Rez, near Prague. It operates as a multipurpose facility with a maximum thermal power of 10 MW. The reactor core usually contains from 28 to 32 fuel assemblies with a total mass of {sup 235}U of about 5 kg. Emitted radiation from the fuel caused by fission is shielded by moderating water, a steel reactor vessel, and heavy concrete. This paper deals with measurement and analysis of the gamma spectrum near the outer surface of the concrete wall, behind biological shielding, mainly in the 3- to 10-MeV energy range. A portable HPGe detector with a portable multichannel analyzer was used to measure gamma spectra. The origin of energy lines in gamma detector spectra was identified. (authors)

  2. The human dimension of AIDS in Cuba: Jorge Pérez MD MS, Director, Pedro Kourí Tropical Medicine Institute. Interviewed by Gail Reed.

    Science.gov (United States)

    Pérez, Jorge

    2011-04-01

    Except for the people living with the disease, no others have so immersed themselves in Cuba's world of HIV/AIDS as Dr Jorge Pérez. It is a world of Cuban returnees from Angola's war against apartheid South Africa, gay and bisexual men, housewives, transactional sex workers, rebellious teenagers, and infected surgeons and scientists-a cultural kaleidoscope reflecting all the faces of AIDS. To more than one international author, he is simply "Cuba's AIDS doctor." Speaking to his patients at the Pedro Kourí Tropical Medicine Institute in Havana, it is easy to see why, but also to appreciate the courage, compassion, and persistent search for new knowledge that characterize the Institute's staff as a whole. Dr Pérez's story-now told in two books based on his diaries-is not his alone. MEDICC Review held two interview sessions with Jorge Pérez just days apart at the beginning of April: one before and one after his designation as the new Director of the Tropical Medicine Institute, where he previously served as Deputy Director and Chief of Hospital Services. More than strictly medical matters, the conversation turned to the human dimension of HIV/AIDS, the depth to which it has touched many directly and affected Cuban society as a whole, and the challenges ahead for Cuba's flagship institution for research and treatment of infectious diseases.

  3. Renzo Ramírez Bacca. Historia Laboral de una hacienda cafetera: La Aurora, 1882-1982

    Directory of Open Access Journals (Sweden)

    Jesús Fernando Barrios Ordóñez

    2011-01-01

    Full Text Available El libro de Renzo Ramírez Bacca, historiador y profesor asociado adscrito al Departamento de Historia de la Universidad Nacional de Colombia, sede Medellín, es el resultado de una investigación profunda y documentada que tiene como propósito analizar los sistemas de organización laboral y las formas de ordenamiento administrativo y productivo en la hacienda cafetera La Aurora, ubicada en el actual municipio de El Líbano, en el departamento del Tolima. Esta hacienda fue una de las mayores del norte del Tolima, en la cual se adoptaron sistemas modernos de producción, relacionados, en un principio, con el sistema de aparcería, categoría de trabajadores permanentes con base en la fuerza de trabajo familiar, bajo la figura de arrendatarios, tabloneros, contratistas, partijeros y agregados. Posteriormente, la tecnificación cafetera se sustituye por la administración directa, que utiliza fuerza de trabajo asalariada temporal, modificando las relaciones laborales de tipo familiar que prevalecían en la hacienda.

  4. Characterization of the Water Quality Status on a Stretch of River Lérez around a Small Hydroelectric Power Station

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    Enrique Valero

    2012-10-01

    Full Text Available The renewable energy emerged as a solution to the environmental problems caused by the conventional sources of energy. Small hydropower (SHP is claimed to cause negligible effects on the ecosystem, although some environmental values are threatened and maintenance of an adequate water quality should be ensured. This work provides a characterization of the water quality status in a river stretch around a SHP plant on river Lérez, northwest Spain, for four years after its construction. The ecological and chemical status of the water as well as the ecological quality of the riparian habitat, were used as measures of quality. Data were compared with the water quality requirements. The variations in the quality parameters were analyzed over time and over the river sections with respect to the SHP plant elements. Two years after construction, the temperature and dissolved oxygen values achieved conditions for salmonid water and close to the reference condition, while pH values were low. The Iberian Biological Monitoring Working Party (IBMWP index showed a positive trend from two years after the construction and stabilized at “unpolluted or not considerably altered water”. Quality parameters did not present significant differences between sampling points. The SHP plant construction momentarily altered the quality characteristics of the water.

  5. differentiation in agritourism ventures of a Group of Rural Change (INTA in Coronel Suárez (Buenos Aires

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    Marina Cordisco

    2013-12-01

    Full Text Available From the converged concepts identity, culture, heritage and territory, is analyzed the possibility of formulating and implementing a strategy of differentiation for the agritourism activity developed by farms of group Cortaderas II (Cambio Rural, INTA, in Coronel Suárez (province of Buenos Aires. With this aim was made a diagnostic through direct interviews and observations of the farms involved. Emphasizing own aspects of its rural environment, was tried to identify cultural values and products with territorial anchorage that they impose a distinctive stamp to the tourist service that they offer. In addition, was investigated in what measure the members are prepared to manage the business, recognizing in them managerial competitions and enterprising characteristics. Finally, it is thought over brings over of the degree of maturity reached, typifying the individual enterprise culture and according to the group work, of way of evaluating if the putting in value of its resources evolves from a " domestic character " up to coming to a " commercial formal character ". It is observed the construction of a socio- cultural-economic identity that makes viable a competitive differential strategy with anchorage in the territory, as well as conditions for the development of the most formalized tourist activity based on the quality management

  6. Francisco Suárez en la vida de su tiempo y en la del nuestro. Editorial

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    Juana María Gil Ruiz

    2017-09-01

    Full Text Available Con la aparición de este número dedicado —como no puede ser de otro modo— a Francisco Suárez, en la vida de su tiempo y en la del nuestro, con motivo del cuarto centenario de su fallecimiento, ACFS inaugura una nueva etapa —la tercera— que pretende, además de aprovechar este homenaje, afrontar los nuevos retos planteados por la sociedad-economía del conocimiento y sus variados indicadores —formales— de medición de calidad. Es cierto que lo que marca la calidad, al menos la científica, debería sobrepasar cualquier requisito formal, pero más allá de lo que siempre debió y debe ser lo importante, el fondo, las revistas jurídicas han tenido que reinventarse para cumplir con los requerimientos de indexación exigidos por las reconocidas Bases de Datos.

  7. Bolívar, Juárez y Guevara: apuntes sobre socialización e identidad

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    Pedro António Da Silva-Abrantes

    2011-01-01

    Full Text Available A través de un análisis de las biografías de Bolívar, Juárez y Guevara, se discute la compleja relación entre socialización, identidad y cambio social, en los tiempos modernos. Tras un debate inicial sobre los usos y limitaciones del método biográfico, se busca comprender la vida de los tres personajes históricos, utilizando y buscando explorar algunas teorías sociológicas recientes. Se concluye que, en los tres casos, la integración desde temprana edad a distintos entornos sociales y, en particular, a procesos educativos múltiples resultantes de distintos movimientos político-pedagógicos, ocurrencias biográficas imprevistas e incluso a partir de cierta edad, de un trabajo consciente de los actores sobre sí mismos, permitió la formación de un habitus de fusión. Se argumenta que esta identidad peculiar personificó (y promovió la unificación de fuerzas sociales en conflicto.

  8. Coverage of violence in risk areas: case of the Ciudad Juárez´Journalist Association

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    José Luis González-Esteban

    2016-11-01

    Full Text Available This research analyzes the situation of journalism in a high risk area, Ciudad Juarez, Mexico. The analysis is based on the knowledge and analysis of the training activity, violence and corruption denounced by Juarez Journalists Association, founded and run by women journalists. A meeting with journalists of the association and in-depth interviews are the main methodological tools to understand the meaning and value of this group of juarenses journalists. In the same way this article analyzes, through a quantitative methodology, the strategy of activism and the international projection of the association through their social networks. In addition, research is completed with a content analysis about the prevalence and significance of the ‘red note’ in El Diario de Juárez, the main newspaper in this border area, which even has a delegation in the US city of El Paso. Coverage of violence in high risk areas gives a special value to journalism in newspapers like the aforementioned and corporate work of this group of juarenses journalists.

  9. José Gestoso y Pérez. Teoría y Praxis de la Conservación

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    Mª Dolores Ruiz de Lacanal Ruiz-Mateos

    2013-12-01

    Full Text Available El objetivo de este artículo es hacer una reflexión sobre las aportaciones que José Gestoso y Pérez (1852-1917 realiza a la teoría y la praxis de la conservación. Persona de gran prestigio y mérito, desarrolló su labor profesional en Sevilla a mediados del siglo XIX y principios del siglo XX y ha sido objeto de numerosas investigaciones. Tras la lectura de los estudios, que le resaltan como un referente claro de la cultura sevillana en sus múltiples manifestaciones, (Historia y crítica del Arte, Arqueología, Archivística, etc., este artículo concentra la atención en sus propios textos, para descubrir que constituyen un conjunto coherente y estructurado de conocimientos teóricos y prácticos, aportan unos objetivos definidos y una metodología con recursos y estrategias, que son claros antecedentes de nuestros actuales “planes” de conservación.

  10. Radioactive waste management at WWER type reactors

    International Nuclear Information System (INIS)

    1993-05-01

    This report was prepared within the framework of the Technical Assistance Regional Project on Advice on Waste Management at WWER Type Reactors, which was initiated by the IAEA in 1991. The Regional Project is an integral part of the IAEA's activities directed towards improvement of the safety and reliability of nuclear power plants with WWER type reactors (Soviet designed PWRs). Forty-five WWER type units are currently in operation and twenty-five are under construction in Bulgaria, Czechoslovakia, Finland, Hungary and the former USSR. The idea of regional collaboration between eastern European countries under the auspices of the IAEA was discussed for the first time during the last meeting of the Council for Mutual Economic Assistance (CMEA) on spent fuel and radioactive waste management, held in Rez, Czechoslovakia, in October 1990. Since then, the CMEA and some of its former Member States have ceased to exist. However, there are many reasons for eastern European countries to continue their regional collaboration at a higher level. The USSR, the designer and supplier of WWER type reactors in eastern European countries, participated in the first phase of the project. The majority of WWER type reactors are situated in States of the former USSR (Russia and Ukraine). The main results of the first phase of the Regional Project are: (i) Re-establishment of communication channels among eastern European countries operating WWER type reactors by incorporating the IAEA's technical assistance; (ii) Identification of common waste management problems (administrative and technical) requiring resolution; (iii) Familiarization with radioactive waste management systems at nuclear power plants with WWER type reactors - Paks (Hungary), Loviisa (Finland), Jaslovske Bohunice (Czechoslovakia) and Novovoronezh (Russian Federation). Tabs

  11. Naturaleza metodológica y actualidad de las «Disputaciones metafísicas» de Francisco Suárez

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    Martin GRABMANN

    2009-09-01

    Full Text Available RESUMEN: Las primera de las conmemoraciones en torno al pensamiento del teólogo y filósofo español Francisco Suárez (1548-1617, que después serán repetidas de forma regular, se produjo en el ámbito académico occidental entorno a la celebración del tercer centenario de su muerte. La universidad de Munich rindió tributo con la publicación del volumen colectivo titulado P. Franz Suarez, S. I. De entre aquellas páginas hemos querido recuperar y adaptar a la lengua castellana el estudio del prestigioso medievalista Martin Grabmann. La referencia a éste entre los especialistas en el pensamiento suareciano es un lugar común a la hora de precisar el carácter sintético y ecléctico de la obra metafísica de Suárez, así como para ilustrar la tesis de la penetración de sus ideas en el ámbito protestante. Es nuestra pretensión que la traducción que aquí presentamos auxilie tanto al historiador, a modo de recordatorio de un valor que generalmente no encuentra asiento en nuestros escritos ni en nuestras aulas, como al especialista, en la justa ponderación de sus rasgos y en especial, de su influencia.ABSTRACT: The first of the conmemorations about the thinking of the spanish theologian and philosopher Francisco Suárez (1548-1617, who later will be repeated of regular, was sucessed in the academic western area into around the celebration of the third centenary of his disappearance. The University of Munich, had shown tribute, printing the collective book called P. Franz Suárez, S. I. The reference to this study between the learners of Suárez is a common place at the moment of specifying the synthetic and eclectic character, of the Suárez’ metaphysical work, as well as reinforcement to the thesis of his fret in the Protestant area of the ideas. It is our pretension that the translation that we present helps so much the historian, as followup of a value that generally finds seat neither in our writings or in our lectures rooms, and

  12. Remediation of old ecological burdens in UJV Rez, a. s. - alpha hall

    International Nuclear Information System (INIS)

    Posvar, R.; Holubova, D.; Svoboda, K.

    2018-01-01

    Two research reactors, hot and semi-hot chambers, laboratories, radioactive waste disposal facilities and many other technologies are in operation at the Nuclear Power Plant site. As a result of these activities a significant amount of radioactive wastes, contaminated and irradiated materials, equipment and construction structures for disposal and disposal were created in the Nuclear Research Institute. These old radioactive loads can be characterized as ecological liabilities incurred prior to the privatization of the Nuclear Power Plant. The implementation of the rehabilitation works of the Nuclear Power Plant continued and continues to be successful. The results of regular monitoring confirm that there is no release of radioactive substances into the environment. This work focuses on the elimination of the alpha hall workplace in facility 250 - Radiochemistry. The Alpha Hall has been used to research and develop chemical separations and analyzes for uranium and transuranium elements in the fuel cycle chemistry (especially the separation and determination of plutonium, america, neptunium, curium and uranium). In 2015, this workplace was influenced a combination of age degradation with radiation degradation of one of the plastic packages to leakage of the Am and Pu compound. The contamination was local and within the limits of non-interference levels. The health of workers and the environment were not compromised. However, this event has led to an acceleration of the redevelopment of the workplace, which took place between 2016 and 2017. For this purpose, a working procedure was developed which regulates the way of remedial work, including the solidification of the most risky materials. (authors)

  13. Neutron absorption profile in a reactor moderated by different mixtures of light and heavy waters

    International Nuclear Information System (INIS)

    Nagy, Mohamed E.; Aly, Mohamed N.; Gaber, Fatma A.; Dorrah, Mahmoud E.

    2014-01-01

    Highlights: • We studied neutron absorption spectra in a mixed water moderated reactor. • Changing D 2 O% in moderator induced neutron energy spectral shift. • Most of the neutrons absorbed in control rods were epithermal. • Control rods worth changes were not proportional to changes of D 2 O% in moderator. • Control rod arrangement influenced the neutronic behavior of the reactor. - Abstract: A Monte-Carlo parametric study was carried out to investigate the neutron absorption profile in a model of LR-0 reactor when it is moderated by different mixtures of heavy/light waters at molecular ratios ranging from 0% up to 100% D 2 O at increments of 10% in D 2 O. The tallies included; neutron absorption profiles in control rods and moderator, and neutron capture profile in 238 U. The work focused on neutron absorption in control rods entailing; total mass of control rods needed to attain criticality, neutron absorption density and total neutron absorption in control rods at each of the studied mixed water moderators. The aim was to explore whether thermal neutron poisons are the most suitable poisons to be used in control rods of nuclear reactors moderated by mixed heavy/light water moderators

  14. INVESTIGACIONES ARQUEOLÓGICAS EN EL FORTÍN PESCADO, PARTIDO DE BENITO JUÁREZ, PROVINCIA DE BUENOS AIRES / Archaelogical research at Fortin Pescado, Benito Juárez county, Buenos Aires province

    Directory of Open Access Journals (Sweden)

    Vanesa Natalia Bagaloni

    2015-12-01

    Full Text Available En este trabajo se presentan los primeros resultados del estudio de los materiales recuperados en la localidad arqueológica Fortín Pescado, ubicada sobre la margen izquierda del arroyo Pescado Castigado, en el partido de Benito Juárez (provincia de Buenos Aires. Esta localidad se compone de dos sitios arqueológicos (Fortín Pescado 1 y Fortín Pescado 2 donde se efectuaron excavaciones y recolecciones en superficie y en el perfil de barrancas aledañas. El conjunto arqueológico de ambos sitios incluye restos faunísticos (mayormente animales domésticos, materiales vítreos (botellas cuadradas y cilíndricas, frascos, tarros y damajuanas, fragmentos de gres (botellas de ginebra y/o agua mineral, lozas (tazas y bowls ingleses, metales (clavos, botón, cuchilla y arma, ladrillos y un fragmento de bola de boleadora. Según diversos documentos escritos procedentes del Servicio Histórico del Ejército, del Archivo General de la Nación y del departamento de Geodesia, este fortín se instaló en 1858 y funcionó por lo menos hasta fines de 1863, cuando pasó a ser usado como posta militar hasta el fin de la década. A partir de las intervenciones arqueológicas y el relevamiento de las fuentes escritas se pudieron determinar áreas de actividades específicas (vivienda, descarte pautado y no pautado, corral dentro de esta localidad.  AbstractIn this paper the first results of the materials recovered at the Fortin Pescado archaeological locality are presented. This locality is situated on the left bank of Pescado Castigado stream (Benito Juárez County, Buenos Aires Province. It is composed by two sites (Fortin Pescado 1 and Fortin Pescado 2 where excavations and surface surveys were developed. Surface surveys were also conducted on the profiles of the surrounding canyons. The archaeological assemblages of both sites include faunal remains (mostly of domestic fauna/animals, glassy materials (square and cylindrical bottles, flasks, jars and jugs

  15. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

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

  16. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

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

  17. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

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

  18. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

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

  19. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

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

  20. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

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

  1. 1875 Los Estados de la costa y el conflicto político con Santiago Pérez

    Directory of Open Access Journals (Sweden)

    Dayana Angélica Rueda Cáceres

    2011-01-01

    Full Text Available Durante el periodo federal colombiano, a los Estados Soberanos de Panamá, Bolívar y Magdalena, se les identificó como Estados costeños, Estados del Norte o Estados del Atlántico. Panamá mantuvo fuertes vínculos con los demás Estados costeños auxiliándolos con material bélico, hombres y dinero en caso que fue necesario en las destinas contiendas ocurridas durante el periodo de 1855 - 1885. En el presente artículo se intenta a través de los acontecimientos políticos y bélicos de 1875, señalar, la participación de las Fuerzas del Estado soberano de Panamá en esta contienda y la relación u alianza político militar que mantuvieron los denominados Estados costeños.2 Dado que 1875 es un año bastante agitado, nos centraremos en el descontento de los Estados de la Costa con el Presidente de la Unión, Santiago Pérez, quien, según los primeros, buscaba favorecer tanto en campaña como en las urnas, la candidatura de Aquileo Parra como su sucesor frente a la emblemática figura del recién llegado al país Rafael Núñez, después de 10 años de ausencia.

  2. Profitability of Cedrela odorata L. in Agroforestry Systems with Coffee in Pérez Zeledón, Costa Rica

    Directory of Open Access Journals (Sweden)

    Mariela González-Rojas

    2017-12-01

    Full Text Available The objective of this research was to determine the production of cedar wood in agroforestry systems (AF with coffee, using a prediction model of the commercial volume obtained in the study area, as well as the profitability generated by the sale of coffee, wood and payment for environmental services (PPSA. The study was carried out in the canton of Pérez Zeledón, province of San José, Costa Rica. There were established 30 temporary sampling plots of 1000 m2 in AF with cedar between five and 17 years of age. The diameter growth (DBH and the commercial height (CH of the species were evaluated, as well as the management of the SAF (activities, inputs and yields and coffee production through the producer interview. The obtained models allowed to predict the commercial volume (m3 tree-1 according to age (R2 = 88.7%, DBH (R2 = 90.3% and CH (R2 = 97.2%. The average coffee production of the sampled sites was 26 fanegas ha-1 year-1. At the age of 17 years of the cedar, a production of 1.04 m3 tree-1 (92.13 m3 ha-1 of standing timber was obtained, which represented a financial contribution of 81% of the net present value (NPV of the AF in the analysis period. The estimated financial indicators allow concluding that the coffee-cedar AF is profitable since it generated a positive NPV of ₡ 8 198 601,5, an internal rate of return (IRR of 16% which was higher than the cost of money (discount rate of 6.1% and a B/C ratio of 1.34.

  3. La estructura espacial urbana y accesibilidad diferenciada a centros de empleo en Ciudad Juárez, Chihuahua

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    César M. Fuentes Flores

    2009-01-01

    Full Text Available Existen disparidades intraurbanas en los tiempos de traslado del viaje al trabajo en transporte público y privado, producto de una accesibilidad diferenciada a los centros de empleo en Ciudad Juárez, Chihuahua; el objetivo del artículo es explicarlas. La metodología empleada es el análisis espacial, además se elaboraron cuatro modelos de regresión simple estimados mediante la técnica de mínimos cuadrados ordinarios (MCO. Las variables se construyeron con información de la Encuesta de origen-destino de 1997, el XII Censo general de población y vivienda de 2000 y el XIII Censo económico de 1999, a nivel del área geográfica básica (AGEB. Los resultados de los modelos de regresión indican que el índice de accesibilidad, el balance entre empleos y viviendas, el valor del suelo y las variables aproximadas de uso del suelo (proporción de trabajadores en el sector secundario y terciario muestran efectos estadísticamente significativos al explicar diferencias en los tiempos de traslado al trabajo en transporte público. Así mismo, el índice de accesibilidad, valor del suelo y la proporción de trabajadores en el sector secundario incrementan dichos tiempos en transporte privado. Los resultados tienen implicaciones en términos de políticas de usos del suelo y planeación del transporte.

  4. Mujeres indígenas, gobierno y comunidad: El caso de mujeres tarahumaras en Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    Martha Estela Pérez García

    2016-01-01

    Full Text Available La situación de las mujeres indígenas en Chihuahua se caracteriza por la marginación, pobreza y desigualdad. Por esta razón, algunos(as miembros de la etnia rarámuri obligados por las necesidades más elementales, emigran con sus familias a las principales ciudades de la entidad. En el caso específico de la comunidad indígena asentada en Ciudad Juárez, Chihuahua, encontramos que son mujeres quienes dirigen las tareas de gobierno, rol tradicionalmente asignados a los hombres. El objetivo de este artículo es realizar un acercamiento de la participación femenina en el gobierno de la colonia tarahumara, con el propósito de conocer cómo se genera esta participación, sus liderazgos y las formas de resolución de sus problemas al interior de la comunidad. Para este propósito se realizaron entrevista con representantes de la comunidad y sus dos gobernadoras, además de un grupo focal con la presidenta y un grupo de mujeres. Los resultados de esta investigación mostraron dos cuestiones significativas: la situación de extrema vulnerabilidad en que viven las indígenas en el entorno urbano y que el gobierno femenino usa estrategias apegadas al rol de género para mantener el orden, el liderazgo y mejorar la calidad de vida de su comunidad.

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

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

  6. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

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

  7. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

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

  8. Multiregion reactors

    International Nuclear Information System (INIS)

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

    1979-08-01

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

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

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

  10. Thermal hydraulic analyses of LVR-15 research reactor with IRT-M fuel

    International Nuclear Information System (INIS)

    Macek, J.

    1997-01-01

    The LVR-15 pool-type research reactor has been in operation at the Nuclear Research Institute at Rez since 1955. Following a number of reconstructions and redesigning, the current reactor power is 15 MW. Thermal hydraulic analyses to demonstrate that the core heat will be safely removed during operation as well as in accident situations were performed based on methodology which had been specifically developed for the LVR-15 research reactor. This methodology was applied to stationary thermal hydraulic computations, as well as to transients, particularly with reactivity failure and loss of circulation pumps emergencies. The applied methodology and the core configuration as used in the Safety Report are described. The initial and boundary conditions are then considered and the summary of the calculated failures with regard to the defined safety limits is presented. The results of the core configuration analyses are also discussed with respect to meeting the safety limits and to the applicability of the methodology to this purpose

  11. Quaternary alluvial fans of Ciudad Juárez, Chihuahua, northern México: OSL ages and implications for climatic history of the region

    Science.gov (United States)

    Zúñiga de León, David; Kershaw, Stephen; Mahan, Shannon

    2016-01-01

    Alluvial fans formed from sediments derived from erosion of the Juárez Mountains in northernmost México have a significant flood impact on the Ciudad Juárez, which is built on the fan system. The northern part of Ciudad Juárez is the most active; further south, older parts of the fan, upon which the rest of the city is built, were largely eroded by natural processes prior to human habitation and subsequently modified only recently by human construction. Three aeolian sand samples, collected from the uppermost (youngest) parts of the fan system in the city area, in places where human intervention has not disturbed the sediment, and constrain the latest dates of fan building. Depositional ages of the Quaternary alluvial fans were measured using Optically Stimulated Luminescence (OSL) on aeolian sands that have inter-fingered with alluvial fan material. These dates are: a) sample P1, 31 ka; b) sample P2, 41 ka; c) sample P3, 74 ka, between Oxygen Isotope Stages (OIS) 3 to 5. They demonstrate that fan development, in the area now occupied by the city, terminated in the Late Pleistocene, immediately after what we interpret to have been an extended period of erosion without further deposition, lasting from the Late Pleistocene to Holocene. The three dates broadly correspond to global glacial periods, implying that the cool, dry periods may reflect periods of aeolian transport in northern México in between phases that were wetter to form the alluvial fans. Alluvial fan margins inter-finger with fluvial terrace sediments derived from the Río Bravo, indicating an additional component of fan dissection by Río Bravo lateral erosion, presumed to be active during earlier times than our OSL ages, but these are not yet dated. Further dating is required to ascertain the controls on the fan and fluvial system.

  12. La vegetación como sistema de control para las Islas de Calor Urbano en Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    Maria Goretti Salas Esparza

    2017-06-01

    Full Text Available A nivel mundial, el territorio ha experimentado un proceso de urbanización, el cual ha modificado las condiciones físicas y climatológicas como consecuencia de la densificación y construcción de las zonas urbanas, sobre todo a partir de la utilización de materiales que retienen el calor y que propician el fenómeno de isla de calor urbano (ICU, término establecido por Gordon Manley en 1958 (Fernández, 1996. Este trabajo evalúa el impacto que tienen las áreas verdes para actuar como sistema de control de isla de calor sobre Ciudad Juárez, Chihuahua, durante el verano del 2016. La metodología consistió en analizar cuatro áreas verdes para determinar la diferencia de temperatura que existe entre las zonas arboladas y las no arboladas, registrando temperaturas con sensores Hobo®, cada 15 minutos. Los resultados obtenidos demostraron que existe una diferencia de temperatura de 3,82 °C entre los lugares arbolados y no arbolados en el área verde con mayor nivel de vegetación, mientras que el área verde con menor nivel de vegetación se encontró una diferencia de 0,53 °C. Sin embargo, el impacto que tendrán sobre la zona urbana dependerá de la configuración y características de la misma área verde.   Documeto fianciado bajo el marco Tesis de Maestría en Planificación y Desarrollo Urbano " Áreas verdes como sistema de control para las Islas de Calor Urbano en Ciudad Juárez, Chihuahua".Universidad Autónoma de Ciudad Juárez

  13. 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.)

  14. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

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

  15. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

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

  16. On the taxonomic status of Liolaemus filiorum Pincheira-Donoso & Ramírez, 2005 (Iguania: Liolaemidae: A response to Pincheira-Donoso

    Directory of Open Access Journals (Sweden)

    Jaime Troncoso-Palacios

    2015-12-01

    Full Text Available I discuss the arguments put forth recently by Pincheira-Donoso, in which the author attempts to revalidate Liolaemus filiorum Pincheira-Donoso & Ramírez, 2005, a species which I had previously considered a junior synonym of L. puritamensis. The author of this revalidation omitted important information including: 1 the description was published without peer review, 2 one of the two types was deposited in a personal collection, 3 the diagnosis is weak and unclear, 4 the holotype was not explicitly described or illustrated. Additionally, the author did not discuss key aspects of my paper, most particularly, the incorrect designation of the holotype of L. filiorum.

  17. Señales desde una biblioteca perdida. Infortunios de Alonso Ramírez: identidad criolla y cuestión barroca

    OpenAIRE

    Becerra, Eduardo

    2010-01-01

    En los setenta y ochenta del siglo XX surge una corriente en la crítica cultural hispanoamericanista poscolonial, centrada en el discurso identitario y emancipador, enfrentada con los usos tradicionales de la filología. Infortunios de Alonso Ramírez(1690), basada en modelos novelescos áureos de éxito como el relato de aventuras, la novela de cautiverio, y la picaresca, es una de las obras más estudiadas. El artículo estudia los modelos retóricos de esta obra, su relación con la novela colonia...

  18. Maquiladoras de arneses automotrices: entre la producción de clase mundial y la precariedad laboral en Juárez

    Directory of Open Access Journals (Sweden)

    Martha Cecilia Miker Palafox

    2010-11-01

    Full Text Available This article show how the globalization process has impacted in the harness maquiladora industry in Ciudad Juárez and how job insecurity and world-class production can coexist in the production of automotive harness where two of the main local stakeholders (unions and the State are completely blurred and accomplices. The document is based mainly in the analysis of four cases of maquiladora plants producing automotive harnesses owned by world leading corporations, which concentrate over 90% of employment and harness production plants in the in the city.

  19. El discurso amoroso en la novela de la Restauración: las novelas de Benito Pérez Galdós

    OpenAIRE

    Pérez López, Ana María

    2006-01-01

    El objetivo de esta Tesis Doctoral ha sido el estudio de las concepciones amorosas que están presentes en la novela española de la Restauración (tomando como punto de referencia la obra de Benito Pérez Galdós), sobre todo, en lo que respecta a una visión idealista, y en una doble vertiente: 1,- La importancia del discurso amoroso para la conformación estructural y temática de estas obras, por tratarse de un componente esencial en la configuración sentimental, moral e intelectual de los person...

  20. Factores biosocioculturales y uso de métodos anticonceptivos en mujeres que acuden al hospital Elpidio Berovidez Pérez, Otuzco 2014.

    OpenAIRE

    Campos Jara, Clara Luz

    2015-01-01

    La investigación tuvo como objetivo general, determinar la relación entre los factores biosocioculturales: edad, estado civil, religión, escolaridad, rol de género con el uso de métodos anticonceptivos en mujeres que acuden al consultorio de obstetricia del Hospital Elpidio Berovidez Pérez, Otuzco 2014, fue de tipo cuantitativo–prospectivo, la muestra estuvo constituida por 115 mujeres de una población de 390, los datos se obtuvieron con la técnica de la entrevista. Obteniéndose los siguiente...

  1. Factores biosocioculturales y uso de métodos anticonceptivos en mujeres que acuden al Hospital Elpidio Berovidez Pérez, Otuzco 2014

    OpenAIRE

    Campos Jara, Clara Luz

    2016-01-01

    La investigación tuvo como objetivo general, determinar la relación entre los factores biosocioculturales: edad, estado civil, religión, escolaridad, rol de género con el uso de métodos anticonceptivos en mujeres que acuden al consultorio de obstetricia del Hospital Elpidio Berovidez Pérez, Otuzco 2014, fue de tipo cuantitativo–prospectivo, la muestra estuvo constituida por 115 mujeres de una población de 390, los datos se obtuvieron con la técnica de la entrevista. Obteniéndose los siguiente...

  2. LA GESTIÓN INTEGRAL DE LOS RESIDUOS SÓLIDOS URBANOS EN JUÁREZ: LECCIONES INNOVADORAS PARA OTROS MUNICIPIOS

    Directory of Open Access Journals (Sweden)

    Ismael Couto Benítez

    2012-06-01

    Full Text Available El arribo de la iniciativa privada a la gestión integral de residuos sólidos urbanos en el municipio de Ciudad Juárez promovió un nuevo mecanismo institucional para operar un servicio público que ha cumplido las expectativas de mejora y eficiencia establecidos por los indicadores de gerenciamiento para el servicio de limpieza pública, además de solventar el problema de la falta de presupuesto para el mantenimiento y renovación del equipo de recolección de basura. Este documento aborda, a partir de una revisión histórica de datos y entrevistas con los directivos de la empresa PASA y los funcionarios del gobierno municipal de Juárez, el modelo en que se gestó y la forma en que opera el servicio de limpia en uno de los cinco municipios más poblados de México. A partir de esta experiencia, se asumen nuevos retos para la administración de los servicios públicos municipales a partir de prácticas de negociación, calidad en el servicio, rendición de cuentas y control gubernamental.   ABSTRACT The integration of the private sector into comprehensive management of urban solid waste in the municipality of Ciudad Juárez shows a new institutional mechanism to operate a public service that has fulfilled the improvement and efficiency expectations established by managerial indicators for public sanitation services, in addition to overcoming the lack of budget provision for maintenance and renewal of waste collection equipment. By means of a historical revision of data as well as interviews with both executive directors of a garbage-collecting firm called PASA and officials of the municipal government of Ciudad Juárez, this document approaches the waste collection model that was created as well as the way in which the garbage collection service operates in one of the five most populated municipalities in Mexico. Based on this experience, the management of municipal public services assumed new challenges by using negotiation practices

  3. Comercio transfronterizo y su impacto en la región de El Paso-Ciudad Juárez: Una propuesta de financiamiento de la planeación binacional

    Directory of Open Access Journals (Sweden)

    Sergio Peña

    2003-01-01

    Full Text Available El presente artículo analiza el impacto del comercio transfronterizo en la región de El Paso-Ciudad Juárez, entendido como tal el valor de las compras que los consumidores mexicanos realizan en El Paso. Los resultados muestran que el monto de las ventas al menudeo en esta ciudad en el año 2000 excedieron en 33% los valores ajustados del modelo. Este último debe interpretarse como el efecto del comercio transfronterizo. Los impuestos generados por el comercio transfronterizo suman aproximadamente 125 millones de dólares y equivalen aproximadamente a los egresos brutos totales del municipio de Ciudad Juárez en el año 2000. El artículo pone de relieve la potencialidad que tendrían esos recursos para el financiamiento del desarrollo urbano binacional de El Paso y Ciudad Juárez

  4. 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

  5. The first critical experiment with a new type of fuel assemblies IRT-3M on the training reactor VR-I

    International Nuclear Information System (INIS)

    Matejka, Karel; Sklenka, Lubomir

    1997-01-01

    The paper 'The first critical experiment with a new type of fuel assemblies IRT-3M on training reactor VR-1 presents basic information about the replacement of fuel on the reactor VR-1 run on FJFI CVUT in Prague. In spring 1997 the IRT-2M fuel type used till then was replaced by the IRT-3M type. When the fuel was replaced, no change in its enrichment was made, i.e. its level remained as 36% 235 U. The replacement itself was carried out in tight co-operation with the Nuclear Research Institute Rez plc., as related to the operation of the research reactor LVR-15. The fuel replacement on the VR-I reactor is a part of the international program RERTR (Reduced Enrichment for Research and Test Reactors) in which the Czech Republic participates. (author)

  6. Pulmonary effects of active smoking and secondhand smoke exposure among adolescent students in Juárez, Mexico.

    Science.gov (United States)

    Bird, Yelena; Staines-Orozco, Hugo

    2016-01-01

    Youth smoking trends among Latin American countries, including Mexico, are on the rise. Notably, although the high prevalence of smoking in teens has been well documented in the literature, few studies have evaluated the impact of smoking and secondhand smoke (SHS) exposure on their respiratory system. To investigate the effects of smoking and SHS exposure on the respiratory health and lung function among eighth-grade students in Juárez, Mexico. A cross-sectional study was undertaken on a sample of convenience. The study outcomes centered on evaluating 300 students' lung function by spirometry (forced expiratory volume in 1 second [FEV1], forced expiratory volume in 1 second/forced vital capacity ratio [FEV1/FVC], and forced mid-expiratory flow rate [FEF25%-75%]) and their respiratory health (smoking behavior and SHS exposure) by their self-reported responses to a standardized respiratory questionnaire. The study outcomes were compared among three distinct groups: 1) nonsmokers/nonexposed to SHS; 2) nonsmokers/exposed to SHS; and 3) smokers. The majority of the study participants were 14 years old (85%), females (54%), who attended eighth grade in a public school setting (56%). Approximately, half reported being of low socioeconomic status (49%) and nonsmokers/exposed to SHS (49%). The lung function parameters of smokers were found to be lower (FEV1 =62.88±10.25; FEV1/FVC =83.50±14.15; and FEF25%-75% =66.35±12.55) than those recorded for the nonsmokers/exposed to SHS (FEV1 =69.41±11.35; FEV1/FVC =88.75±15.75; and FEF25%-75% =78.90±14.65) and significantly reduced when compared to the nonsmokers/nonexposed to SHS (FEV1 =79.14±13.61; FEV1/FVC =94.88±21.88; and FEF25%-75% =87.36±17.02) (P<0.001). Similarly, respiratory complaints were more prevalent among smokers and those exposed to SHS when compared to nonsmokers/nonexposed to SHS. Our findings suggest that initiation of cigarette smoking and, to a lesser extent, exposure to SHS in adolescence leads to

  7. Progress report '84

    International Nuclear Information System (INIS)

    Havelka, St.

    1985-01-01

    The most important achievements are summed up of the Nuclear Research Institute in Rez in 1984. They are as follows: mobile cementation lines for the disposal of liquid radioactive wastes, completion of the basic line for the reprocessing of spent fuel, reconstruction of the semi-hot cell for the production of thalium 210 Tl, the dummy experiment on the LR-0 reactor which made it possible to define the effect of neutron dose on the service life of a reactor pressure vessel; research was also carried out related to the nuclear safety of PWR reactors, to reactor physics, technology and materials, the fuel cycle, neutron activation analysis and neutron radiography. In the field of production and services there are research results in the manufacture of radiopharmaceuticals and semiconductor detectors, in standardization and in irradiation, computation and information services. Also mentioned is the fulfilment of the Institute's social programme. (M.D.)

  8. Los cambios en la estructura intraurbana de Ciudad Juárez, Chihuahua, de monocéntrica a multicéntrica

    Directory of Open Access Journals (Sweden)

    César M. Flores Fuentes

    2001-01-01

    Full Text Available El artículo tiene como objetivo analizar los cambios en la estructura intraurbana de Ciudad Juárez, Chihuahua, durante el periodo 1989-1993. Para ello se usaron los censos económicos de comercio y servicios de 1989 y 1994, el censo de población de 1990 y el conteo de población de1995, ambos a nivel de AGEB. Lo anterior fue posible mediante la construcción del índice de centralidad. En 1989 la estructura intraurbana de Ciudad Juárez mostró la presencia de dos centros principales. Dichos centros, aunque con la misma jerarquía urbana, tienen distintas funciones, como resultado de contar con ramas económicas que tienen diferentes áreas de mercado, desigual densidad poblacional y distinta capacidad de compra de sus principales consumidores. Para 1994 la ciudad siguió teniendo esos dos centros principales, aunque se crearon tres nuevos subcentros que se localizan fuera de las tradicionales áreas centrales, en zonas de fácil acceso y buena infraestructura. En este contexto, la estructura intraurbana se encuentra en proceso de convertirse de monocéntrica en multicéntrica

  9. Política social, protección social y programa empleo temporal: el caso Juárez, México

    Directory of Open Access Journals (Sweden)

    Claudia Marcela Roqueme Ramírez

    2013-01-01

    Full Text Available Este trabajo es un análisis del Programa Empleo Temporal (PET en Ciudad Juárez en el marco del concepto protección social. Para ello se indaga acerca de la política social en México como un intento de comprender hasta qué punto ha contribuido dicho programa a esta alternativa de desarrollo. En este sentido, la revisión bibliográfica se empleó como una herramienta documental y metodológica que permitió conocer otras experiencias en América Latina para situar que la problemática del desempleo y la protección constituyen aún un desafío. Ciudad Juárez no es la excepción. La indagación del PET conduce a proponer que, aunque sus efectos sean positivos temporalmente, los resultados obtenidos son limitados ya que las políticas de acción están encaminadas a solventar en su mayoría contingencias y no una sustentabilidad a mediano y largo plazo. Finalmente, se propone la creación de un índice para monitorear y evaluar el impacto del PET en términos de cobertura, del perfil de los beneficiarios y de los ingresos generados entre los beneficiados.

  10. Convergencia tecnológica y nacimiento de las maquiladoras de tercera generación: el caso Delphi-Juárez

    Directory of Open Access Journals (Sweden)

    Arturo Lara Rivero

    2001-01-01

    Full Text Available El objetivo de este trabajo es el de explicar el nacimiento de un moderno, inédito centro de investigación y desarrollo de auto partes electrónicas: Delphi - Juárez . La pregunta básica que guía este trabajo es la siguiente: ¿cuáles son las implicaciones de la convergencia tecnológica electrónica / automotriz sobre el número, distribución espacial y jerárquica de los proveedores? Esta convergencia tecnológica viene a revalorizar las antiguas funciones eléctricas (y tanto a los viejos proveedores de partes eléctricas maduras como a los proveedores de arneses y a insertarlas en una nueva jerarquía tecnológica con interacciones más intensas entre proveedores de arneses, léase maquiladoras del sector auto partes electrónicos / eléctricos y las empresas propiamente automotrices. Resulta imprescindible leer la formación del centro de investigación y desarrollo Delphi Juárez desde la perspectiva de los procesos de convergencia, resolución de desequilibrios tecnológicos y coevolución tecnológica del campo electrónico y automotriz.

  11. Nuevos hallazgos documentales y biográficos sobre Alonso Xuárez maestro de Sebastián Durón

    Directory of Open Access Journals (Sweden)

    de la Fuente Charfolé, José Luis

    2012-12-01

    Full Text Available Alonso Xuárez was no minor composer in the musical field of his time. The quality and effectiveness of his compositions makes them deserving of a leading place in Spanish and European music of the 17th century. In spite of this almost nothing is known about this composer prior to his being appointed to teach in the chapel of Cuenca cathedral. Virtually all the currently available data is of a secondary and collateral nature and arises from research into his disciple the organist Sebastián Durón, the renowned opera composer and teacher at the Capilla Real of Charles II.

    Alonso Xuárez no fue un compositor menor dentro del panorama musical de su tiempo. La calidad y eficacia de su música merece estar en primera línea de la música española y europea del siglo XVII. Sin embargo, el desconocimiento de este músico es casi completo con anterioridad a su nombramiento en el magisterio de capilla de la catedral de Cuenca. Prácticamente todos los datos expuestos hasta el momento han sido restos secundarios y colaterales desprendidos de otras investigaciones realizadas sobre la figura de su discípulo, el reputado compositor de teatro lírico y maestro de la Capilla Real de Carlos II, el organista Sebastián Durón.

  12. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

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

  13. 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

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

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

  15. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  16. Heterogeneous reactors

    International Nuclear Information System (INIS)

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

    1979-08-01

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

  17. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-08-01

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

  18. Reactor safety

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  19. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  20. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

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

  1. RA Reactor

    International Nuclear Information System (INIS)

    1989-01-01

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

  2. Reactor physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1998-01-01

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

  3. Reactor core

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

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

  4. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

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

  5. Reactor container

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

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

  7. Validation of the VTT's reactor physics code system

    International Nuclear Information System (INIS)

    Tanskanen, A.

    1998-01-01

    At VTT Energy several international reactor physics codes and nuclear data libraries are used in a variety of applications. The codes and libraries are under constant development and every now and then new updated versions are released, which are taken in use as soon as they have been validated at VTT Energy. The primary aim of the validation is to ensure that the code works properly, and that it can be used correctly. Moreover, the applicability of the codes and libraries are studied in order to establish their advantages and weak points. The capability of generating program-specific nuclear data for different reactor physics codes starting from the same evaluated data is sometimes of great benefit. VTT Energy has acquired a nuclear data processing system based on the NJOY-94.105 and TRANSX-2.15 processing codes. The validity of the processing system has been demonstrated by generating pointwise (MCNP) and groupwise (ANISN) temperature-dependent cross section sets for the benchmark calculations of the Doppler coefficient of reactivity. At VTT Energy the KENO-VI three-dimensional Monte Carlo code is used in criticality safety analyses. The KENO-VI code and the 44GROUPNDF5 data library have been validated at VTT Energy against the ZR-6 and LR-0 critical experiments. Burnup Credit refers to the reduction in reactivity of burned nuclear fuel due to the change in composition during irradiation. VTT Energy has participated in the calculational VVER-440 burnup credit benchmark in order to validate criticality safety calculation tools. (orig.)

  8. Reactor physical program in the frame of the MSR-SPHINX transmuter concept development

    International Nuclear Information System (INIS)

    Hron, M.; Mikisek, M.

    2008-01-01

    In the frame of the R and D program for the Molten Salt Reactor (MSR) - SPHINX (Spent Hot fuel Incinerator by Neutron flux) concept, which has been under development in the Czech Republic as an actinide burner in resonance neutron spectrum and a radionuclide transmuter in a well-thermalized neutron spectrum, and namely its reactor physical part, the relatively broad experimental activities have been involved in the program, recently, which will serve for a validation of computer codes and verification of design inputs for designing of a demonstration unit of the MSR-type. The experimental program, which has been focused, in its first stage, on a short-term irradiation of small size samples of molten-salt systems as well as structural materials proposed for the MSR blanket in the field of high neutron flux of research reactors, will be in the proposed next stage of the program focused on a large-scale experimental verification of design inputs by use of MSR-type inserted zones into the existing light water moderated experimental reactor LR-0, which may allow to modify it to experimental zero power salt reactor SR-0. There has been a preparatory stage of the project called EROS started in the year 2006 and new experiments with MSR-type zones irradiated by cyclotron based neutron source are planned at the end of 2007 and should go on in the year 2008. There will be a brief description of the so far prepared and performed experimental programs introduced in the paper. (authors)

  9. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

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

  10. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

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

  11. Carlos María Ramírez sai em defesa de José Artigas: da crítica à (reconstrução do herói oriental = Carlos María Ramírez defends José Artigas: from criticism to the eastern hero reconstruction

    Directory of Open Access Journals (Sweden)

    Fuão, Juarez J. Rodrigues

    2009-01-01

    Full Text Available O artigo analisa a obra Juicio Crítico del Bosquejo Histórico de la República Oriental del Uruguay por el Dr. D. Francisco A. Berra, escrita por Carlos María Ramírez, e o papel do intelectual na construção idealizada de José Artigas. Publicada no ano de 1882, período marcado pelo intenso debate acerca do passado uruguaio, tal obra participou do processo de reabilitação da imagem do líder independentista, caracterizando-o como o grande libertador e o Precursor da Nacionalidade Uruguaia

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

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

  13. Activismo transnacional y calidad de la democracia en México: Reflexiones en torno al caso de Ciudad Juárez

    Directory of Open Access Journals (Sweden)

    Alberto Martín

    2008-04-01

    Full Text Available Abstract: Transnational activism and quality of democracy  in Mexico: reflections centring on the case of Ciudad JuárezThis article analyses the impact of transnational  activism in the call to solve the deaths of hundreds of women in Cuidad Juárez. The efforts of  organizations of relatives of disappeared women  to secure the solidarity of national and international organizations and networks have been crucial  in influencing the federal Mexican government to  investigate these crimes. In addition, by placing  the problem inside wider frames of interpretation  – those of gender violence and human rights–, the  organizations of Juarez have helped to open the  debate concerning the question of violence in  general against women in Mexico. Nevertheless,  the results of the movement at the local level are  still far from satisfactory due to questions related  both to internal problems and weaknesses of local  organizations as well as to structural problems of  democracy in Mexico, which include the weakness of rule of law and the ineffectiveness of the  political system in implementing effective accountability.Resumen:El artículo analiza el impacto de la internacionalización de la movilización en pro del esclarecimiento de los crímenes cometidos contra mujeres  en Ciudad Juárez, México. La capacidad de las  organizaciones de familiares de desaparecidas de  concitar la solidaridad de organizaciones y redes  nacionales e internacionales, ha sido determinante  para desencadenar la intervención del gobierno  federal mexicano en la investigación de los crí- menes. Asimismo, a través de la inserción del  problema en marcos de interpretación más amplios – los de la violencia de género y los derechos humanos -, las organizaciones de Juárez han  contribuido a abrir el debate en torno a la violencia contra la mujer en México. Sin embargo, a  nivel local los resultados del movimiento se encuentran aún lejos

  14. Between fear and differentiation. The current situation of gated communities within border towns such as Tijuana, Nogales and Ciudad Juárez

    Directory of Open Access Journals (Sweden)

    Jesús Ángel Enríquez Acosta

    2007-01-01

    Full Text Available In the cities of Tijuana, Nogales and Ciudad Juárez, located in the northwestern border between Mexico and the United States, one of the more popular urbanization processes is the modality of closed divisions. These residential areas are characterized for being a physical space protected and separated from the city disturbances with bars and fences, and most of them present monitoring houses with access restrictions and private surveillance. The concept of closed divisions tends to expand in the urban landscape of the border cities without restrictions except for those established by the real estate market. Nevertheless, it's important to analyze the impact of closed divisions in the morphology of the cities, the urban sustentability of this developments and the social segregation they cause.

  15. Condiciones de trabajo en la industria maquiladora de tipo electrónico. El caso de Ciudad Juárez

    Directory of Open Access Journals (Sweden)

    Lilia Venegas Aguilera

    1985-01-01

    Full Text Available Este trabajo es un avance de la investigación emprendida en el año de 1981 realizada en torno a las condiciones de vida y de trabajo en la industria maquiladora. Para ello se eligió a Ciudad Juárez, que para 1982 contaba ya con 42,695 trabajadores en este tipo de industria. En primer lugar se presenta la importancia y características de esta industria, particularmente de tipo electrónico, y dentro de este marco referencial se aborda el análisis de las condiciones laborales de las trabajadoras de esta rama industrial que representaban el 67% del total de trabajadores de maquiladoras de esa ciudad fronteriza. La fuente de información proviene de una encuesta aplicada en 28 empresas, el 57% de las existentes y alrededor de 162 obreras.

  16. Modos subordinados de acceso a los clásicos en Los príncipes valientes de Javier Pérez Andújar

    OpenAIRE

    Cáliz Montes, Jessica

    2015-01-01

    Le présent article aborde la question de la diffusion de la culture savante à travers la culture visuelle en se centrant sur Los príncipes valientes (2007) de Javier Pérez Andújar. Concrètement, il analyse la cohabitation entre la tradition populaire, orale, et une nouvelle culture populaire, pendant la période du « tardo-franquisme ». Cette nouvelle culture est diffusée grâce à différents moyens, qui appartiennent à la « sous-culture » (Amorós) – la télévision, les bandes dessinées, le ciném...

  17. Disidir el régimen de horror y muerte: colectivos juveniles femeninos en Ciudad Juárez (México

    Directory of Open Access Journals (Sweden)

    Salvador Salazar Gutiérrez

    2017-01-01

    Full Text Available El texto muestra algunos hallazgos en torno al análisis de acciones colectivas en Ciudad Juárez (México, las cuales plantean una serie de estrategias para develar y disentir del régimen de horror y muerte caracterizado por la violencia durante las dos últimas décadas. Por medio de un trabajo etnográico con los colectivos Batallones Femeninos y Nuestras Hijas de Regreso a Casa, presenta cómo prácticas organizativas asociadas con la música o a la intervención urbana de murales son estrategias para promover una ética por la vida en relación con mujeres jóvenes.

  18. Puebla Territory-Specific Basket of Goods Strategies and Their Local Repercussions for Employment and Profit: the Case of Xicotepec de Juárez, Puebla

    Directory of Open Access Journals (Sweden)

    Mario del Roble Pensado Leglise

    2015-07-01

    Full Text Available Developing a basket of land goods means a systemic strateg y for small farmers because it allows reaching multiple objectives in order to promote territorial competitiveness to access market niches with varied rural goods, strengthen social capital and generate better local levels in employment and income, together with increasing and preserving the environment. This analysis implied the application of a system dynamics model which produced possible future scenarios (through Ve n s i m®DSS 5.8 about employment and income obtained by smallholder coffee farmers from Xicotepec de Juárez municipality in Puebla, regarding the setting of the above mentioned strateg y for rural development. Results showed that this strateg y was implemented successfully and also revealed opportunities for: a improving the development capacity of small farmers; b making the institutional context favorable; c The reinforcement of social capital essential to implement this land strategy.

  19. Infortunios de Alonso Ramírez, de Carlos de Sigüenza y Góngora: aproximaciones a una geografía poscolonial

    Directory of Open Access Journals (Sweden)

    Mariana Zinni

    2014-06-01

    Infortunios de Alonso Ramírez can be read as a mimetic exercise related to some core problems regarding the dynamics of colonial domination. Such exercise not only mimes-imitates textual aspects of other genres by reshaping the process of text constitution itself (picaresque novel, travelogue, but also inscribes itself in the relationships between colonized and colonizers. I propose a reading of this text by arguing that Sigüenza y Góngora, while re-presenting the colony vis-à-vis the metropolis, situates Mexico City in a cultural circuit and proposes a movement of “metropolization” of the colonial city regarding the other periphery, the Philippines. Consequently, Sigüenza will descenter the empire by establishing the existence of this other suburb in a clever stroke of which I will propose to call “postcolonial geography”.

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

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

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

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

  2. Reactor container

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  3. REACTOR SHIELD

    Science.gov (United States)

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

    1959-02-17

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

  4. 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.

  5. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

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

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

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

  7. 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.)

  8. Data acquisition for the LVR-15 research reactor. Final report

    International Nuclear Information System (INIS)

    Dusek, J.; Holy, J.; Rysavy, J.

    1993-11-01

    The activities are reviewed carried out under contract No. 5686 between the IAEA and the Nuclear Research Institute at Rez. A list of components, their description and block diagrams of the LVR-15 reactor are presented. Totally, 40 failures during testing and 48 failures during operation were recorded for the period 1991 to 1993. The failure causes and development are briefly described. Information on the failures was classified and included into the system. The contribution to data classification and processing is presented. A number of additional variants are pointed out, of the exact use of non-parametric and parametric statistical methods when developing the comprehensive probabilistic model. A list is given of initiating events as starting points of accident sequences collected from the operating experience. The report consists of three supplements: (i) Data collection on the LVR-15 research reactor; (ii) Some statistical methods for the data processing; (iii) Initiating events data of research reactor for the use of probabilistic safety assessment. (J.B.) 54 tabs., 17 figs., 14 refs

  9. Reactor containment

    International Nuclear Information System (INIS)

    Kawabe, Ryuhei; Yamaki, Rika.

    1990-01-01

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

  10. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

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

  11. Time changes of vertical profile of neutron fluence rate in LVR-15 reactor

    International Nuclear Information System (INIS)

    Viererbl, L.; Stehno, J.; Erben, O.; Lahodova, Z.; Marek, M.

    2003-01-01

    The LVR-15 reactor is a light water research type reactor, which is situated, in Nuclear Research Institute, Rez near Prague. The reactor is used as a multipurpose facility. For some experiments and material productions, e.g. for homogeneity of silicon resistance in production of radiation doped silicon, the time changes of vertical profile of neutron fluence rate are particularly important. The assembly used for silicon irradiation has two self-powered neutron detectors installed in a vertical irradiation channel in LVR-15 reactor. Vertical profile of thermal neutron fluence rate was automatically scanned during reactor operation. The results of measurements made in 2002 and 2003 with these detectors are presented. A set of vertical profile measurements was made during two 21-days reactor cycles. During the cycle the vertical profile slightly changes both in the position of its maximum and in the shape. The time dependences of the position of profile maximum and the profile width at half maximum during the cycle are given. (author)

  12. Extensive utilization of training reactor VR-1

    International Nuclear Information System (INIS)

    Matejka, Karel; Sklenka, Lubomir

    2003-01-01

    institutions; Studying of transmutation technologies ADTT. Public relation activities: Keeping current state in the field number of user schools and number visitors; Developing new demonstration experiments for Secondary/High School students. International co-operation: Continuing close co-operation with Universities in Germany, Austria, Hungary, Slovakia etc.; Participation in Reduce enrichment of research and test reactors RERTR Program with cooperation with Nuclear Research Institute in Rez; Participation in European Nuclear Education Network ENEN and NEPTUNO; Additional courses for potential users. The experiences with the VR-1 operation are excellent for the last 12 years. There was no accident regarding nuclear safety or radiation protection during the whole period of the use. Operation of the reactor is widely included in many study branches and it significantly contributes to the education of our students and also to wide public in terms of conditions and acceptability of the use of nuclear energy. (author)

  13. Development of gas cooled reactors and experimental setup of high temperature helium loop for in-pile operation

    Energy Technology Data Exchange (ETDEWEB)

    Miletić, Marija, E-mail: marija_miletic@live.com [Czech Technical University in Prague, Prague (Czech Republic); Fukač, Rostislav, E-mail: fuk@cvrez.cz [Research Centre Rez Ltd., Rez (Czech Republic); Pioro, Igor, E-mail: Igor.Pioro@uoit.ca [University of Ontario Institute of Technology, Oshawa (Canada); Dragunov, Alexey, E-mail: Alexey.Dragunov@uoit.ca [University of Ontario Institute of Technology, Oshawa (Canada)

    2014-09-15

    Highlights: • Gas as a coolant in Gen-IV reactors, history and development. • Main physical parameters comparison of gas coolants: carbon dioxide, helium, hydrogen with water. • Forced convection in turbulent pipe flow. • Gas cooled fast reactor concept comparisons to very high temperature reactor concept. • High temperature helium loop: concept, development, mechanism, design and constraints. - Abstract: Rapidly increasing energy and electricity demands, global concerns over the climate changes and strong dependence on foreign fossil fuel supplies are powerfully influencing greater use of nuclear power. In order to establish the viability of next-generation reactor concepts to meet tomorrow's needs for clean and reliable energy production the fundamental research and development issues need to be addressed for the Generation-IV nuclear-energy systems. Generation-IV reactor concepts are being developed to use more advanced materials, coolants and higher burn-ups fuels, while keeping a nuclear reactor safe and reliable. One of the six Generation-IV concepts is a very high temperature reactor (VHTR). The VHTR concept uses a graphite-moderated core with a once-through uranium fuel cycle, using high temperature helium as the coolant. Because helium is naturally inert and single-phase, the helium-cooled reactor can operate at much higher temperatures, leading to higher efficiency. Current VHTR concepts will use fuels such as uranium dioxide, uranium carbide, or uranium oxycarbide. Since some of these fuels are new in nuclear industry and due to their unknown properties and behavior within VHTR conditions it is very important to address these issues by investigate their characteristics within conditions close to those in VHTRs. This research can be performed in a research reactor with in-pile helium loop designed and constructed in Research Center Rez Ltd. One of the topics analyzed in this article are also physical characteristic and benefits of gas

  14. The Good News of the prophet-woman: identity and political culture in the writings of Fourierists Mª Josefa Zapata and Margarita Pérez de Celis | La Buena Nueva de la mujer profeta: identidad y cultura política en las fourieristas Mª Josefa Zapata y Margarita Pérez de Celis

    Directory of Open Access Journals (Sweden)

    Gloria Espigado Tocino

    2008-12-01

    Full Text Available This article describes how the Fourierists Josefa Zapata and Margarita Pérez de Celis constructed a liberating identity for women through their writings in their own newspapers. Followers of the theories of the French utopian socialist Charles Fourier, they used a prophetic form of discourse to announce the advent of a new era for mankind, in which women would be redeemed. Advocates of a humanitarian Christianity which sought to correct fundamental social inequalities, they were, however, subject to censorship which was always on the alert for the threat of subversion that their discourse entailed. | Este artículo describe cómo las fourieristas Josefa Zapata y Margarita Pérez de Celis construyeron una identidad emancipadora para la mujer, a través de sus escritos en sus propios periódicos. Seguidoras de las teorías del socialista utópico francés Charles Fourier, adoptaron la expresión profética para anunciar el advenimiento de una nueva era para la humanidad, donde la mujer sería igualmente redimida. Seguidoras de un cristianismo humanitarista que resolviera los desequilibrios sociales fundamentales fueron, sin embargo, objeto de la censura que estuvo atenta a la amenaza de subversión que su discurso encerraba.

  15. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  16. 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

  17. Loop capabilities in Rez for water chemistry and corrosion control of cladding and in-core components

    International Nuclear Information System (INIS)

    Kysela, J.; Zmitko, M.; Srank, J.; Vsolak, R.

    1999-01-01

    Main characteristics of LVR-15 research reactor and its irradiation facilities are presented. For testing of cladding, internals and RPV materials specialised loop are used. There are now five high pressure loops modelling PWR, WWER or BWR water environment and chemistry. Loops can be connected with instrumented in-pile channels enable slow strain rate testing, 1CT or 2CT specimens loading and electrically heated rods exposition. Reactor dosimetry including neutronic parameters measurements and calculations and mock-up experiments are used. Water chemistry control involves gas (O 2 , H 2 ) dosing system, Orbisphere H 2 /O 2 measurement, electrochemical potential (ECP) measurements and specialised analytical chemistry laboratory. For cladding corrosion studies in-pile channels with four electrically heated rods with heat flux up to 100 W/cm 2 , void fraction 5 % at the outlet, inlet temperature 320 deg. C and flow velocity 3 m/s were development and tested. For corrosion layer investigation there is eddy current measurements and PIE techniques which use crud thickness measurement, chemical analyses of the crud, optical metallography, hydrogen analysis, SEM and TEM. (author)

  18. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-05-10

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

  19. Nuclear reactors

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  20. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

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

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

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

  2. NEUTRONIC REACTOR

    Science.gov (United States)

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

    1958-04-15

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

  3. Relación entre consultas a urgencias por enfermedad respiratoria y contaminación atmosférica en Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    Hernández-Cadena Leticia

    2000-01-01

    Full Text Available OBJETIVO: Analizar la relación entre las concentraciones ambientales de partículas de diámetro <=10 µm (PM10 y de ozono con el número diario de consultas al servicio de urgencias por enfermedades respiratorias agudas y asma en niños menores de 15 años, residentes de Ciudad Juárez, Chihuahua, México. MATERIAL Y MÉTODOS: Este estudio se realizó durante los años de 1998 y 1999, utilizando un diseño de tipo ecológico. Los datos atmosféricos se obtuvieron de la base de datos de la Agencia de Protección al Ambiente (EPA, provenientes de ocho estaciones de monitoreo ubicadas en Ciudad Juárez y en El Paso, Texas. Los datos de consultas al servicio de urgencias por causas respiratorias se obtuvieron de los registros médicos de dos hospitales del Instituto Mexicano del Seguro Social (IMSS, en Ciudad Juárez, Chihuahua, de julio de 1997 a diciembre de 1998. Los diagnósticos se clasificaron en dos grupos: a asma, y b infecciones respiratorias altas, conforme a la Clasificación Internacional de Enfermedades (CIE-9 o CIE-10. El análisis se realizó con la utilización de la metodología de series de tiempo que emplea regresión Poisson. RESULTADOS: Durante el periodo de estudio la media de 24 horas de PM10 fue de 34.46 µg/m³ (DE=17.99 y la media de los niveles de ozono fue de 51.60 partes por billón (ppb (DE=20.70. El modelo propuesto estima que un incremento de 20 µg/m³ en el promedio de 24 horas, en la exposición a PM10, se relaciona con un incremento de 4.97% (IC 95% 0.97-9.13 en las consultas por asma con un retraso de cinco días y con un incremento de 9% (IC 95% 1.8-16.8 cuando se considera a la exposición acumulada de cinco días anteriores. Respecto a enfermedades respiratorias altas se encontró un aumento de 2.95% en las consultas a urgencias por cada 20 µm/m³ de incremento en el promedio de 24 horas en la exposición a PM10. Se observó que el impacto de PM10 sobre las visitas de urgencia por asma fue más severo en

  4. “In the city of god” The advocacy of Mary by Miguel Suárez and the wall paintings at the Founder’s Manor in Tunja. New documents and interpretations.

    Directory of Open Access Journals (Sweden)

    Abel Fernando Martínez Martín

    2015-07-01

    Full Text Available This text exposes some documental sources gathered from the Regional Archive of Boyacá (RAB, which identify the relevance of Miguel Suárez de Figueroa, eldest son and heir to Gonzalo Suárez Rendón, founder of the city of Tunja, in charge of inishing and decorating of the roofs of the Founder’s Manor,as well as main sponsor and founder of Rosario Chapel, located in Santo Domingo church. Furthermore, an iconographic interpretation of the roof of the main hall in the Founder’s Manor is proposed, different from the one exposed by the historians Santiago Sebastián and José Miguel Morales Folguera.

  5. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

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

  6. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

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

  7. Reactor facility

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  8. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

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

  9. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

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

  10. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

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

  11. Reactor system

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Narabayashi, Naoshi.

    1990-01-01

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

  12. Reactor core

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  13. ¿Vindicando al charnego? El discurso autobiográfico de Javier Pérez Andújar y Jorge Javier Vázquez

    Directory of Open Access Journals (Sweden)

    Aramburu, Mikel

    2016-06-01

    Full Text Available In this article I analyse two autobiographical narrations that have recently been published by the sons of southern Spanish migrants to Catalonia. In Paseos con mi madre by Javier Pérez Andújar (2011, and La vida iba en serio by Jorge Javier Vázquez (2013, the authors deal with their social condition as youngsters in the urban periphery, producing a discourse, written in the first person, that is unprecedented in the Catalan context. The relevance of these books derives from a number of factors. First, they offer a new voice that rises out of a self-representation vacuum in this social sector. Secondly, they conflictively rethink a social place which hegemonic discourse had assumed «normalized» and overcome. Thirdly, although both reflect on their migratory origin and the difficulty of fitting into Catalonia’s urban mesocracy, their migratory background is largely subsumed in the experience of urban segregation, and hardly expressed at all in either ethnic or national terms.En este artículo analizo dos relatos autobiográficos publicados recientemente por hijos de inmigrantes procedentes del sur de España y radicados en Cataluña. Javier Pérez Andújar (2011 en Paseos con mi madre y Jorge Javier Vázquez (2013 en La vida iba en serio tematizan su condición social como jóvenes de las periferias urbanas presentando un discurso que, contado en primera persona, es inédito en el panorama catalán. Su relevancia deriva de una serie de factores. Primero porque conforman una nueva voz que emerge en un vacío de autorrepresentaciones de este sector social. Segundo porque problematizan conflictivamente un lugar social que en el discurso hegemónico se había dado por «normalizado» y superado. Finalmente, aunque ambos reflexionan sobre sus orígenes migratorios y su difícil encaje en la mesocracia catalana, la condición migratoria originaria apenas se expresa en términos étnicos o nacionales; está en gran parte subsumida en la

  14. Efecto tóxico del DDT, clordano y agua de la presa Ignacio Ramírez (México, sobre Daphnia magna (Crustacea: Daphnidae

    Directory of Open Access Journals (Sweden)

    Laura Martínez-Tabche

    1999-12-01

    Full Text Available Actualmente en México son empleados los plaguicidas diclorodifeniltricloroetano (DDT y clordano (CLO para combatir la malaria y termitas. De 1990 a 1996 un total de 27 ton de DDT y 508 de CLO, en forma de productos técnicos, fueron importados. El objetivo de este estudio fue establecer una metodología para determinar el impacto ambiental que pueden producir estos compuestos sobre un embalse. El efecto tóxico del DDT y CLO fue evaluado sobre la actividad de la o-demetilasa (OD y del acetilcolinesterasa (AchA del cladócero Daphnia magna al exponerla a diferentes concentraciones de los insecticidas disueltos en el agua de tres sitios de la presa Ignacio Ramírez (PIR. El efecto del agua contaminada con los insecticidas sobre la actividad de la AChA y OD, así como la CL50, fueron utilizadas como indicadores de exposición para determinar los lugares más contaminadas de la PIR. Las características fisicoquímicas del agua así como la biodiversidad de los sitios en estudio de la presa fueron considerados. Los resultados obtenidos demuestran que la estación cercana a la compuerta exhibe un potencial de toxicidad, ya que las actividades enzimáticas fueron modificadas. Se sugiere utilizar las actividades de AchA y OD del cladócero para evaluar la toxicidad de un cuerpo de agua contaminado por insecticidas organoclorados.Chlorodiphenylnitrichloroethane (DDT and chlordane (CLO are currently used in Mexico to control malaria and termites. From 1990 to 1996 a total of 27 ton of DDT and 508 of CLO were imported. We establish a methodology to determine their environmental impact in a Mexican dam (Ignacio Ramírez. The toxic effect of DDT and CLO were evaluated on the o-demethylase (OD and acethycholinesterase activities (AchA of the cladoceran Daphnia magna exposed to different concentrations of the insecticides solved in water from three sites. Their effect on the AchA and OD activities, and so the CL50 were used as exposure bioindicators to

  15. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

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

  16. Referencias bibliográficas: Julio Cortázar, perspectivas críticas. Ensayos inéditos / Pol Popovic Karic y Fidel Chávez Pérez, coordinadores.

    OpenAIRE

    Guerrero Almagro, Berta

    2014-01-01

    Reseña de Julio Cortázar, perspectivas críticas. Ensayos inéditos. Pol Popovic Karic y Fidel Chávez Pérez, coordinadores. Instituto Tecnológico y de Estudios Superiores de Monterrey, Campus de Monterrey y Miguel Ángel Porrúa, librero-editor México, 2012. 384 pp. (ISBN: 978-607-401-581-2)

  17. Redescription of Chabaudacuaria multispinosa (Pérez Vigueras, 1938) n. g., n. comb. (Nematoda: Spirurida: Acuariidae) based on specimens from Ardea herodias L. and Nyctanassa violacea (L.) (Ardeidae) in Florida.

    Science.gov (United States)

    Mutafchiev, Yasen; Kinsella, John M

    2012-10-01

    Chabaudacuaria n. g. is erected, as monotypic, for C. multispinosa (Pérez Vigueras, 1938) n. comb. (Spirurida: Acuariidae) [syns Cheilospirura multispinosa Pérez Vigueras, 1938; Acuaria multispinosa (Pérez Vigueras, 1938) Yamaguti, 1961]. This species, a parasite of various ardeid birds, is redescribed by means of light and scanning electron microscopy based on material from great blue herons Ardea herodias L. and yellow-crowned night herons Nyctanassa violacea (L.) in Florida, USA. Chabaudacuaria n. g. resembles Acuaria Bremser, 1811, Cheilospirura Diesing, 1861, Skrjabinocerca Schikhobalova, 1930 and Xenocordon Mawson, 1982 in its straight cordons which do not anastomose. However, it can be distinguished from them by the didelphic-prodelphic uterus and the absence of caudal alae in the males. In the pattern of its cordons (consisting of a row of plates and a longitudinal ridge) and the absence of an area rugosa, the new genus is similar to Chevreuxia Seurat, 1918, Syncuaria Gil'bert, 1927, Aviculariella Wehr, 1931, Skrjabinocara Kurashvili, 1940, Decorataria Sobolev, 1949 and Desportesius Chabaud & Campana, 1949, which are characterised by anastomosing cordons. The didelphic-prodelphic female reproductive system of Chabaudacuaria is intermediate between the didelphic-amphidelphic uterus of Chevreuxia and the monodelphic-prodelphic uterus of Syncuaria, Aviculariella, Skrjabinocara, Desportesius and Decorataria. Therefore, the straight and non-anastomosing cordons are considered to be autapomorphic for Chabaudacuaria.

  18. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  19. Estudo populacional do camarão-rosa Penaeus Paulensis pérez farfante (natantia, penaeidae na Lagoa da Conceiçáo, Santa Catarina, Brasil Populational study of the pink-shrimp Penaeus Paulensis pérez farfante (natantia, penaeidae in the Conceição Lake, Florianópolis, Santa Catarina, Brazil

    Directory of Open Access Journals (Sweden)

    Joaquim Olinto Branco

    1998-01-01

    Full Text Available In the time period between May/92 to April/93, 2693 (1243 males and 1450 females specimens of Penaeus paulensis Pérez Farfante, 1967 were collected. The shrimps were captured by night using a hand net in äreas between 30 to 150 cm deep. The abundance of P. paulensis is regulated mainly by the temperature, the summer being the season of greater profusion. The major recruiting period takes place in the Spring with shrimps measuring between 1,0 to 3,0 cm and approximately 2,0 months old. The population reaches the pre-adult in the Fall-Winter period with average length between 8,8 cm (females and 9,3 cm (males. The migration to the ocean occurs during the Winter. The artisanal fishing in the Conceição Lake is predatory, acting upon the young and pre-adult shrimps, which may jeopardize the marine reproducer stock.

  20. Seguridad urbana y vulnerabilidad social en Ciudad Juárez. Un modelo desde la perspectiva de análisis espacial

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    Sara Morales Cárdenas

    2013-01-01

    Full Text Available Partiendo del concepto de “seguridad urbana”, introducido por un-Habitat en 2007 dentro de la agenda de Ciudades seguras, el presente trabajo propone analizar a Ciudad Juárez, urbe considerada entre las más inseguras y violentas del país y del mundo. Se presenta el desarrollo de un índice de seguridad urbana (isu basado en un modelo multicriterio de análisis espacial que propone identificar y explicar cómo se manifiestan territorialmente las amenazas a la seguridad urbana y su relación con los índices de vulnerabilidad social asociada a la pobreza. La importancia de este análisis radica en la necesidad de articular los estudios estadísticos y los patrones de distribución de las amenazas a la seguridad urbana con los procesos de planificación urbana como instrumento preventivo que permita formular políticas para reducir la inseguridad urbana.

  1. Elaboración del duelo de una madre cuyo hijo trabajaba como sicario en Ciudad Juárez, Chihuahua

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    Rosalía Delgado Durán

    2014-01-01

    Full Text Available El presente trabajo es parte de una investigación cualitativa sobre el proceso de ela - boración de duelo de la madre de un sicario en el contexto de una terapia Gestalt. Se utilizó para su análisis la perspectiva de las etapas del duelo de Kübler-Ross (2006:59- 119. La exacerbación de la violencia generada en buena medida por pugnas entre gru - pos del crimen organizado en Ciudad Juárez, Chihuahua (Martínez, 2008, ha dado como resultado una gran cantidad de muertes, una de ellas es el caso que nos ocupa. Si bien uno de los objetivos iniciales de la investigación era documentar y analizar las etapas en el desarrollo del duelo de una madre a partir del fallecimiento de su hijo, este se replanteó durante el transcurso de la misma, ya que una de las características del duelo de esta madre es que inició justo cuando se enteró del trabajo que él realizaba.

  2. The mourning novel in relation to the historical novel: an analysis of Santo diablo, by Ernesto Pérez Zúñiga

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    Anthony Sterling Nuckols

    2016-07-01

    Full Text Available We analyze what we call the novel of mourning in opposition to the novel of historical memory. While both assume a critical position with respect to the violence of the 20th century in Spain, they differ in how they deal with the losses of the past. The novel of historical memory, influenced by the internationalization of memory discourses and movements, seeks to combat the imposed forgetting through a literary recovery of forgotten cases from the past. The novel of mourning, however, seeks to break this dichotomy between forgetting/memory, understanding that the losses of the past are unrecoverable and that a more just future is only achievable by recognizing the past’s tragic nature: more than a (reopening or closing of wounds, it means living with them, also permitting a way of relating to other tragedies that would otherwise be foreign to us. As an example we analyze Ernesto Pérez Zúñiga’s Santo Diablo (2004.

  3. Distribution pattern of juveniles of the pink shrimps Farfantepenaeus brasiliensis (Latreille, 1817 and F. paulensis (Pérez-Farfante, 1967 on the southeastern Brazilian coast

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    Rogério Caetano da Costa

    Full Text Available Abstract The spatio-temporal distribution of juveniles of the pink shrimps Farfantepenaeus brasiliensis (Latreille, 1817 and Farfantepenaeus paulensis (Pérez-Farfante, 1967 in the Ubatuba region (SP was investigated. Sampling was performed in the bays of Ubatumirim (UBM, Ubatuba (UBA and Mar Virado (MV. A total of 2,018 F. brasiliensis and F. paulensis were collected. The largest catch of juveniles of both species occurred in UBA (N = 867, followed by UBM (N = 729 and MV (N= 422. The bottom sediment in MV had the highest silt and clay content, which explains the negative correlation of the substrate with the abundance of both species. Temperature was positively correlated with the abundance of both species. Juveniles were highly abundant in shallower areas in the summer of 1998. The high rainfall in this El Niño period may have lowered the salinity in estuarine waters and led the shrimps to move to coastal areas in search of higher salinities such as in bays. With this unusually early reduction in salinity, individuals migrated to the bay before the closed season began and thus became more exposed to fishing. We confirmed that monitoring environmental variations, especially in El Niño years, is essential for understanding the distribution patterns of juveniles of both species.

  4. La consigna de los solitarios. Escritura y sobrevivencia en Un año sin amor. Diario del SIDA de Pablo Pérez

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    Alberto Giordano

    2014-06-01

    Full Text Available A partir del reconocimiento de dos momentos en el desarrollo histórico del género ‘narraciones autobiográficas sobre el SIDA’, identificado cada uno con una forma distinta de representarse la enfermedad y la condición del enfermo, este trabajo propone una lectura comparada de las novelas de Hervé Guibert, À l’ami qui ne m’a pas sauvé la vie (1990 y Le protocole compassionnel (1991 y de Un año sin amor. Diario del SIDA (1997 de Pablo Pérez, centrada en dos tópicos: a la construcción de un tipo específico de subjetividad, la del “sobreviviente”, y b los alcances literarios de las distintas elecciones formales (la novela autobiográfica o el diario íntimo para la exposición del diálogo activo entre vida y muerte que caracteriza a ese tipo de subjetividad.

  5. Gestión pública para solucionar un problema ambiental: manejo de llantas de desecho en Ciudad Juárez

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    Gustavo Córdova Bojórquez

    2012-01-01

    Full Text Available La reutilización de llantas usadas es un problema ambiental cuando ya no es posible seguirlas usando y se consideran basura, que se almacena en casas, se deposita en tiraderos clandestinos y se tira en la vía pública. Se convierten en refugio de plagas, roedores e insectos vectores de enfermedades, además constituyen un riesgo para el entorno y la salud humana, peligro que se incrementa ante la posibilidad de un incendio. El objetivo del presente trabajo es analizar la gestión del manejo de la llanta de desecho en Ciudad Juárez, Chihuahua, hogar del mayor tiradero de llantas en la región fronteriza. Los resultados muestran que el gobierno ha tenido una participación mínima, hasta el momento en que se inicia un proceso de gestión mixta que involucra además al sector privado, al académico y a la sociedad civil; a partir de esta gestión mixta comienzan realmente acciones específicas para resolver el problema de la llanta usada.

  6. Las estructuras de Emilio Pérez Piñero en la musealización de dos espacios singulares

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    M. Carmen Pérez Almagro

    2013-03-01

    Full Text Available A principios de la década de los 70 del pasado siglo XX, el arquitecto español Emilio Pérez Piñero realiza dos estructuras para cubrir dos espacios museográficos que perduran hasta el presente como hitos de la musealización del patrimonio histórico-artístico español. Se trata de la Cúpula reticular poliédrica F-12 para el Teatro-Museo Dalí de Figueres (Girona y de la Cubierta para la Necrópolis Paleocristiana de Tarragona. Ambas obras se realizan como consecuencia de dos encargos oficiales del Ministerio de la Vivienda y del Ministerio de Educación y Ciencia, respectivamente. Por la prematura muerte del arquitecto, su hermano José María es quien finaliza el montaje de las estructuras, que pasan a ser iconos actuales de la arquitectura estructural utilizada para la musealización y la conservación del patrimonio.

  7. La jerarquía episcopal y el proyecto democratizador de Adolfo Suárez (julio de 1976-junio de 1977

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    Romina De Carli

    2009-12-01

    Full Text Available Utilizando el material documental del fondo Santa Sede del Archivo del MAE de España y el reconpilado en los Boletines de las Diócesis y Archisiócesis de España, en las revistas “Iglesia Viva” y Razón y Fe” y del folleto “Iglesia en Madrid” entre otros, se procura explicar la postura que la jerarquía episcopal española adoptó frente al programa democratizador de Adolfo Suárez durante julio de 1976 y junio de 1977. De manera especial, se consideran la elaboración y aprobación de la Ley para la Reforma Política y el proceso de legalización de los partidos políticos de la oposición franquista._____________________ABSTRACT:Using the Holy See fund’s documents of Spain MAE Archives and the material collected by the study of Spain Dioceses and Archdioces Bulletins, “Iglesia Viva” and “Razón y Fe” magazines, and the weekly magazine “Iglesia en Madrid”, they wants explain the episcopal hierarchy attitude with respect to Adolfo Suárez’s democratic programme. Specially, they analyses the formulation and approval of Politics Reform Law, and the process of party legalization.

  8. El Agroturismo desde el paradigma del Trabajo en Red y la Coopetencia. Estudio de caso en Pymes del partido de Cnel. Suárez, Buenos Aires

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    Marina Cordisco

    2012-11-01

    Full Text Available El presente artículo identifica el tipo de trabajo en red que realizan los establecimientos del Grupo Cambio Rural (INTA “Cortaderas II” dedicados al agroturismo en el partido de Cnel. Suárez, provincia de Buenos Aires. Persigue analizar si dicha interacción puede encuadrarse bajo el concepto de coopetición, evaluando la presencia de actitudes de cooperación o de conflicto. Se trata de un estudio de caso, para el cual se relevó información a través de entrevistas, encuestas y observación directa. Se advirtió que el grupo constituye una red empresarial horizontal de carácter local, integrada por agentes de un mismo nivel dentro de la cadena de valor, que procuran principalmente dar soluciones a cuestiones de acceso al mercado. Predominan actitudes de cooperación y solidaridad. Sin embargo, conforme evolucione la red en el tiempo, es dable esperar que surjan fisuras que conduzcan hacia un comportamiento competitivo entre los integrantes, producto de sus simetrías como competidores y a partir del conocimiento adquirido en conjunto.

  9. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  10. Nuclear reactor

    International Nuclear Information System (INIS)

    Sasaki, Tomozo.

    1987-01-01

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

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Sakurai, Mikio; Yamauchi, Koki.

    1983-01-01

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

  12. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  13. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

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

  14. Reactor container

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  15. LAS MUERTAS DE JUÁREZ: BIOÉTICA, GÉNERO, PODER E INJUSTICIA AS MORTAS DE JUÁREZ: BIOÉTICA, GÊNERO, PODER E INJUSTIÇA DEAD WOMEN OF JUAREZ: BIOETHICS, GENDER, POWER, AND INJUSTICE

    Directory of Open Access Journals (Sweden)

    Jorge Alberto Álvarez Díaz

    2003-01-01

    Full Text Available Más de 300 mujeres muertas... la historia está llena de injusticias. En ocasiones, las víctimas, sus descendientes u organizaciones han reclamado por la injusticia realizada. Este trabajo intenta ser un reclamo por la injusticia vivida por más de 300 mujeres, muchas de ellas víctimas de violación y homicidio, en Ciudad Juárez, Chihuahua, México. En la década pasada (1993-2003 más de 300 mujeres han desaparecido; muchas se han encontrado posteriormente violadas, mutiladas y asesinadas. Recordando el principialismo, el énfasis se hace en una reflexión posmodernista de la bioética, el género, el poder y la injusticia. Se hace un análisis de la violencia como un problema de salud pública, con un énfasis especial en la salud sexual y la violencia en contra del género femenino. Se comenta la relación entre violación y homicidio contra mujeres. Finalmente, un comentario sobre el escalofriante caso de "las muertas de Juárez". Analizando los datos epidemiológicos sobre violación y homicidio en México, es particularmente importante recalcar que los casos de Juárez no son "típicos", son realmente diferentesMais de 300 mulheres mortas... a história está cheia de injustiças. Por vezes, as vítimas, seus descendentes ou organizações protestaram pela injustiça ocorrida. Este trabalho procura ser um clamor pela injustiça vivida por mais de 300 mulheres, muitas delas vítimas de estupro e homicídio, na Cidade Juárez, Chihuahua, México. Na década passada (1993-2003, mais de 300 mulheres desapareceram; muitas foram encontradas posteriormente como vítimas de estupro, mutiladas e assassinadas. Lembrando o principialismo, a ênfase é feita numa reflexão pós-moderna da bioética, o gênero, o poder e a injustiça. Analisa-se a violência como um problema de saúde pública, com uma ênfase especial na saúde sexual e na violência contra o gênero feminino. Comenta-se a relação entre estupro e homicídio contra as mulheres

  16. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

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

  17. Nuclear reactors

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Jungmann, A.

    1975-01-01

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

  19. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

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

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Yoshioka, Michiko.

    1985-01-01

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

  1. MLR reactor

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

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

  3. Reactor container

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  4. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  5. Molten salt reactors: reactor cores

    International Nuclear Information System (INIS)

    1983-01-01

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

  6. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

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

  7. 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

  8. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

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

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    Jolly, R.

    1979-01-01

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

  10. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  11. Nondestructive testing of nuclear reactor components integrity

    International Nuclear Information System (INIS)

    Mala, M.; Miklos, M.

    2011-01-01

    Nuclear energy must respond to current challenges in the energy market. The significant parameters are increase of the nuclear fuel price, closed fuel cycle, reduction and safe and the final disposal of high level radioactive waste. Nowadays, the discussions on suitable energy mix are taking place not only here in Czech Republic, but also in many other European countries. It is necessary to establish an appropriate ratio among the production of electricity from conventional, nuclear and renewable energy sources. Also, it is necessary to find ways how to streamline the economy, central part of the nuclear fuel cycle and thereby to increase the competitiveness of nuclear energy. This streamlining can be carried out by improving utilization of existing nuclear fuel with maintaining a high degree of nuclear facilities safety. Increasing operational reliability and safety together with increasing utilization of nuclear fuel place increasing demands on monitoring of changes during fuel burnup. The potential fuel assembly damages in light water reactors are prevented by the introduction of new procedures and programs of the fuel assembly monitoring. One of them is the Post Irradiation Inspection Program (PIIP) which is a good tool for monitoring of chemical regime impact on the fuel assembly cladding behavior. Main nondestructive techniques that are used at nuclear power plants for the fuel assembly integrity evaluation are ultrasonic measurements, eddy current measurements, radiographic testing, acoustic techniques and others. Ultrasonic system is usual tool for leak fuel rod evaluation and it is also used at Temelin NPP. Since 2009, Temelin NPP has cooperated with Research Center Rez Ltd in frame of PIIP program at both units WWER 1000. This program was established for US VVantage6 fuel assemblies and also it continues for Russian TVSA-T fuel assemblies. (author)

  12. Nuclear reactors

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  13. Reactor container

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  14. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

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

  15. Nuclear reactors

    International Nuclear Information System (INIS)

    Matheson, J.E.

    1983-01-01

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

  16. Prevalencia de asma y otras enfermedades alérgicas en niños escolares de Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    Barraza-Villarreal Albino

    2001-01-01

    Full Text Available Objetivo. Determinar la prevalencia y severidad del asma, de la rinitis y del eczema en escolares. Material y métodos. Estudio transversal efectuado entre abril de 1998 y mayo de 1999 en Ciudad Juárez, Chihuahua, México, a una muestra aleatoria de 6 174 niños de 53 escuelas. Se aplicó la metodología propuesta por el International Study of Asthma and Allergies in Childhood (ISAAC (etapas 1 y 2 para determinar la prevalencia y severidad del asma, rinitis y eczema. La información de prevalencia, tanto actual como acumulada para dichos padecimientos, se obtuvo mediante un cuestionario ya estandarizado y contestado por los padres de los niños. El diseño de la muestra se hizo por un muestreo mixto, en el cual se estratificó por nivel de contaminación ambiental. Se estimaron prevalencias actual y acumulada estratificando por grupo de edad, sexo, área e historia familiar de asma. Resultados. La prevalencia acumulada de asma por diagnóstico médico y sibilancia (silbidos fue de 6.8% (IC95% 6.2-7.4 y 20.% (IC95% 19.7-21.8, respectivamente; la prevalencia de sibilancia en los últimos 12 meses fue mayor en el grupo de 6-8 años que en el de 11-14 años(9.7% contra 5.8% (phttp://www.insp.mx/salud/index.html

  17. de la industria maquiladora para la exportación en Ciudad Juárez: una solución factorial

    Directory of Open Access Journals (Sweden)

    Andrés Hernández Gómez

    2015-01-01

    Full Text Available En este artículo se presentan los resultados de un estudio efectuado a personal rela - cionado con el proceso de implantación del Mantenimiento Productivo Total (MPT en empresas de la industria maquiladora de Ciudad Juárez, Chihuahua, México. Se aplicó un Análisis Factorial para identificar los Factores Críticos de Éxito (FCE vinculados con la implantación del MPT. El artículo inicia con la revisión del estado del arte que se llevó a cabo para la identificación de los FCE, los cuales están organizados en aspectos estratégi - cos y administrativos, del desarrollo del recurso humano y técnicos propios del MPT. Con esta información se construyó un instrumento para determinar los FCE en las plantas. La tercera sección describe la metodología, se valida el cuestionario y se justifica la aplicación de las pruebas estadísticas y el Análisis Factorial. La cuarta sección presenta los resultados, iniciando con la descripción del muestreo, conformado por 306 sujetos vinculados con la implantación del MPT. Se identificaron nueve factores críticos de éxito relacionados con la implantación efectiva del MPT, y se discuten sus efectos. Derechos Reservados©2015 Universidad Nacional Autónoma de México, Facultad de Contaduría y Administración. Este es un artículo de acceso abierto distribuido bajo los términos de la Licencia Creative Commons CC BY-NC-ND 4.0.

  18. EL USO DE LA RENDICIÓN DE CUENTAS PARA UN PERIODISMO DE CALIDAD. EL FEMINICIDIO EN JUÁREZ BAJO LA LUPA

    Directory of Open Access Journals (Sweden)

    Adina Barrera Hernández

    2015-06-01

    Full Text Available En México, el periodismo encargado de fuentes ofi ciales se ha caracterizado por reproducir el discurso hegemónico de las instituciones gubernamentales. La falta de una postura crítica ante dicha información, sumada a las lógicas mercantiles de las industrias de la comunicación, provoca que el derecho de las audiencias a la información se confi gure limitadamente. Investigar desde el marco de los derechos humanos y de género obliga al gremio a trabajar en favor de la ciudadanía y a ayudar a la libre crítica del ejercicio de poder y la evaluación del desempeño de las instituciones. Esta es una propuesta para el uso de la rendición de cuentas como herramienta en la investigación sobre el feminicidio en Ciudad Juárez, Chihuahua. AbstractThe journalism, which is in charge of offi cial sources in Mexico, is characterized because of the production of the hegemonic discourse of the governmental institutions. The lack of a critical point of view related to this information, together with commercial activities of the communications industry causes the individuals’ right to obtain information to be limited. Researching human and gender rights requires the guild to work in favor of the citizens and help to exercise the freedom to criticize those in power and to access the effectiveness of governmental institutions. This is a proposal for the use of accountability as a research tool on femicide in Juarez, Chihuahua.

  19. Evaluación térmica del material ISOBLOCK en el clima cálido seco de ciudad. Juárez, México.

    Directory of Open Access Journals (Sweden)

    Luis Carlos Herrera Sosa

    2017-12-01

    Full Text Available Para que las viviendas mejoren su comportamiento térmico y disminuyan el consumo energético, producto del uso excesivo de sistemas de climatización convencional, las Normas de Eficiencia Energética de México establecen un factor de Resistencia Térmica (“R” mínima de acuerdo con cada región climática del país. Este documento presenta las conclusiones del trabajo de investigación térmica del material denominado Isoblock, que consiste en un block de concreto con aislamiento en su interior, que cumple satisfactoriamente con el factor “R” solicitado por la normativa. La investigación busca demostrar que es necesario que la normativa citada contemple la masa térmica de los materiales dentro de los parámetros térmicos a considerar. Desde ese enfoque, la metodología consistió en comparar el Isoblock con un block de concreto convencional en dos módulos de iguales características durante las temporadas climáticas extremas en Ciudad Juárez, Chihuahua. Por último, se simuló térmicamente con el software Design Builder V4.5 y se correlacionaron los resultados para su validación. A partir de dichos resultados se simuló el módulo de Isoblock con mayor cantidad de masa térmica sin variar su espesor, para medir su impacto en la temperatura interior. Los datos obtenidos demuestran que un material con un mismo factor “R” puede alcanzar temperaturas del aire interior más confortables, en temporadas extremas.

  20. La estructura urbana y las diferencias espaciales en el tiempo de traslado del viaje al trabajo en Ciudad Juárez, Chihuahua

    Directory of Open Access Journals (Sweden)

    César M. Fuentes Flores

    2008-01-01

    Full Text Available Este artículo tiene como objetivo analizar las diferencias intraurbanas en los tiempos de traslado del viaje al trabajo en transporte público y privado, asociado a variables de uso del suelo (razón empleo/viviendas, densidad de población, valor del suelo, a características socioeconómicas (proporción de población con ingreso bajo y alto, y a la tenencia de la vivienda (proporción de viviendas propias y rentadas en Ciudad Juárez, Chihuahua. Las variables fueron construidas con información de la Encuesta de Origen-Destino 1997 (IMIP, el XII Censo de Ppoblación y Vivienda 2000 (INEEGI y el XIII Censo Económico 1999 (INEEGI a nivel de AGEB. El análisis se realizó mediante la construcción de cuatro modelos de regresión que se estimaron mediante la técnica de mínimos cuadrados ordinarios. Los resultados muestran que las variables razón empleo/viviendas, valor del suelo, y proporción de viviendas rentadas son estadísticamente significativas para explicar menores tiempos de traslado en transporte público. En contraste, la densidad de población y la proporción de viviendas propias son estadísticamente significativas para explicar menores tiempos de traslado en transporte público. La proporción de población de bajos ingresos es estadísticamente significativa para explicar los cambios en los tiempos de traslado en transporte privado.

  1. La genealogía de los reglamentos escolares en México: análisis de la obra de Rafael Ramírez

    Directory of Open Access Journals (Sweden)

    Ana Cecilia Valencia Aguirre

    2011-01-01

    Full Text Available Este trabajo es resultado de un análisis cuya pregunta central es ¿Cuál es la genealogía de los reglamentos en las escuelas de educación primaria en México? el objetivo es analizar la obra de Rafael Ramírez, a través de la literatura formativa de los profesores, considerada un elemento fundacional de los mandatos institucionales de la escuela primaria, ya que genera un discurso que instituye la normatividad en la escuela básica mexicana. El método utilizado es el análisis crítico del discurso de Van Dijk, los actos de habla de Searle y la perspectiva de las metáforas de la vida cotidiana de Lakoff. La hipótesis que orienta la indagación plantea que los primeros pasos de la institucionalización del control escolar estuvieron atravesados por el discurso cristiano-católico expresado en diversos interdiscursos de la época y fundamentalmente en los reglamentos escolares que comenzaron a aparecer como parte de la literatura formativa de los profesores de escuelas primarias. Dicho análisis permite concluir que esta literatura refleja gran parte del imaginario de los profesores de escuelas públicas, ya que expresa un nacionalismobasado en el imaginario de la familia nuclear cristiana, elemento clave que configuró una de las imágenes más vivas en la conformación del estado mexicano posrevolucionario.

  2. Evaluación del desempeño del docente de la unidad educativa Prof. Fernando Ramírez

    Directory of Open Access Journals (Sweden)

    Jorge F. Ojeda Rodríguez

    2012-04-01

    Full Text Available En la aplicación práctica de sistema de evaluación del desempeño de los maestros cada día recobra más importancia en pro de mejorar las cualidades profesionales del docente. Por lo que el propósito de este estudio es analizar el Evaluación Del Desempeño Del Docente De La Unidad Educativa Prof. Fernando Ramírez Municipio Independencia Estado Yaracuy, en sus dimensiones pedagógicas, emocional y de responsabilidad se fundamenta en una investigación descriptiva apoyado en un diseño de campo. La población estuvo representada por treinta y dos (32 docentes que laboran en el plantel objeto de este estudio, la muestra fue la totalidad de la población, para recolectar la información se elaboró como instrumento un cuestionario de 30 ítems con escala tipo Likert con cuatro alternativas de respuestas el cual se sometió a la validez de contenido a través del juicio de expertos, asimismo se aplicó el Coeficiente de Confiabilidad Alfa-Cronbach, obteniéndose como resultado 0,90. Para analizar la información se procedió a la tabulación, codificación y graficación de datos. Sobre la base de los resultados se presentaron las conclusiones del estudio.

  3. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

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

  4. Hybrid adsorptive membrane reactor

    Science.gov (United States)

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

    2011-03-01

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

  5. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-11-01

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

  6. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-01

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

  7. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-15

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

  8. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-09-15

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

  9. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-15

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

  10. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-01

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

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

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

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

  12. The CEA research reactors

    International Nuclear Information System (INIS)

    Schwartz, J.P.

    1993-01-01

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

  13. Atomic reactor thermal engineering

    International Nuclear Information System (INIS)

    Kim, Gwang Ryong

    1983-02-01

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

  14. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

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

  15. Neutron and photon spectrometry in mixed radiation fields

    International Nuclear Information System (INIS)

    Jancar, A.; Kopecky, Z.; Veskrna, M.

    2014-01-01

    Spectrometric measurements of the mixed fields of neutron and photon radiation in the workplaces with the L-R-0 research reactor located in the UJV Rez and with the Van de Graaff accelerator, located in the UTEF laboratories Prague, are presented in this paper. The experimental spectrometric measurements were performed using a newly developed digital measuring system, based on the technology of analog-digital converters with a very high sampling frequency (up to 2 GHz), in connection with organic scintillation detector, type BC-501A, and stilbene detector. The results of experimental measurements show high quality of spectrometry mixed fields of neutron and photon radiation across the wide dynamic range of measured energy. (authors)

  16. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

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

  17. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

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

  19. Reactor container

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

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

  1. Nuclear reactor neutron shielding

    Science.gov (United States)

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

    2017-09-12

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

  2. Desarrollo de un destino de turismo médico en el contexto de la frontera México-Estados Unidos: el caso de Ciudad Juárez, Chihuahua, México

    OpenAIRE

    Martínez Almanza, María Teresa

    2016-01-01

    La asistencia sanitaria es uno de los temas primordiales del siglo XXI. Los problemas relacionados con la atención médica contemporánea han generado una creciente demanda de servicios de pacientes extranjeros. En el marco de la teoría fundamentada, mediante 69 entrevistas en profundidad, realizadas de 2013 a 2015, se analiza el proceso de desarrollo de Ciudad Juárez, Chihuahua, México como un destino turístico médico de frontera. Se presenta una narrativa de la génesis y evolución del caso d...

  3. Algunos coleópteros (Coleoptera: Carabidae, Promecheilidae) de islas Diego Ramírez (56º 32S; 68º 43W), Región de Magallanes

    OpenAIRE

    Elgueta, Mario; Flores, Gustavo Ernesto; Roig Junent, Fidel Alejandro

    2015-01-01

    En la presente contribución se entrega información sobre la identificación y antecedentes por primera vez de tres especies de coleópteros de las islas Diego Ramírez. Hasta el momento se reconoció la presencia de insectos en estas islas solo a nivel de familias o géneros. Se presenta un comentario zoogeográfico. Fil: Elgueta, Mario. Area Entomología, Museo Nacional de Historia Natural; Chile; Fil: Flores, Gustavo Ernesto. Consejo Nacional de Invest.cientif.y Tecnicas. Centro Cientifico T...

  4. Diarios de campo extranjeros y diarios de campo nacionales. Indiferencias de José Pérez de Barradas y de Gregorio Hernández de Alba en Tierradrento y San Agustín.

    Directory of Open Access Journals (Sweden)

    Carl Henrik Langebaek Rueda

    2010-07-01

    Full Text Available This article compares the feld experience of two archaeologists and anthropologists who worked in colombia in the thirties of the twentieth century. The practices of professional exercise are discussed from the feld logs of spanish national José Pérez de barradas and colombian gregorio hernández de alba. this comparison serves to put the work of the foreigner and the colombian into perspective in relation with the construction of professional discipline, the image of nature and the indigenous, as well as the tension between the “nationalist” proposal and criticism of it by foreigners.

  5. Evaluación de calidad en la colangiopancreatografía retrógrada endoscópica en el Hospital Universitario Clínico Quirúrgico Comandante Faustino Pérez Hernández

    OpenAIRE

    Ramos Pachón, Carlos Manuel; Ávalos García, Roxana; Haza Medina, Teresa; Umpierre García, Ibis

    2013-01-01

    Fundamento: es responsabilidad de los endoscopistas garantizar la realización de procederes de calidad, la cual se basa en parámetros definidos por las diferentes sociedades de endoscopia a nivel mundial. Objetivo: evaluar la calidad en la atención a pacientes que se realizaron la colangiopancreatografía retrógrada endoscópica en el hospital Faustino Pérez Hernández. Métodos: se realizó un estudio de evaluación de la calidad de las colangiopancreatografías retrógradas endoscópicas, describién...

  6. 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.)

  7. The prototype fast reactor

    International Nuclear Information System (INIS)

    Broomfield, A.M.

    1985-01-01

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

  8. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

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

  9. NCSU Reactor Sharing Program

    International Nuclear Information System (INIS)

    Perez, P.B.

    1993-01-01

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

  10. Reactor safety method

    International Nuclear Information System (INIS)

    Vachon, L.J.

    1980-01-01

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

  11. Un manual español de administración y contabilidad señorial de principios de siglo XVII: el compendio en materia de acrecentar Estado y hazienda, tocante al oficio de contador, de Gabriel Pérez del Barrio Angulo. (A Spanish guide book on administration and accounting of the early 17th Century: the compendium for the increase of the state and treasury, with regards to the post of accountant, by Gabriel Pérez del Barrio Angulo)

    OpenAIRE

    González Ferrando, José Mª

    2013-01-01

    Frente a lo ocurrido en Inglaterra, donde cuentan con manuscritos sobre administración y contabilidad señorial desde el siglo XIII, en España sólo se conocen hasta ahora cuatro textos de los siglos XV al XVII en que sus autores se ocupan con mayor o menor detalle de este asunto, pero de los que sólo uno, publicado inicialmente en 1613, puede equipararse en cierto modo a los ingleses: el ‘Compendio en razón de acrecentar Estado y Hacienda y Oficio de Contador’ de Gabriel Pérez del Barrio. (Aga...

  12. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

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

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

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

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

  14. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

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

  15. El problema de la felicidad en Aristóte- les: respuestas desde Francisco Suárez y Martha Nussbaum

    Directory of Open Access Journals (Sweden)

    Rosa Colmenarejo Fernández

    2017-09-01

    Full Text Available La idea de felicidad en Aristóteles está mediada por el sentido teleológico que otorga a la vida humana. La vida está orientada de un modo intrínseco e inherente hacia la eudaimonía, hacia la vida buena. Este es, grosso modo, el fundamento de la ética aristotélica. En este trabajo se pretenden confrontar las respuestas, en tanto que interpretaciones, de la idea de felicidad que han obtenido dos autores que apoyan sus respectivas teorías éticas en los planteamientos aristotélicos de felicidad. Sin embargo, las respuestas son bien distintas, y dependen de los presupuestos metafísicos de ambos autores. Mientras Francisco Suárez (1548-1617 desde la comprensión del ser humano como un ser en relación, la idea de vida buena le lleva a desarrollar lo que algunos han denominado un “antropocentrismo crítico” de clara inspiración ignaciana, en la que nunca pierde de vista el valor de lo social como fuente primera para la caracterización de lo humano ni el sentido trascendente del fin último de la vida humana; Martha Nussbaum (1947 se servirá de una interpretación ilustrada, que inspirará el pensamiento liberal posterior, para justificar la radical diferenciación del yo como paso ineludible para el reconocimiento de aquello que nos hace humanos, aquello que denomina “capacidades centrales”. Los cuatrocientos años que median entre ambas propuestas nos parecen más que una medida de inconmensurabilidad, una oportunidad para sustentar la crítica denominada “individualismo metodológico”, una de las más controvertidas que ha recibido el denominado Enfoque de las Capacidades Humanas, desarrollado entre otros por la propia Nussbaum junto a Amartya Sen a partir de los años 1980.

  16. Postponed Is Not Canceled: Role of Craniospinal Radiation Therapy in the Management of Recurrent Infant Medulloblastoma—An Experience From the HIT-REZ 1997 and 2005 Studies

    Energy Technology Data Exchange (ETDEWEB)

    Müller, Klaus, E-mail: Klaus.Mueller@medizin.uni-leipzig.de [Department of Radiation Oncology, University of Leipzig Medical Center, Leipzig (Germany); Mynarek, Martin [Department of Pediatric Hematology and Oncology, University Medical Center Hamburg-Eppendorf, Hamburg (Germany); Zwiener, Isabella [Institute for Medical Biostatistics, Epidemiology and Informatics, University of Mainz Medical Center, Mainz (Germany); Siegler, Nele [University Hospital of Essen, Pediatrics III, Essen (Germany); Zimmermann, Martina [Department of Pediatric Hematology and Oncology, Children' s Hospital, University Hospital of Bonn, Bonn (Germany); Christiansen, Hans [Department of Radiotherapy, Hannover Medical School, Hannover (Germany); Budach, Wilfried [Clinic and Policlinic for Radiation Therapy and Radiooncology, University of Düsseldorf, Düsseldorf (Germany); Henke, Guido [Department of Radiation Oncology, Kantonsspital St. Gallen, St. Gallen (Switzerland); Warmuth-Metz, Monika [Department of Neuroradiology, University of Würzburg, Würzburg (Germany); Pietsch, Torsten [Department of Neuropathology, University of Bonn Medical Center, Bonn (Germany); Hoff, Katja von [Department of Pediatric Hematology and Oncology, University Medical Center Hamburg-Eppendorf, Hamburg (Germany); Bueren, Andre von [Department of Pediatric Hematology and Oncology, University Medical Center Hamburg-Eppendorf, Hamburg (Germany); Division of Pediatric Hematology and Oncology, Department of Pediatrics and Adolescent Medicine, University Medical Center Göttingen, Göttingen (Germany); Bode, Udo [Department of Pediatric Hematology and Oncology, Children' s Hospital, University Hospital of Bonn, Bonn (Germany); and others

    2014-04-01

    Purpose: To evaluate the efficacy of craniospinal irradiation (CSI) in the management of recurrent infant medulloblastoma after surgery and chemotherapy alone. Methods and Materials: Seventeen pediatric medulloblastoma patients registered in the HIT-REZ 1997 and 2005 studies underwent CSI as salvage treatment at first recurrence. All patients had achieved complete remission after first-line treatment consisting of surgery and chemotherapy. Eleven patients showed metastatic disease at relapse. Five patients underwent surgery prior to radiation therapy, which resulted in complete resection in 1 case. In 1 patient, complete resection of the residual tumor was performed after CSI. Eleven patients received chemotherapy prior, 6 patients during and 8 patients after CSI. All patients received CSI with a median total dose of 35.2 Gy, and all but 1 received a boost to the posterior fossa (median total dose, 55.0 Gy). Metastases were boosted with an individual radiation dose, depending on their location and extent. Results: During a median follow-up time of 6.2 years since recurrence, 11 patients showed progressive disease and died. Median progression-free (overall) survival was 2.9 ± 1.1 (3.8 ± 0.8) years. Progression-free survival (PFS) rates at 1, 3, and 5 years were 88% ± 8%, 46% ± 12%, and 40% ± 12%, respectively. Overall survival (OS) rates at 1, 3, and 5 years were 94% ± 6%, 58% ± 12%, and 39% ± 12%, respectively. For 11 patients with classic medulloblastoma, 3-year (and 5-year) PFS and OS were 62% ± 15% and 72% ± 14% (52% ± 16% and 51% ± 16%), respectively. On univariate analysis, metastatic disease was not associated with poorer progression-free and overall survival. Conclusions: Our results suggest that salvage treatment of relapsed medulloblastomas consisting of CSI and chemotherapy offers a second chance for cure, even for patients with classic histological findings. Metastatic disease at relapse did not have an impact

  17. Utilización de antimicrobianos en el Hogar materno Doña Leonor Pérez durante el período 2007-2009

    Directory of Open Access Journals (Sweden)

    Jessy Pavón Pérez

    2013-03-01

    Full Text Available Introducción: el uso inadecuado de los medicamentos supone un importante problema sanitario y económico, más sensible en el caso de los niños, ancianos y las embarazadas. Existen una gran diversidad de medicamentos y sobre muchos de ellos no se tiene un criterio definitivo de su inocuidad, por lo que la información disponible para la prescripción de fármacos en mujeres embarazadas, es muy escasa. Objetivo: evaluar la calidad en el uso racional de antimicrobianos en las gestantes ingresadas en el Hogar materno «Doña Leonor Pérez Cabrera» durante el período 2007- 2009. Métodos: este trabajo constituye un estudio de utilización de medicamento del tipo indicación prescripción, retrospectivo y descriptivo. Se revisaron las historias clínicas y se obtuvieron las variables biosociales edad materna, edad gestacional al ingreso, ocupación, diagnóstico que precisó el uso de antimicrobianos, forma de diagnóstico más utilizado así como los antimicrobianos más prescritos. Resultados: a través del análisis de las variables y de los esquemas terapéuticos se pudo evaluar la calidad de la prescripción de los antimicrobianos. Los resultados obtenidos permitieron constatar que predominaron las gestantes con edades entre 21 y 30 años, con edades gestacionales al ingreso entre 21 y 30 semanas y trabajadoras. La patología que mayormente motivó la utilización de antimicrobianos fue la sepsis vaginal, diagnosticada de forma clínica en casi la totalidad de los casos y los antimicrobianos más prescritos fueron la azitromicina, metronidazol, clotrimazol y nistatina. Conclusiones: con excepción de algunos antimicrobianos prescritos, la calidad de la prescripción en su mayoría resultó adecuada, la efectividad del tratamiento en su mayor parte fue buena y en general el uso racional de los antimicrobianos clasificó como alta y aceptable.

  18. Un programa de fertilización sustentable para el Ingenio "Presidente Benito Juárez" en Tabasco, México

    Directory of Open Access Journals (Sweden)

    S. Salgado-García

    2011-01-01

    Full Text Available Las dosis de fertilización y sitio específicos para el cultivo de caña de azúcar en el área de abastecimiento del Ingenio "Presidente Benito Juárez" (Ipbj no habían sido precisados, sin embargo, el alto costo de los fertilizantes químicos y la necesidad de reducir la contaminación del ambiente obligan a optimizar su uso. A fin de precisar dosis de fertilización adecuadas para dicha área, este trabajo emplea la metodología del "Sistema Integrado para Recomendar Dosis de Fertilizantes", tomando en cuenta las características de los suelos y el rendimiento potencial. Como parte de este estudio, se identificaron las subunidades de suelo mediante interpretación de fotografías aéreas, reconocimientos de campo y muestreos (-1.20 m en el área de influencia del Ipbj (92,973 ha. En cada unidad se describieron perfiles agrológicos y se hicieron análisis físico-químicos para clasificar los suelos, según el Referencial Mundial de Suelos (wrb. Los resultados generaron cinco polígonos de Thiessen, con precipitaciones anuales entre 1,640 a 2,227 mm. Se determinó una dosis de fertilización npk para cada subunidad de suelo, usando el modelo conceptual de balance entre demanda del nutrimento, el suministro y la eficiencia del fertilizante aplicado. Las dosis de fertilización ajustadas son (N, P2O5, K2O kg/ha, 120-60-60 para los suelos Cambisolesflúvicos, endogléyicos y estágnicos, 120-70-80 para Cambisoles y Gleysoles; 160-80-80 para Vertisoles gléyico-estágnicos, 120-80-80 para Vertisoles estágnico-éutricos. Además, se generó un mapa de fertilización específico para el área de abasto del Ipbj, a escala 1:40 000.

  19. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Yasutomi, Yoshiyuki; Nakagawa, Moroo; Sawai, Yuichi; Chiba, Akio; Suzuki, Yasutaka.

    1997-01-01

    Silicon composited with reinforcing metals is used for a divertor cooling substrate having an effect as a cooling tube to provide a silicon base composite material having increased electric resistance and toughness. The blending ratio of reinforcing materials in the form of granules, whiskers or long fibers is controlled in order to control heat conductivity, electric resistivity and mechanical performances. The divertor cooling substrate comprising the silicon base composite material is integrated with a plasma facing material. The production method therefor includes ordinary metal matrix composite forming methods such as powder metallurgy, melting penetration method, high pressure solidification casting method, centrifugal casting method and vacuum casting method. Since the cooling plate is constituted with the light metal and highly electric resistant metal base composite material, sharing force due to eddy current can be reduced, and radiation exposure can be minimized. Accordingly, a cooling structure for a thermonuclear reactor effective for the improvement of environmental problems caused by waste disposal can be attained. (N.H.)

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  1. Nuclear reactors

    International Nuclear Information System (INIS)

    Pearson, K.G.

    1977-01-01

    Reference is made to auxiliary means of cooling the nuclear fuel clusters used in light or heavy water cooled nuclear reactors. One method is to provide one or more spray cooling tubes. From holes in the side walls of those tubes coolant water may be sprayed laterally into the cluster against the rods. The flow of main coolant may thus be supplemented or even replaced by the auxiliary coolant. A difficulty, however, is that only those fuel rods close to a spray cooling tube can readily be reached by the auxiliary coolant. In the arrangement described, where the fuel rods are spaced apart by transverse grids, at least one of the interspaces between the grids is provided with an axially extending auxiliary coolant conduit having lateral holes through which an auxiliary coolant is sprayed into the cluster. A deflector is provided that extends from a transverse grid into a position in front of the holes and deflects auxiliary coolant on to parts of the fuel rods otherwise inaccessible to the auxiliary coolant. The construction of the deflector is described. (U.K.)

  2. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

    A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

  3. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

    The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

  4. Experimental facilities for Generation IV reactors research

    International Nuclear Information System (INIS)

    Krecanova, E.; Di Gabriele, F.; Berka, J.; Zychova, M.; Macak, J.; Vojacek, A.

    2013-06-01

    Centrum Vyzkumu Rez (CVR) is research and development Company situated in Czech Republic and member of the UJV group. One of its major fields is material research for Generation IV reactor concepts, especially supercritical water-cooled reactor (SCWR), very high temperature/gas-cooled fast reactor (VHTR/GFR) and lead-cooled fast reactor (LFR). The CVR is equipped by and is building unique experimental facilities which simulate the environment in the active zones of these reactor concepts and enable to pre-qualify and to select proper constructional materials for the most stressed components of the facility (cladding, vessel, piping). New infrastructure is founded within the Sustainable Energy project focused on implementation the Generation IV and fusion experimental facilities. The research of SCWR concept is divided to research and development of the constructional materials ensured by SuperCritical Water Loop (SCWL) and fuel components research on Fuel Qualification Test loop (SCWL-FQT). SCWL provides environment of the primary circuits of European SCWR, pressure 25 MPa, temperature 600 deg. C and its major purpose is to simulate behavior of the primary medium and candidate constructional materials. On-line monitoring system is included to collect the operational data relevant to experiment and its evaluation (pH, conductivity, chemical species concentration). SCWL-FQT is facility focused on the behavior of cladding material and fuel at the conditions of so-called preheater, the first pass of the medium through the fuel (in case of European SCWR concept). The conditions are 450 deg. C and 25 MPa. SCWL-FQT is unique facility enabling research of the shortened fuel rods. VHTR/GFR research covers material testing and also cleaning methods of the medium in primary circuit. The High Temperature Helium Loop (HTHL) enables exposure of materials and simulates the VHTR/GFR core environment to analyze the behavior of medium, especially in presence of organic compounds and

  5. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  6. Nuclear Research Institute Rez view

    International Nuclear Information System (INIS)

    Biza, K.; Pazdera, F.; Vasa, I.; Zdarek, J.

    2004-01-01

    In this presentation author deals with the present state and perspectives of nuclear energy in the Czech Republic and in the Slovak Republic. It is concluded that lifetime extension and finalization of Mochovce NPP Units 3 and 4 is the cheapest solution for base load production of electricity and is in line with the European union energy challenges: - decrease of carbon dioxide emissions; dependence on energy sources from politically unstable regions; decrease import dependence on energy sources. Nuclear energy is one of important sources for long term sustainability in energy. GEN IV is successful with meet the new requirements after 2025. We should participate on this long term development effort

  7. The fast breeder reactor

    International Nuclear Information System (INIS)

    Collier, J.

    1990-01-01

    The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

  8. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

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

  9. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  10. Guide to power reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

  11. Reactor core of FBR type reactor

    International Nuclear Information System (INIS)

    Hayashi, Hideyuki; Ichimiya, Masakazu.

    1994-01-01

    A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

  12. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  13. Tokamak reactor studies

    International Nuclear Information System (INIS)

    Baker, C.C.

    1981-01-01

    This paper presents an overview of tokamak reactor studies with particular attention to commercial reactor concepts developed within the last three years. Emphasis is placed on DT fueled reactors for electricity production. A brief history of tokamak reactor studies is presented. The STARFIRE, NUWMAK, and HFCTR studies are highlighted. Recent developments that have increased the commercial attractiveness of tokamak reactor designs are discussed. These developments include smaller plant sizes, higher first wall loadings, improved maintenance concepts, steady-state operation, non-divertor particle control, and improved reactor safety features

  14. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  15. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  16. ¿La práctica de la siembra directa en cultivos de soja favorece las poblaciones de acridios (Orthoptera: Acrididae en el partido de Benito Juárez? Does the direct tillage practice in soybean crops favour grasshopper populations (Orthoptera: Acrididae, in Benito Juárez county?

    Directory of Open Access Journals (Sweden)

    Daniel Scuffi

    2012-12-01

    Full Text Available Considerando el desarrollo del cultivo de soja en siembra directa en el partido de Benito Juárez, y que algunos autores sostienen que esta práctica favorece los acridios, se evaluó la riqueza de especies y la abundancia en soja con siembra directa y convencional. Se registraron siete especies (Aleuas lineatus Stål, Covasacris pallidinota (Bruner, Baeacris pseudopunctulatus (Ronderos, Dichroplus elongatus Giglio-Tos, Dichroplus maculipennis (Blanchard, Dichroplus pratensis Bruner y Scotussa lemniscata (Stål. La riqueza de especies acumulada en los diferentes cultivos fue similar (p> 0,05. En soja de primera con siembra directa, se registraron 2,3 ± 0,19 especies, en soja de primera con siembra convencional 1,45 ± 0,15 especies y en soja de segunda con siembra directa 2,25 ± 0,28 especies. Dichroplus elongatus fue la especie más abundante en todos los cultivos y en todos los momentos. Las restantes presentaron baja abundancia y se registraron en algunos momentos. No existió diferencia (p> 0,05 en la abundancia de tucuras entre los cultivos y en las diferentes fechas de muestreo. La baja riqueza de especies registrada estaría relacionada con la baja diversidad vegetal de los cultivos. Este estudio no mostró diferencias en la abundancia y riqueza de especies de acuerdo a la labranza utilizada.Considering the development of the soybean crops using direct tillage in Benito Juárez county, and taking into account that for some authors this practice favours the grasshopper populations, the abundance and species richness in soybean with direct and conventional tillage were evaluated. Seven species were registered (Aleuas lineatus Stål, Covasacris pallidinota (Bruner, Baeacris pseudopunctulatus (Ronderos, Dichroplus elongatus Giglio-Tos, Dichroplus maculipennis (Blanchard, Dichroplus pratensis Bruner and Scotussa lemniscata (Stål. The accumulated richness was similar (p> 0.05, along the different crops; 2.3 ± 0.19 species were registered in

  17. Disponibilidad de esporomas de hongos comestibles en los bosques de pino-encino de Ixtlán de Juárez, Oaxaca Edible mushroom sporocarp availability in pine-oak forests in Ixtlán de Juárez, Oaxaca

    Directory of Open Access Journals (Sweden)

    Roberto Garibay-Orijel

    2009-08-01

    Full Text Available Los hongos comestibles son recursos forestales cuyo aprovechamiento sustentable depende del conocimiento de la distribución y productividad de sus esporomas. En el presente trabajo se evaluó la disponibilidad de 81 hongos comestibles por medio de la abundancia, distribución temporal y espacial de sus esporomas. Estas variables se integraron en un índice de importancia ecológica (VI que brinda una medida para estimar la disponibilidad de sus esporomas en los bosques. El estudio se realizó durante 2001 y 2002 en los bosques de Pinus-Quercus de Ixtlán de Juárez, Oaxaca. Las especies más abundantes fueron Laccaria laccata var. pallidifolia, Gymnopus confluens y Laccaria vinaceobrunnea. La especie con mayor producción de biomasa húmeda de esporomas (2.21 Kg/sitio de muestreo fue Laccaria laccata var. Pallidifolia. Sólo G. confluens y G. dryophilus produjeron esporomas desde principios de junio hasta finales de octubre. Las especies con mayor disponibilidad fueron L. laccata var. pallidifolia, G. confluens, L. vinaceobrunnea y H. purpurascens. La riqueza de hongos comestibles silvestres en Ixtlán es alta (96 especies, pero su disponibilidad es muy heterogénea (de L. laccata var. pallidifolia VI = 0.7905, a Helvella infula VI = 0.0055. Dentro del mismo bosque, en sitios relativamente cercanos la composición de especies es diferente y su producción de esporomas y biomasa son contrastantes.Wild edible mushrooms are non timber forest products whose sustainable use must have an ecological basis. In this work, we measured the availability of 81 edible mushrooms by means of their abundance, frequency, biomass production, temporal and spatial distribution of their fruiting bodies. These variables were integrated into an ecological importance index (IV which describes sporome availability in the forest. The research was carried out during 2001 and 2002 in the Pinus-Quercus forests of Ixtlán de Juárez, Oaxaca. The most abundant species were

  18. Flux effect on neutron irradiation embrittlement of reactor pressure vessel steels irradiated to high fluences

    International Nuclear Information System (INIS)

    Soneda, N.; Dohi, K.; Nishida, K.; Nomoto, A.; Iwasaki, M.; Tsuno, S.; Akiyama, T.; Watanabe, S.; Ohta, T.

    2011-01-01

    Neutron irradiation embrittlement of reactor pressure vessel (RPV) steels is of great concern for the long term operation of light water reactors. In particular, the embrittlement of the RPV steels of pressurized water reactors (PWRs) at very high fluences beyond 6*10 19 n/cm 2 , E > 1 MeV, needs to be understood in more depth because materials irradiated in material test reactors (MTRs) to such high fluences show larger shifts than predicted by current embrittlement correlation equations available worldwide. The primary difference between the irradiation conditions of MTRs and surveillance capsules is the neutron flux. The neutron flux of MTR is typically more than one order of magnitude higher than that of surveillance capsule, but it is not necessarily clear if this difference in neutron flux causes difference in mechanical properties of RPV. In this paper, we perform direct comparison, in terms of mechanical property and microstructure, between the materials irradiated in surveillance capsules and MTRs to clarify the effect of flux at very high fluences and fluxes. We irradiate the archive materials of some of the commercial reactors in Japan in the MTR, LVR-15, of NRI Rez, Czech Republic. Charpy impact test results of the MTR-irradiated materials are compared with the data from surveillance tests. The comparison of the results of microstructural analyses by means of atom probe tomography is also described to demonstrate the similarity / differences in surveillance and MTR-irradiated materials in terms of solute atom behavior. It appears that high Cu material irradiated in a MTR presents larger shifts than those of surveillance data, while low Cu materials present similar embrittlement. The microstructural changes caused by MTR irradiation and surveillance irradiation are clearly different

  19. Research reactor spent nuclear fuel shipment from the Czech Republic to the Russian Federation

    International Nuclear Information System (INIS)

    Svoboda, K.; Broz, V.; Novosad, P.; Podlaha, J.; Svitak, F.

    2009-01-01

    In May 2004, the Global Threat Reduction Initiative agreement was signed by the governments of the United States and the Russian Federation. The goal of this initiative is to minimize, in cooperation with the International Atomic Energy Agency (IAEA) in Vienna, the existing threat of misuse of nuclear and radioactive materials for terrorist purposes, particularly highly enriched uranium (HEU), fresh and spent nuclear fuel (SNF), and plutonium, which have been stored in a number of countries. Within the framework of the initiative, HEU materials and SNF from research reactors of Russian origin will be transported back to the Russian Federation for reprocessing/liquidation. The program is designated as the Russian Research Reactor Fuel Return (RRRFR) Program and is similar to the U.S. Foreign Research Reactor Spent Nuclear Fuel Acceptance Program, which is underway for nuclear materials of United States origin. These RRRFR activities are carried out under the responsibilities of the respective ministries (i.e., U.S. Department of Energy (DOE) and Russian Federation Rosatom). The Czech Republic and the Nuclear Research Institute Rez, plc (NRI) joined Global Threat Reduction Initiative in 2004. During NRI's more than 50 years of existence, radioactive and nuclear materials had accumulated and had been safely stored on its grounds. In 1995, the Czech regulatory body , State Office for Nuclear Safety (SONS), instructed NRI that all ecological burdens from its past activities must be addressed and that the SNF from the research reactor LVR -15 had to be transported for reprocessing. At the end of November 2007, all these activities culminated with the unique shipment to the Russian Federation of 527 fuel assemblies of SNF type EK-10 (enrichment 10% U-235) and IRT-M (enrichment 36% and 80% U-235) and 657 irradiated fuel rods of EK-10 fuel, which were used in LVR-15 reactor. (authors)

  20. A report on recent progress of Central Analytical Laboratory (NRI Rez plc.) for upgrading capabilities for identification of illicit nuclear materials

    International Nuclear Information System (INIS)

    Malek, Z.; Sus, F.

    2002-01-01

    Nuclear Research Institute Rez plc in the Central Analytical Laboratory under co-ordination of the European Commission Joint Research Centre 'Institute for Transuranium Elements' in Karlsruhe (ITU). In the framework of this PHARE project, the corresponding analytical capabilities of the Central Analytical Laboratory (CAL) of NRI have been substantially upgraded. In case of requested analysis of nuclear material of unknown origin seized in the Czech Republic it is now possible - after categorization by standard isotopic measurements - to perform a rapid precision measurement of impurity contents. This upgrade has been successfully applied to complementary measurements of nuclear material previously seized in the Czech Republic. The related results were included in a compilation of data characteristic for nuclear material used in Czech research facilities. The complete set has been incorporated in the nuclear material database system available at ITU Karlsruhe. In order to develop a common scheme for complementary analyses of nuclear material of unknown origin in the respective EU institutions - upon request of a partner state's nuclear regulatory authority - selected sample material was shipped to ITU Karlsruhe (part of the EU's Joint Research Centre JRC) and corresponding analyses were performed. The experience gained therein can be used as model for an interface procedure which in case of necessity can be invoked on short notice. These activities laid an excellent basis for a co-operation of both SONS and NRI with the Joint Research Center of the European Commission in the fields of: elaboration of state response procedures following seizure of vagabonding nuclear material; qualification of analytical procedures for nuclear safeguards. In the 2001 CAL of NRI participated in the second interlaboratory comparison (Round Robin) exercise, organized by the Nuclear Smuggling International Technical Working Group (ITWG), oriented towards forensic analysis of a selected high

  1. Identificación de asentamientos irregulares y diagnóstico de sus necesidades de infraestructura en Ciudad Juárez, Chihuahua, México

    Directory of Open Access Journals (Sweden)

    Ivan Elias Ruiz Hernandez

    2015-01-01

    ón remota, análisis espacial e información censal. Los atributos físicos incluyen las condiciones del terreno, disección vertical y zonas de riesgo geológico y de inundación. Los atributos socioeconómicos incluyen, polígonos de pobreza, cobertura de agua potable y drenaje, nivel de hacinamiento, relación centro-periferia y valor del suelo. Los atributos de organización espacial y tipo de materiales de construcción, fueron recabados de imágenes satelitales de alta resolución y métricas de paisaje. Estos tres grupos de variables fueron integrados en un modelo multicriterio para la identificación de AI en Ciudad Juárez, Chihuahua, México. El modelo permite no solo la identificación de dichos AI sino también la realización de un diagnóstico de sus necesidades de infraestructura y servicios urbanos contando con un nivel de exactitud del 97.66%. Esta investigación presenta un método nuevo y confiable para la identificación de AI y a su vez los resultados obtenidos proveen una importante herramienta para los responsables del desarrollo urbano en la toma de decisiones.

  2. América en la librería de don Lorenzo Ramírez de Prado, Consejero de Indias

    Directory of Open Access Journals (Sweden)

    Nieves Pena Sueiro

    2013-12-01

    Full Text Available El estudio de inventarios de bibliotecas del Siglo de Oro resulta de gran importancia para aquellos que se interesan por la cultura áurea, pues desvela datos sobre sus poseedores; también sobre lecturas, obras, ejemplares, etc., que de otra manera no podríamos conocer. Una de las bibliotecas más importantes del siglo XVII fue la de don Lorenzo Ramírez de Prado, erudito y bibliófilo, que reunió en su casa madrileña por lo menos unos 8.951 volúmenes. Quizás la especial relación que tuvo don Lorenzo con América a lo largo de su vida –fue ahijado del humanista Pedro de Valencia, cronista de Indias; fue Consejero de Indias desde 1626 hasta su muerte, como también lo fue su hermano Alonso; otro de sus hermanos, Marcos, fue obispo de Michoacán, etc.–, influyó en que entre los fondos de su biblioteca se encuentren las principales obras de tema americano y algunas editadas en el Nuevo Mundo. En este trabajo pretendemos, tras el examen exhaustivo del inventario, ofrecer una relación de los registros del fondo americano (tema americano y obras impresas en América que existían en la librería en el momento en que se inventarió, seguido del análisis y las conclusiones de este. The study of library inventories of the Golden Age is of great interest to those who study the culture of this period, as it reveals much about their owners, and also about readings, plays, copies, etc. about which otherwise we would not know. One of the most important libraries of the seventeenth century was that of Don Lorenzo Ramirez de Prado, erudite and bibliophile, who collected in his Madrid home at least 8,951 volumes. Don Lorenzo was godson of the humanist Pedro de Valencia, chronicler of the Indies, he was Counselor of the Indies from 1626 until his death, as was his brother Alonso; another brother, Marcos, was Bishop of Michoacan. Perhaps the special relationship that Don Lorenzo had with America throughout his life was the reason that among the

  3. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  4. Reactor System Design

    International Nuclear Information System (INIS)

    Chi, S. K.; Kim, G. K.; Yeo, J. W.

    2006-08-01

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  5. Fusion reactor design studies

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Santarius, J.F.

    1990-01-01

    This report discusses the following topics on the ARIES tokamak: systems; plasma power balance; impurity control and fusion ash removal; fusion product ripple loss; energy conversion; reactor fueling; first wall design; shield design; reactor safety; and fuel cost and resources

  6. 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

  7. Control for nuclear reactor

    International Nuclear Information System (INIS)

    Ash, E.B.; Bernath, L.; Facha, J.V.

    1980-01-01

    A nuclear reactor is provided with several hydraulically-supported spherical bodies having a high neutron absorption cross section, which fall by gravity into the core region of the reactor when the flow of supporting fluid is shut off. (auth)

  8. Hybrid plasmachemical reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lelevkin, V. M., E-mail: lelevkin44@mail.ru; Smirnova, Yu. G.; Tokarev, A. V. [Kyrgyz-Russian Slavic University (Kyrgyzstan)

    2015-04-15

    A hybrid plasmachemical reactor on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the reactor as functions of the dielectric barrier discharge parameters are determined.

  9. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2002-01-01

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  10. Guidebook to nuclear reactors

    International Nuclear Information System (INIS)

    Nero, A.V. Jr.

    1976-05-01

    A general introduction to reactor physics and theory is followed by descriptions of commercial nuclear reactor types. Future directions for nuclear power are also discussed. The technical level of the material is suitable for laymen

  11. continuous stirred tank reactor (CSTR)

    African Journals Online (AJOL)

    AFRICAN JOURNALS ONLINE (AJOL) · Journals · Advanced Search ... stirred tank reactor (CSTR) and the small and large intestines as plug flow reactor (PFR) ... from the two equations are used for the reactor sizing of the modeled reactors.

  12. Reactor physics aspects of CANDU reactors

    International Nuclear Information System (INIS)

    Critoph, E.

    1980-01-01

    These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

  13. Molten salt breeder reactor

    International Nuclear Information System (INIS)

    1977-01-01

    MSBR Study Group formed in October 1974 has studied molten salt breeder reactor and its various aspects. Usage of a molten salt fuel, extremely interesting as reactor chemistry, is a great feature to MSBR; there is no need for separate fuel making, reprocessing, waste storage facilities. The group studied the following, and these results are presented: molten salt technology, molten salt fuel chemistry and reprocessing, reactor characteristics, economy, reactor structural materials, etc. (Mori, K.)

  14. Zero energy reactor 'RB'

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, D; Takac, S; Markovic, H; Raisic, N; Zdravkovic, Z; Radanovic, Lj [Boris Kidric Institute of Nuclear Sciences, Vinca, Beograd (Yugoslavia)

    1959-03-15

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  15. Reactor utilization, Annex A

    International Nuclear Information System (INIS)

    Martinc, R.; Stanic, A.

    1984-01-01

    Reactor was operated until August 1984 due to prohibition issued by the Ministry since the reactor does not have the emergency cooling system nor special filters in the ventilation system yet. This means that the operation plan was fulfilled by 69%. This annex includes detailed tables containing data about utilization of reactor experimental channels, irradiated samples, as well as interruptions of operation. Detailed data about reactor power during this period are shown as well

  16. PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

    Masood, Z.

    2016-01-01

    The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

  17. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  18. The fast reactor

    International Nuclear Information System (INIS)

    1980-02-01

    The subject is discussed as follows: brief description of fast reactors; advantage in conserving uranium resources; experience, in UK and elsewhere, in fast reactor design, construction and operation; safety; production of plutonium, security aspects; consideration of future UK fast reactor programme. (U.K.)

  19. Mirror fusion reactor design

    International Nuclear Information System (INIS)

    Neef, W.S. Jr.; Carlson, G.A.

    1979-01-01

    Recent conceptual reactor designs based on mirror confinement are described. Four components of mirror reactors for which materials considerations and structural mechanics analysis must play an important role in successful design are discussed. The reactor components are: (a) first-wall and thermal conversion blanket, (b) superconducting magnets and their force restraining structure, (c) neutral beam injectors, and (d) plasma direct energy converters

  20. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  1. Rotating reactors : a review

    NARCIS (Netherlands)

    Visscher, F.; Schaaf, van der J.; Nijhuis, T.A.; Schouten, J.C.

    2013-01-01

    This review-perspective paper describes the current state-of-the-art in the field of rotating reactors. The paper has a focus on rotating reactor technology with applications at lab scale, pilot scale and industrial scale. Rotating reactors are classified and discussed according to their geometry:

  2. Refuelling nuclear reactors

    International Nuclear Information System (INIS)

    Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

    1981-01-01

    An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

  3. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  4. Ulysse, mentor reactor

    International Nuclear Information System (INIS)

    Bouquin, B.; Rio, I.; Safieh, J.

    1997-01-01

    On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

  5. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1981-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drivemechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displayer rods through the reactor vessel

  6. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1982-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drive mechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displacer rods through the reactor vessel. (author)

  7. Development of fuel cycle technology for molten-salt reactor systems

    International Nuclear Information System (INIS)

    Uhlir, J.

    2006-01-01

    Full text: Full text: The Molten-Salt Reactor (MSR) represents one of promising advanced reactor type assigned to the GEN IV reactor systems. It can be operated either as thorium breeder within the Th -133U fuel cycle or as actinide transmuter incinerating transuranium fuel. Essentially the main advantage of MSR comes out from the prerequisite, that this reactor type should be directly connected with the 'on-line' reprocessing of circulating liquid (molten-salt) fuel. This principle should allow very effective extraction of freshly constituted fissile material (233U). Besides, the on-line fuel salt clean up is necessary within a long run to keep the reactor in operation. As a matter of principle, it permits to clear away typical reactor poisons like xenon, krypton, lanthanides etc. and possibly also other products of burned plutonium and transmuted minor actinides. The fuel salt clean up technology should be linked with the fresh MSR fuel processing to continuously refill the new fuel (thorium or transuranics) into the reactor system. On the other hand, the technologies of fresh transuranium molten-salt fuel processing from the current LWR spent fuel and of the on-line reprocessing of MSR fuel represent two killing points of the whole MSR technology, which have to be successfully solved before MSR deployment in the future. There are three main pyrochemical partitioning techniques proposed for processing and/or reprocessing of MSR fuel: Fluoride volatilization processes, Molten salt / liquid metal extraction processes and Electrochemical separation processes. Two of them - Fluoride Volatility Method and Electrochemical separation process from fluoride media are under development in the Nuclear Research Institute Rez pic. R and D in the field of Fluoride Volatility Method is concentrated to the development and verification of experimental semi-pilot technology for LWR spent fuel reprocessing, which may result in a product the form and composition of which might be

  8. Neutron behavior, reactor control, and reactor heat transfer. Volume four

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant)

  9. Reactor as furnace and reactor as lamp

    International Nuclear Information System (INIS)

    Goldanskii, V.I.

    1992-01-01

    There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

  10. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  11. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

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

  12. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1981-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  13. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  14. Mayor frecuencia de giardiosis en niños con raquitismo comparada con niños sanos de la población de Suárez, Cauca, Colombia

    OpenAIRE

    Oscar L. Sierra; Lidia N. Peñalosa; Yolanda Alarcón

    1998-01-01

    Se examinaron huevos, quistes y trofozoítos de parásitos intestinales en heces de 332 niños sanos y 70 niños con raquitismo descrito como un trastorno heredado debido a malabsorción de calcio por resistencia a la vitamina D en Suárez, departamento del Cauca. La frecuencia total de parasitosis fue de 65,9% y la de poliparasitismo de 10,9%. Se encontraron frecuencias elevadas de giardiosis y poliparasitismo en niños con raquitismo (17,l y 18,6%) comparado con niños sanos (9,O y 9,3%) y dichas d...

  15. Restauración de arte contemporáneo y conservación preventiva. Un caso práctico: La Fundación Antonio Pérez de Cuenca

    OpenAIRE

    Díaz Martínez, Marta María

    2016-01-01

    El primer bloque de la tesis hace un repaso por los criterios que se tienen en cuenta a la hora de restaurar una obra de arte contemporáneo y las técnicas más empleadas. El segundo aborda el tema de la conservación preventiva y los factores a considerar en la conservación de cualquier colección. Y el tercer bloque consiste en una aplicación práctica de los anteriores, con el diseño de un plan de conservación preventiva de la Fundación Antonio Pérez, de Cuenca y los proyectos de restaura...

  16. O feminicídio de juárez: alterações económicas, narrativas sociais e discursos coloniais na fronteira dos EUA e MÉXICO

    OpenAIRE

    Lobo, Patrícia Alves

    2016-01-01

    Desde maio de 1993 que, em Ciudad Juárez, centenas de mulheres foram assassinadas, violadas, torturadas e mutiladas e milhares continuam desaparecidas. Neste artigo, começa-se por evidenciar a interligação entre as alterações económicas geradas pelo Acordo de Comércio Livre da América do Norte e a destabilização dos papéis de género no norte do México, o que originou novos focos de violência contra as mulheres. Em segundo lugar, expõe-se a dialética que está subjacente aos modelos patriarcais...

  17. La relación entre el miedo a la violación y el sexismo benévolo en una muestra de mujeres de Ciudad Juárez (México)

    OpenAIRE

    Espinoza Ornelas, Roxana; Moya, Miguel; Willis, Guillermo B.

    2015-01-01

    En este artículo se estudió la relación entre el miedo a la violación y el sexismo benévolo en 2 muestras de mujeres de Ciudad Juárez (México). Usando un diseño correlacional, en el Estudio 1 (N = 225 mujeres) se encontró que cuanto mayor es el miedo a la violación, mayores puntuaciones se obtienen en sexismo benévolo, pero no en sexismo hostil. En el Estudio 2 (N = 188 mujeres) se manipuló experimentalmente el miedo considerando 3 condiciones: miedo a la violación, miedo al crimen y condició...

  18. Suárez Hugo Jose, Coord., El sentido y el método. Sociología de la cultura y análisis de contenido

    Directory of Open Access Journals (Sweden)

    Julie Hermesse

    2010-10-01

    Full Text Available L’ouvrage coordonné par Hugo José Suárez rencontrera les attentes de tout chercheur désireux d’approfondir ou de se familiariser avec la sociologie de la culture et l’analyse structurale de contenu telles qu’elles ont été développées à Louvain à partir des années 1970. Il relève le défi de présenter pédagogiquement le programme de base de l’analyse structurale louvaniste : extraire par un processus opératoire concret des systèmes de sens (modèles culturels qui orientent le comportement des s...

  19. Estrategia audiovisual de comunicación política en la Selva en Chiapas: la experiencia de los comunicadores tseltales Mariano Estrada y Arturo Pérez

    Directory of Open Access Journals (Sweden)

    Delmar Ulises Méndez Gómez

    2018-01-01

    Full Text Available En México, la formación de comunicadores que desarrollan su quehacer en las comunidades y se vinculan con los pueblos originarios a los que pertenecen, ha sido importante en las últimas décadas porque ha permitido la ampliación y circulación de la voz de quienes han sido invisibilizados y negados, así como el ejercicio de su derecho a la comunicación e información. En este texto se examina el trabajo audiovisual de los comunicadores tseltales Mariano Estrada y Arturo Pérez, originarios de la región Selva de Chiapas, su proceso de formación, el sentido político de su trabajo y sus estrategias de comunicación.

  20. The fast breeder reactor

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  1. One piece reactor removal

    International Nuclear Information System (INIS)

    Chia, Wei-Min; Wang, Song-Feng

    1993-01-01

    The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

  2. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  3. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  4. The Maple reactor project

    International Nuclear Information System (INIS)

    Malkoske, G.R.; Labrie, J.-P.

    2003-01-01

    MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

  5. Fission reactors and materials

    International Nuclear Information System (INIS)

    Frost, B.R.T.

    1981-12-01

    The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions

  6. Validation of thermal hydraulic computer codes for advanced light water reactor

    International Nuclear Information System (INIS)

    Macek, J.

    2001-01-01

    The Czech Republic operates 4 WWER-440 units, two WWER-1000 units are being finalised (one of them is undergoing commissioning). Thermal-hydraulics Department of the Nuclear Research Institute Rez performs accident analyses for these plants using a number of computer codes. To model the primary and secondary circuits behaviour the system codes ATHLET, CATHARE, RELAP, TRAC are applied. Containment and pressure-suppressure system are modelled with RALOC and MELCOR codes, the reactor power calculations (point and space-neutron kinetics) are made with DYN3D, NESTLE and CDF codes (FLUENT, TRIO) are used for some specific problems. An integral part of the current Czech project 'New Energy Sources' is selection of a new nuclear source. Within this and the preceding projects financed by the Czech Ministry of Industry and Trade and the EU PHARE, the Department carries and has carried out the systematic validation of thermal-hydraulic and reactor physics computer codes applying data obtained on several experimental facilities as well as the real operational data. The paper provides a concise information on these activities of the NRI and its Thermal-hydraulics Department. A detailed example of the system code validation and the consequent utilisation of the results for a real NPP purposes is included. (author)

  7. Un modelo monárquico legislativo y jurídico para la Orden de Santiago : el maestre Lorenzo Suárez de Figueroa y los establecimientos de Uclés (1395 y Mérida (1403

    Directory of Open Access Journals (Sweden)

    Gonzalo Carrasco García

    2011-01-01

    Full Text Available El maestre de Santiago, Lorenzo Suárez de Figueroa, inauguró un nuevo modelo de establecimientos donde aunaba dos tipos de disposiciones: el espiritual y temporal para los freires, y el de ordenanzas y leyes para sus vasallos. Su aprobación tuvo lugar en el hasta ahora poco conocido capítulo general de Uclés de 1395 y en el capítulo de Mérida de 1403 y están inspirados principalmente en la legislación de las Cortes de Juan I y Enrique III. Este estudio demuestra como el maestre, afecto a la causa del autoritarismo regio, asumió algunas de sus características para su propio proyecto de monarquismo maestral dentro de la Orden. Como apéndice documental se incluye la edición de los establecimientos de Mérida de 1403 y una reconstrucción de los de Uclés de 1395.Lorenzo Suárez de Figueroa, Master of the Order of Santiago, launched a new model of statutes combining two types of provisions: spiritual and temporal measures for the brethren, and laws and ordinances for his vassals. Their approval took place in the previously ill-known General Chapter of Uclés in 1395 and in the Mérida Chapter of 1403 and were essentially inspired by laws enacted in the Cortes of Juan I and Enrique III. This study shows how the Master, an advocate of the royal authoritarian cause, was able to include some of these characteristics in his own project of monarchical mastership in the Order. The edition of the Mérida Statutes of 1403 is included in the appendix along with a reconstruction of those approved in Uclés in 1395.

  8. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

    2008-10-15

    This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

  9. Odiseo a través de la parodia. Desmitificación e ironía de una Ítaca nostálgica en Prometeo de Pérez de Ayala y ¿Por qué corres, Ulises? de Gala. – Odysseus through parody. Demythologization and irony of a nostalgic Ithaca in Prometeo by Pérez de Ayala and ¿Por qué corres, Ulises? by Gala

    Directory of Open Access Journals (Sweden)

    López López, Carmen María

    2014-12-01

    Full Text Available The aim of this article is to propose a critical and comparative study beginning from the epic model variations on the Spanish Literature from the twentieth century: Prometeo by Ramón Pérez de Ayala and ¿Por qué corres, Ulises? by Antonio Gala. To this purpose, a historic perspective will be designed, according to some Homeric episodes inside of the Odisea: the stay of the hero with Nausicaa in the phaeacians’ land, with the nymph Calypso in Ogygia, with the magician Circe in the Eea’s island, in the Lotofagi’s land, the Nekuia and the re-encounter with Penelope. To conclude, this article pretends to analyze the sense of the laugh from the tradition, to deal with the reinterpretation of the myth as a parody and an irony regarding the Homeric narration.

  10. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Carlos Ruben Calabrese

    1999-01-01

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  11. Siting of research reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of this document is to develop criteria for siting and the site-related design basis for research reactors. The concepts presented in this document are intended as recommendations for new reactors and are not suggested for backfitting purposes for facilities already in existence. In siting research reactors serious consideration is given to minimizing the effects of the site on the reactor and the reactor on the site and the potential impact of the reactor on the environment. In this document guidance is first provided on the evaluation of the radiological impact of the installation under normal reactor operation and accident conditions. A classification of research reactors in groups is then proposed, together with a different approach for each group, to take into account the relevant safety problems associated with facilities of different characteristics. Guidance is also provided for both extreme natural events and for man-induced external events which could affect the safe operation of the reactor. Extreme natural events include earthquakes, flooding for river or coastal sites and extreme meteorological phenomena. The feasibility of emergency planning is finally considered for each group of reactors

  12. Reactor core for FBR type reactor

    International Nuclear Information System (INIS)

    Fujita, Tomoko; Watanabe, Hisao; Kasai, Shigeo; Yokoyama, Tsugio; Matsumoto, Hiroshi.

    1996-01-01

    In a gas-sealed assembly for a FBR type reactor, two or more kinds of assemblies having different eigen frequency and a structure for suppressing oscillation of liquid surface are disposed in a reactor core. Coolant introduction channels for introducing coolants from inside and outside are disposed in the inside of structural members of an upper shielding member to form a shielding member-cooling structure in the reactor core. A structure for promoting heat conduction between a sealed gas in the assembly and coolants at the inner side or the outside of the assembly is disposed in the reactor core. A material which generates heat by neutron irradiation is disposed in the assembly to heat the sealed gases positively by radiation heat from the heat generation member also upon occurrence of power elevation-type event to cause temperature expansion. Namely, the coolants flown out from or into the gas sealed-assemblies cause differential fluctuation on the liquid surface, and the change of the capacity of a gas region is also different on every gas-sealed assemblies thereby enabling to suppress fluctuation of the reactor power. Pressure loss is increased by a baffle plate or the like to lower the liquid surface of the sodium coolants or decrease the elevating speed thereof thereby suppressing fluctuation of the reactor power. (N.H.)

  13. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  14. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  15. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

  16. Multipurpose research reactors

    International Nuclear Information System (INIS)

    1988-01-01

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  17. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  18. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

  19. Upgradation of Apsara reactor

    International Nuclear Information System (INIS)

    Mammen, S.; Mukherjee, P.; Bhatnagar, A.; Sasidharan, K.; Raina, V.K.

    2009-01-01

    Apsara is a 1 MW swimming pool type research reactor using high enriched uranium as fuel with light water as coolant and moderator. The reactor is in operation for more than five decades and has been extensively used for basic research, radioisotope production, neutron radiography, detector testing, shielding experiments etc. In view of its long service period, it is planned to carry out refurbishment of the reactor to extend its useful life. During refurbishment, it is also planned to upgrade the reactor to a 2 MW reactor to improve its utilization and to upgrade the structure, system and components in line with the current safety standards. This paper gives a brief account of the design features and safety aspects of the upgraded Apsara reactor. (author)

  20. Caracterización de las comunidades de acridios (Orthoptera: Acridoidea del partido de Benito Juárez, sudeste de la provincia de Buenos Aires, Argentina Grasshopper (Orthoptera: Acridoidea community structure in Benito Juárez county, in outhern Buenos Aires province, Argentina

    Directory of Open Access Journals (Sweden)

    María Laura de Wysiecki

    2004-12-01

    Full Text Available Se analizó la riqueza, densidad, constancia y distribución de especies de acridios, en distintas comunidades vegetales (1997-2002 en el partido de Benito Juárez, sudeste de la provincia de Buenos Aires. Las comunidades vegetales se categorizaron en pastizales nativos, comunidades halófilas, pasturas sin disturbio, pasturas con moderado disturbio y pasturas con alto disturbio. En total se registraron 23 especies de acridios. Los melanoplinos dominaron en casi todas las comunidades vegetales, excepto en las halófilas que se caracterizaron por la presencia de un acridino, Covasacris pallidinota (Bruner. La riqueza de especies promedio por sitio por año, varió entre 2,10 ± 0,60 especies en las pasturas con moderado disturbio y 6,20 ± 0,58 especies en las comunidades halófilas. La riqueza de especies acumulada fue de 17 en los pastizales nativos, 14 en las comunidades halófilas, 19 en las pasturas sin disturbio, 18 en las pasturas con moderado disturbio y 14 en las pasturas con alto disturbio. La densidad promedio de acridios fue máxima en el 2001 y 2002. Dichroplus pratensis Bruner y Dichroplus elongatus Giglio-Tos dominaron en los pastizales nativos y en las pasturas con alto disturbio, C. pallidinota en las comunidades halófilas, D. elongatus y Scotussa lemniscata (Stål en las pasturas sin disturbio y en las pasturas con moderado disturbio. La estructura taxonómica de las comunidades de acridios fue constante en los pastizales nativos, las comunidades halófilas y las pasturas. Hubo pocas especies de amplia distribución e intermedias y las raras fueron las más numerosas. De las 23 especies registradas en todos los sitios, D. elongatus fue la única de amplia distribución. Históricamente, para la zona de estudio, Dichroplus maculipennis (Blanch fue señalada como la especie dominante. Sin embargo, nuestros resultados sugieren que en la actualidad la especie dominante es D. elongatus. Si bien resulta imposible conocer las causas

  1. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1980-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

  2. Spectral shift reactor control method

    International Nuclear Information System (INIS)

    Impink, A.J. Jr.

    1981-01-01

    A method of operating a nuclear reactor having a core and coolant displacer elements arranged in the core wherein is established a reator coolant temperature set point at which it is desired to operate said reactor and first reactor coolant temperature band limits are provided within which said set point is located and it is desired to operate said reactor charactrized in that said reactor coolant displacer elements are moved relative to the reactor core for adjusting the volume of reactor coolant in said core as said reactor coolant temperature approaches said first band limits thereby to maintain said reactor coolant temperature near said set point and within said first band limits

  3. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1985-08-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

  4. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

    1982-09-01

    Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  5. Power reactors operational diagnosis

    International Nuclear Information System (INIS)

    Dach, K.; Pecinka, L.

    1976-01-01

    The definition of reactor operational diagnostics is presented and the fundamental trends of research are determined. The possible sources of power reactor malfunctions, the methods of defect detection, the data evaluation and the analysis of the results are discussed in detail. In view of scarcity of a theoretical basis and of insufficient in-core instrumentation, operational diagnostics cannot be as yet incorporated in a computer-aided reactor control system. (author)

  6. Fast reactors worldwide

    International Nuclear Information System (INIS)

    Hall, R.S.; Vignon, D.

    1985-01-01

    The paper concerns the evolution of fast reactors over the past 30 years, and their present status. Fast reactor development in different countries is described, and the present position, with emphasis on cost reduction and collaboration, is examined. The French development of the fast breeder type reactor is reviewed, and includes: the acquisition of technical skills, the search for competitive costs and the spx2 project, and more advanced designs. Future prospects are also discussed. (U.K.)

  7. Pressurised water reactor operation

    International Nuclear Information System (INIS)

    Birnie, S.; Lamonby, J.K.

    1987-01-01

    The operation of a pressurized water reactor (PWR) is described with respect to the procedure for a unit start-up. The systems details and numerical data are for a four loop PWR station of the design proposed for Sizewell-'B', United Kingdom. A description is given of: the initial conditions, filling the reactor coolant system (RCS), heat-up and pressurisation of the RCS, secondary system preparations, reactor start-up, and reactivity control at power. (UK)

  8. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  9. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  10. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

  11. The Dragon reactor experiment

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The concept on which the Dragon Reactor Experiment was based was evolved at the Atomic Energy Research Establishment at Harwell in 1956, and in February of that year a High Temperature Gas- cooled Reactor Project Group was set up to study the feasibility of a helium-cooled reactor with a graphite or beryllium moderator, and with the emphasis on the thorium fuel cycle [af

  12. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.

    1999-01-01

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  13. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  14. Integral fast reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1989-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics

  15. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  16. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1988-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  17. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  18. HOMOGENEOUS NUCLEAR POWER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  19. Australian research reactor studies

    International Nuclear Information System (INIS)

    McCulloch, D.B.

    1978-01-01

    The Australian AEC has two research reactors at the Lucas Heights Research Establishment, a 10 HW DIDO class materials testing reactor, HIFAR, and a smaller 100kW reactor MOATA, which was recently upgraded from 10kW power level. Because of the HIFAR being some 20 years old, major renewal and repair programmes are necessary to keep it operational. To enable meeting projected increases in demand for radioisotopes, plans for a new reactor to replace the HIFAR have been made and the design criteria are described in the paper. (author)

  20. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1978-01-01

    We have carried out conceptual design studies of fusion reactors based on the three current mirror confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. Tandem mirror designs include a commercial 1000 MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single cell pilot plant

  1. Reactor feedwater system

    International Nuclear Information System (INIS)

    Hikabe, Katsumi.

    1978-01-01

    Purpose: In order to prevent thermal stresses of a core of PWR type reactor, described has been a method for feeding heated recirculating water to the core in the case of the reactor start-up or shut-down. Constitution: A recirculating water is degassed, cleaned up and heated in the steam condensers, and then feeds the water to the reactor, characterized in that heaters are provided in the bypasses of the turbine, so that heated water is constantly supplied to the reactor. (Nakamura, S.)

  2. Remote Reactor Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-10-21

    The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

  3. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2002-01-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

  4. Trench reactor: an overview

    International Nuclear Information System (INIS)

    Spinrad, B.I.; Rohach, A.F.; Razzaque, M.M.; Sankoorikal, J.T.; Schmidt, R.S.; Lofshult, J.; Ramin, T.; Sokmen, N.; Lin, L.C.

    1988-01-01

    Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report

  5. New reactor concepts

    International Nuclear Information System (INIS)

    Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A.

    1998-11-01

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

  6. Advanced CANDU reactors

    International Nuclear Information System (INIS)

    Dunn, J.T.; Finlay, R.B.; Olmstead, R.A.

    1988-12-01

    AECL has undertaken the design and development of a series of advanced CANDU reactors in the 700-1150 MW(e) size range. These advanced reactor designs are the product of ongoing generic research and development programs on CANDU technology and design studies for advanced CANDU reactors. The prime objective is to create a series of advanced CANDU reactors which are cost competitive with coal-fired plants in the market for large electricity generating stations. Specific plant designs in the advanced CANDU series will be ready for project commitment in the early 1990s and will be capable of further development to remain competitive well into the next century

  7. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Doshi, P.K.; George, R.A.; Dollard, W.J.

    1982-01-01

    A mechanical spectral shift arrangement for controlling a nuclear reactor includes a plurality of reactor coolant displacer members which are inserted into a reactor core at the beginning of the core life to reduce the volume of reactor coolant-moderator in the core at start-up. However, as the reactivity of the core declines with fuel depletion, selected displacer members are withdrawn from the core at selected time intervals to increase core moderation at a time when fuel reactivity is declining. (author)

  8. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  9. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

  10. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  11. Multi purpose research reactor

    International Nuclear Information System (INIS)

    Raina, V.K.; Sasidharan, K.; Sengupta, Samiran; Singh, Tej

    2006-01-01

    At present Dhruva and Cirus reactors provide the majority of research reactor based facilities to cater to the various needs of a vast pool of researchers in the field of material sciences, physics, chemistry, bio sciences, research and development work for nuclear power plants and production of radio isotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 20 MWt multi purpose research reactor is being designed. This paper describes some of the design features and safety aspects of this reactor

  12. FBR type reactors

    International Nuclear Information System (INIS)

    Suzuoki, Akira; Yamakawa, Masanori.

    1985-01-01

    Purpose: To enable safety and reliable after-heat removal from a reactor core. Constitution: During ordinary operation of a FBR type reactor, sodium coolants heated to a high temperature in a reactor core are exhausted therefrom, collide against the reactor core upper mechanisms to radially change the flowing direction and then enter between each of the guide vanes. In the case if a main recycling pump is failed and stopped during reactor operation and the recycling force is eliminated, the swirling stream of sodium that has been resulted by the flow guide mechanism during normal reactor operation is continuously maintained within a plenum at a high temperature. Accordingly, the sodium recycling force in the coolant flow channels within the reactor vessel can surely be maintained for a long period of time due to the centrifugal force of the sodium swirling stream. In this way, since the reactor core recycling flow rate can be secured even after the stopping of the main recycling pump, after-heat from the reactor core can safely and surely be removed. (Seki, T.)

  13. FBR type reactor

    International Nuclear Information System (INIS)

    Hayase, Tamotsu.

    1991-01-01

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

  14. Farewell to a reactor

    International Nuclear Information System (INIS)

    Skanborg, P.

    1976-01-01

    Denmark's second reactor, DR 2, whose first criticality took place the night of 18/19 December 1958 was shut down for the last time on 31 October 1975. It was a light-water moderrated and cooled reactor of swimming-pool type with a thermal power of 5 MW, using 90% enriched uranium. The operation is described. The reactor and auxiliary equipment are now being put 'in store' - all fuel elements sent for reprocessing, the reactor tank and cooling circuits emptied, and a lead shielding placed over the tank opening. The rest of the equipment will remain in place. (B.P.)

  15. Indian advanced nuclear reactors

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2005-01-01

    For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

  16. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

    2000-01-01

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  17. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  18. FFTF reactor assembly system technology

    International Nuclear Information System (INIS)

    Mangelsdorf, T.A.

    1975-01-01

    An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs

  19. Reactor building for a nuclear reactor

    International Nuclear Information System (INIS)

    Haidlen, F.

    1976-01-01

    The invention concerns the improvement of the design of a liner, supported by a latticed steel girder structure and destined for guaranteeing a gastight closure for the plant compartments in the reactor building of a pressurized water reactor. It is intended to provide the steel girder structure on their top side with grates, being suited for walking upon, and to hang on their lower side diaphragms in modular construction as a liner. At the edges they may be sealed with bellows in order to avoid thermal stresses. The steel girder structure may at the same time serve as supports for parts of the steam pipe. (RW) [de

  20. Revitalization of reactor usage through reactor sharing

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1986-01-01

    The purpose of this work was to renew interest in using the University Florida Training Reactor (UFTR) for educational and training purposes outside the Nuclear Engineering Sciences (NES) and Environmental Engineering Sciences (EES) Departments at the University of Florida and for research by others outside the NES Department. The availability of the UFTR made possible through a US Department of Energy (DOE) Reactor Sharing Grant provided the mechanism to pursue generation of renewed interest at all levels both within the University of Florida and from other educational and corporate institutions

  1. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    An improvement is proposed concerning the easier disengagement of the coupling at the reactor coolant pump for a nuclear reactor transporting a pressurized coolant. According to the invention the disengaging coupling consists of two parts separated by screws. At least one of the screws contains a propellent charge ananged within a bore and provided with a speed-dependent ignition device in such a way that by separation of the screws at overspeeds the coupling is disengaged. The sub-claims are concerned with the kind of ignition ot the propellent charge. (UWI) [de

  2. The fusion reactor

    International Nuclear Information System (INIS)

    Brennan, M.H.

    1974-01-01

    Basic principles of the fusion reactor are outlined. Plasma heating and confinement schemes are described. These confinement systems include the linear Z pinch, magnetic mirrors and Tokamaks. A fusion reactor is described and a discussion is given of its environmental impact and its fuel situation. (R.L.)

  3. Molten salt reactor concept

    International Nuclear Information System (INIS)

    Sood, D.D.

    1980-01-01

    Molten salt reactor is an advanced breeder concept which is suited for the utilization of thorium for nuclear power production. This reactor is based on the use of solutions of uranium or plutonium fluorides in LiF-BeF 2 -ThF 4 as fuel. Unlike the conventional reactors, no external coolant is used in the reactor core and the fuel salt itself is circulated through heat exchangers to transfer the fission produced heat to a secondary salt (NaF-NaBF 4 ) for steam generation. A part of the fuel stream is continuously processed to isolate 233 Pa, so that it can decay to fissile 233 U without getting converted to 234 Pa, and for the removal of neutron absorbing fission products. This on-line processing scheme makes this reactor concept to achieve a breeding ratio of 1.07 which is the highest for any thermal breeder reactor. Experimental studies at the Bhabha Atomic Research Centre, Bombay, have established the use of plutonium as fuel for this reactor. This molten salt reactor concept is described and the work conducted at the Bhabha Atomic Research Centre is summarised. (auth.)

  4. The heavy water reactors

    International Nuclear Information System (INIS)

    Brudermueller, G.

    1976-01-01

    This is a survey of the development so far of this reactor line which is in operation all over the world in various types (e.g. BHWR, PHWR). MZFR and the CANDU-type reactors are discussed in more detail. (UA) [de

  5. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1983-01-01

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

  6. Osiris reactor descriptive report

    International Nuclear Information System (INIS)

    1976-03-01

    OSIRIS is a swimming pool reactor of 70 MW thermal power. Its main purpose is the irradiation of reactor materials in high neutron flux. A description is given of the air conditioning, ventilation, and radioactive gas removal system. (R.L.)

  7. FBR type reactor core

    International Nuclear Information System (INIS)

    Tamiya, Tadashi; Kawashima, Katsuyuki; Fujimura, Koji; Murakami, Tomoko.

    1995-01-01

    Neutron reflectors are disposed at the periphery of a reactor core fuel region and a blanket region, and a neutron shielding region is disposed at the periphery of them. The neutron reflector has a hollow duct structure having a sealed upper portion, a lower portion opened to cooling water, in which a gas and coolants separately sealed in the inside thereof. A driving pressure of a primary recycling pump is lowered upon reduction of coolant flow rate, then the liquid level of coolants in the neutron reflector is lowered due to imbalance between the driving pressure and a gas pressure, so that coolants having an effect as a reflector are eliminated from the outer circumference of the reactor core. Therefore, the amount of neutrons leaking from the reactor core is increased, and negative reactivity is charged to the reactor core. The negative reactivity of the neutron reflector is made greater than a power compensation reactivity. Since this enables reactor scram by using an inherent performance of the reactor core, the reactor core safety of an LMFBR-type reactor can be improved. (I.N.)

  8. Mirror hybrid reactor studies

    International Nuclear Information System (INIS)

    Bender, D.J.

    1978-01-01

    The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed

  9. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    2000-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

  10. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Lineberry, M.J.

    1990-01-01

    Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 5 refs., 3 figs

  11. Gas-cooled reactors

    International Nuclear Information System (INIS)

    Vakilian, M.

    1977-05-01

    The present study is the second part of a general survey of Gas Cooled Reactors (GCRs). In this part, the course of development, overall performance and present development status of High Temperature Gas Cooled Reactors (HTCRs) and advances of HTGR systems are reviewed. (author)

  12. A nuclear power reactor

    International Nuclear Information System (INIS)

    Borrman, B.E.; Broden, P.; Lundin, N.

    1979-12-01

    The invention consists of shock absorbing support beams fastened to the underside of the reactor tank lid of a BWR type reactor, whose purpose is to provide support to the steam separator and dryer unit against accelerations due to earthquakes, without causing undue thermal stresses in the unit due to differential expansion. (J.I.W.)

  13. International thermal reactor development

    International Nuclear Information System (INIS)

    Zebroski, E.L.

    1977-01-01

    The worldwide development of nuclear power plants is reviewed. Charts are presented which show the commitment to light-water reactor capacity construction with breakdown by region and country. Additional charts show the major nuclear research centers which have substantial scope in light water reactor development and extensive international activities

  14. Thermal reactor strategy

    International Nuclear Information System (INIS)

    1981-01-01

    This statement sets down briefly the CEGB's views on the requirement for nuclear power and outlines current progress in the implementation of the CEGB's thermal reactor strategy. The programme is traced historically, together with statements of Government policy. The place of Magnox, AGR, SGHWR, PWR and fast breeder reactors is discussed. Advantages and problems associated with the various types are outlined. (U.K.)

  15. Supercritical Water Reactors

    International Nuclear Information System (INIS)

    Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

    2014-01-01

    The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

  16. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2001-01-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  17. Fusion reactors - types - problems

    International Nuclear Information System (INIS)

    Schmitter, K.H.

    1979-07-01

    A short account is given of the principles of fusion reactions and of the expected advantages of fusion reactors. Descriptions are presented of various Tokamak experimental devices being developed in a number of countries and of some mirror machines. The technical obstacles to be overcome before a fusion reactor could be self-supporting are discussed. (U.K.)

  18. Reactor cost driving items

    International Nuclear Information System (INIS)

    Spears, W.R.

    1987-01-01

    Assuming that the design solutions presently perceived for NET can be extrapolated for use in a power reactor, and using costing experience with present day fusion experiments and with fission power plants, the major components of the cost of a tokamak fusion power reactor are described. The analysis shows the emphasis worth placing on various areas of plant design to reduce costs

  19. Tank type reactor

    International Nuclear Information System (INIS)

    Otsuka, Fumio.

    1989-01-01

    The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

  20. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  1. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-06

    We needed to find a space reactor concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled reactors coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.

  2. Reactor dynamics calculations

    International Nuclear Information System (INIS)

    Devooght, J.; Lefvert, T.; Stankiewiez, J.

    1981-01-01

    This chapter deals with the work done in reactor dynamics within the Coordinated Research Program on Transport Theory and Advanced Reactor Calculations by three groups in Belgium, Poland, Sweden and Italy. Discretization methods in diffusion theory, collision probability methods in time-dependent neutron transport and singular perturbation method are represented in this paper

  3. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  4. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Lyon, J.F.; Carreras, B.A.; Lynch, V.E.; Tolliver, J.S.; Sviatoslavsky, I.N.

    1988-05-01

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R 0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R 0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  5. Iris reactor conceptual design

    International Nuclear Information System (INIS)

    Carelli, M.D.; Conway, L.E.; Petrovic, B.; Paramonov, D.V.; Galvin, M.; Todreas, N.E.; Lombardi, C.V.; Maldari, F.; Ricotti, M.E.; Cinotti, L.

    2001-01-01

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  6. The secure heating reactor

    International Nuclear Information System (INIS)

    Pind, C.

    1987-01-01

    The SECURE heating reactor was designed by ASEA-ATOM as a realistic alternative for district heating in urban areas and for supplying heat to process industries. SECURE has unique safety characteristics, that are based on fundamental laws of physics. The safety does not depend on active components or operator intervention for shutdown and cooling of the reactor. The inherent safety characteristics of the plant cannot be affected by operator errors. Due to its very low environment impact, it can be sited close to heat consumers. The SECURE heating reactor has been shown to be competitive in comparison with other alternatives for heating Helsinki and Seoul. The SECURE heating reactor forms a basis for the power-producing SECURE-P reactor known as PIUS (Process Inherent Ultimate Safety), which is based on the same inherent safety principles. The thermohydraulic function and transient response have been demonstrated in a large electrically heated loop at the ASEA-ATOM laboratories

  7. Nuclear reactor design

    CERN Document Server

    2014-01-01

    This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

  8. Mirror reactor surface study

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, A. L.; Damm, C. C.; Futch, A. H.; Hiskes, J. R.; Meisenheimer, R. G.; Moir, R. W.; Simonen, T. C.; Stallard, B. W.; Taylor, C. E.

    1976-09-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included.

  9. Reactor control device

    International Nuclear Information System (INIS)

    Fukami, Haruo; Morimoto, Yoshinori.

    1981-01-01

    Purpose: To operate a reactor always with safety operation while eliminating the danger of tripping. Constitution: In a reactor control device adapted to detect the process variants of a reactor, control a control rod drive controlling system based on the detected signal to thereby control the driving the control rods, control the reactor power and control the electric power generated from an electric generator by the output from the reactor, detection means is provided for the detection of the electric power from said electric generator, and a compensation device is provided for outputting control rod driving compensation signals to the control rod driving controlling system in accordance with the amount of variation in the detected value. (Seki, T.)

  10. Reactor feedwater device

    International Nuclear Information System (INIS)

    Igarashi, Noboru.

    1986-01-01

    Purpose: To suppress soluble radioactive corrosion products in a feedwater device. Method: In a light water cooled nuclear reactor, an iron injection system is connected to feedwater pipeways and the iron concentration in the feedwater or reactor coolant is adjusted between twice and ten times of the nickel concentration. When the nickel/iron ratio in the reactor coolant or feedwater goes nearer to 1/2, iron ions are injected together with iron particles to the reactor coolant to suppress the leaching of stainless steels, decrease the nickel in water and increase the iron concentration. As a result, it is possible to suppress the intrusion of nickel as one of parent nuclide of radioactive nuclides. Further, since the iron particles intruded into the reactor constitute nuclei for capturing the radioactive nuclides to reduce the soluble radioactive corrosion products, the radioactive nuclides deposited uniformly to the inside of the pipeways in each of the coolant circuits can be reduced. (Kawakami, Y.)

  11. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    Veeraraghaven, N.

    1990-01-01

    DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 10 14 n/cm 2 /sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

  12. Reactor power control device

    International Nuclear Information System (INIS)

    Kobayashi, Akira.

    1980-01-01

    Purpose: To prevent misoperation in a control system for the adjustment of core coolant flow rate, and the increase in the neutron flux density caused from the misoperation in BWR type reactors. Constitution: In a reactor power control system adapted to control the reactor power by the adjustment of core flow rate, average neutron flux signals of a reactor core, entire core flow rate signals and operation state signals for coolant recycling system are inputted to a microcomputer. The outputs from the computer are sent to a recycling MG set speed controller to control the reactor core flow rate. The computer calculates the change ratio with time in the average neutron flux signals, correlation between the average neutron flux signals and the entire core flow rate signals, change ratio with time in the operation state signals for the coolant recycling system and the like and judges the abnormality in the coolant recycling system based on the calculated results. (Ikeda, J.)

  13. Fusion reactor pumped laser

    International Nuclear Information System (INIS)

    Jassby, D.L.

    1988-01-01

    A nuclear pumped laser is described comprising: a toroidal fusion reactor, the reactor generating energetic neutrons; an annular gas cell disposed around the outer periphery of the reactor, the cell including an annular reflecting mirror disposed at the bottom of the cell and an annular output window disposed at the top of the cell; a gas lasing medium disposed within the annular cell for generating output laser radiation; neutron reflector material means disposed around the annular cell for reflecting neutrons incident thereon back into the gas cell; neutron moderator material means disposed between the reactor and the gas cell and between the gas cell and the neutron reflector material for moderating the energy of energetic neutrons from the reactor; converting means for converting energy from the moderated neutrons to energy pumping means for pumping the gas lasing medium; and beam compactor means for receiving output laser radiation from the annular output window and generating a single output laser beam therefrom

  14. Reactor core cooling device

    International Nuclear Information System (INIS)

    Kobayashi, Masahiro.

    1986-01-01

    Purpose: To safely and effectively cool down the reactor core after it has been shut down but is still hot due to after-heat. Constitution: Since the coolant extraction nozzle is situated at a location higher than the coolant injection nozzle, the coolant sprayed from the nozzle, is free from sucking immediately from the extraction nozzle and is therefore used effectively to cool the reactor core. As all the portions from the top to the bottom of the reactor are cooled simultaneously, the efficiency of the reactor cooling process is increased. Since the coolant extraction nozzle can be installed at a point considerably higher than the coolant injection nozzle, the distance from the coolant surface to the point of the coolant extraction nozzle can be made large, preventing cavitation near the coolant extraction nozzle. Therefore, without increasing the capacity of the heat exchanger, the reactor can be cooled down after a shutdown safely and efficiently. (Kawakami, Y.)

  15. Mirror reactor surface study

    International Nuclear Information System (INIS)

    Hunt, A.L.; Damm, C.C.; Futch, A.H.; Hiskes, J.R.; Meisenheimer, R.G.; Moir, R.W.; Simonen, T.C.; Stallard, B.W.; Taylor, C.E.

    1976-01-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  16. Status of French reactors

    International Nuclear Information System (INIS)

    Ballagny, A.

    1997-01-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm 3 . The OSIRIS reactor has already been converted to LEU. It will use U 3 Si 2 as soon as its present stock of UO 2 fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU

  17. Utilización de antimicrobianos en el Hogar materno Doña Leonor Pérez durante el período 2007-2009 Use of antimicrobials in "Doña Leonor Pérez" home for pregnant women in the 2007-2009 period

    Directory of Open Access Journals (Sweden)

    Jessy Pavón Pérez

    2013-03-01

    Full Text Available Introducción: el uso inadecuado de los medicamentos supone un importante problema sanitario y económico, más sensible en el caso de los niños, ancianos y las embarazadas. Existen una gran diversidad de medicamentos y sobre muchos de ellos no se tiene un criterio definitivo de su inocuidad, por lo que la información disponible para la prescripción de fármacos en mujeres embarazadas, es muy escasa. Objetivo: evaluar la calidad en el uso racional de antimicrobianos en las gestantes ingresadas en el Hogar materno «Doña Leonor Pérez Cabrera» durante el período 2007- 2009. Métodos: este trabajo constituye un estudio de utilización de medicamento del tipo indicación prescripción, retrospectivo y descriptivo. Se revisaron las historias clínicas y se obtuvieron las variables biosociales edad materna, edad gestacional al ingreso, ocupación, diagnóstico que precisó el uso de antimicrobianos, forma de diagnóstico más utilizado así como los antimicrobianos más prescritos. Resultados: a través del análisis de las variables y de los esquemas terapéuticos se pudo evaluar la calidad de la prescripción de los antimicrobianos. Los resultados obtenidos permitieron constatar que predominaron las gestantes con edades entre 21 y 30 años, con edades gestacionales al ingreso entre 21 y 30 semanas y trabajadoras. La patología que mayormente motivó la utilización de antimicrobianos fue la sepsis vaginal, diagnosticada de forma clínica en casi la totalidad de los casos y los antimicrobianos más prescritos fueron la azitromicina, metronidazol, clotrimazol y nistatina. Conclusiones: con excepción de algunos antimicrobianos prescritos, la calidad de la prescripción en su mayoría resultó adecuada, la efectividad del tratamiento en su mayor parte fue buena y en general el uso racional de los antimicrobianos clasificó como alta y aceptable.Introduction: the misuse of drugs is a major health and economic problem, which is more sensitive in

  18. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    Ordonez, J.P.

    1990-01-01

    INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

  19. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Hirota, Jitsuya; Asaoka, Takumi; Suzuki, Tomoo; Mitani, Hiroshi; Akino, Fujiyoshi

    1977-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1976 are described. Works of the division concern mainly the development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and the development of Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and activities of the Committee on Reactor Physics. (auth.)

  20. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1978-10-01

    Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)