Science.gov

Sample records for romanian 14-mw triga

  1. The SANS facility at the Pitesti 14MW TRIGA reactor

    SciTech Connect

    Ionita, I. Grabcev, B.; Todireanu, S.; Constantin, F.; Shvetsov, V.; Anghel, E.; Popescu, G.; Mincu, M.; Datcu, A.

    2006-12-15

    The SANS facility existing at the Pitesti 14MW TRIGA reactor is presented. The main characteristics and the preliminary evaluation of the installation performances are given. A monochromatic neutron beam with 1.5 A {<=} {lambda} {<=} 5 A is produced by a mechanical velocity selector with helical slots. A fruitful partnership was established between INR Pitesti (Romania) and JINR Dubna (Russia). The first step in this cooperation consists in the manufacturing in Dubna of a battery of gas-filled positional detectors devoted to the SANS instrument.

  2. Testing WIMS-D4M cross sections and the ANL ENDF/B-V 69 group library. Results from global diffusion and Monte Carlo calculations compared with measurements in the Romanian 14-MW TRIGA reactor

    SciTech Connect

    Bretscher, M.M.

    1993-12-31

    The WIMS-D4 code has been modified (WIMS-D4M) to produce microscopic isotopic cross sections in ISOTXS format for use in diffusion and transport calculations. Beginning with 69-group libraries based on ENDF/B-V data, numerous cell calculations have been made to prepare a set of broad group cross sections for use in diffusion calculations. Global calculations have been made for two control rod states of the Romanian steady state TRIGA reactor with 29 fresh HEU fuel clusters. Detailed Monte Carlo calculations also have been performed for the same reactor configurations using data based on ENDF/B-V. Results from these global calculations are compared with each other and with the measured excess reactivities. Although region-averaged macroscopic principal cross sections obtained from WIMS-D4M are in good agreement with the corresponding Monte Carlo values, problems exist with the high energy (E > 10 keV) microscopic hydrogen transport cross sections.

  3. Transition from HEU to LEU fuel in Romania's 14-MW TRIGA reactor

    SciTech Connect

    Bretscher, M.M.; Snelgrove, J.L.

    1991-01-01

    The 14-MW TRIGA steady state reactor (SSR) located in Pitesti, Romania, first went critical in the fall of 1979. Initially, the core configuration for full power operation used 29 fuel clusters each containing a 5 {times} 5 square array of HEU (10 wt%) -- ZrH -- Er (2.8 wt%) fuel-moderator rods (1.295 cm o.d.) clad in Incology. With a total inventory of 35 HEU fuel clusters, burnup considerations required a gradual expansion of the core from 29 to 32 and finally to 35 clusters before the reactor was shut down because of insufficient excess reactivity. At this time each of the original 29 fuel clusters had an overage {sup 235}U burnup in the range from 50 to 62%. Because of the US policy regarding the export of highly enriched uranium, fresh HEU TRIGA replacement fuel is not available. After a number of safety-related measurements, the SSR is expected to resume full power operation in the near future using a mixed core containing five LEU TRIGA clusters of the same geometry as the original fuel but with fuel-moderator rods containing 45 wt% U (19.7% {sup 235}U enrichment) and 1.1 wt% Er. Rods for 14 additional LEU fuel clusters will be fabricated by General Atomics. In support of the SSR mixed core operation numerous neutronic calculations have been performed. This paper presents some of the results of those calculations.

  4. Transition from HEU to LEU fuel in Romania`s 14-MW TRIGA reactor

    SciTech Connect

    Bretscher, M.M.; Snelgrove, J.L.

    1991-12-31

    The 14-MW TRIGA steady state reactor (SSR) located in Pitesti, Romania, first went critical in the fall of 1979. Initially, the core configuration for full power operation used 29 fuel clusters each containing a 5 {times} 5 square array of HEU (10 wt%) -- ZrH -- Er (2.8 wt%) fuel-moderator rods (1.295 cm o.d.) clad in Incology. With a total inventory of 35 HEU fuel clusters, burnup considerations required a gradual expansion of the core from 29 to 32 and finally to 35 clusters before the reactor was shut down because of insufficient excess reactivity. At this time each of the original 29 fuel clusters had an overage {sup 235}U burnup in the range from 50 to 62%. Because of the US policy regarding the export of highly enriched uranium, fresh HEU TRIGA replacement fuel is not available. After a number of safety-related measurements, the SSR is expected to resume full power operation in the near future using a mixed core containing five LEU TRIGA clusters of the same geometry as the original fuel but with fuel-moderator rods containing 45 wt% U (19.7% {sup 235}U enrichment) and 1.1 wt% Er. Rods for 14 additional LEU fuel clusters will be fabricated by General Atomics. In support of the SSR mixed core operation numerous neutronic calculations have been performed. This paper presents some of the results of those calculations.

  5. Determination of α and f parameters at the 14-MW TRIGA reactor at Pitesti, Romania

    NASA Astrophysics Data System (ADS)

    Bărbos, D.; Păunoiu, C.; Roth, C.

    2010-10-01

    For experimental α determination the two-monitor method has been applied to determine α parameter in the irradiation channels at TRIGA 14 MW reactor (SCN Pitesti). The modified two-monitor method by using Cd ratio measurements eliminates the introducing of systematic errors due to the inaccuracy of absolute nuclear data. This characterization of the epithermal neutron spectrum is used in the k0-method of NAA, implemented at the SCN Pitesti. Neutron spectrum parameters were determined in the inner irradiation channel XC-1 and for outer irradiation channels: Beryllium J-6, Beryllium J-7, and Beryllium K-11. For α and f parameter verification a standard reference material denominated ECRM379-1 was analyzed using k0 standardization.

  6. Analytical analyses of startup measurements associated with the first use of LEU fuel in Romania's 14-MW TRIGA reactor

    SciTech Connect

    Bretscher, M.M.; Snelgrove, J.L. ); Ciocanescu, M. )

    1992-01-01

    The 14-MW TRIGA steady state reactor (SSR) is located in Pitesti, Romania. Beginning with an HEU core (10 wt% U), the reactor first went critical in November 1979 but was shut down ten years later because of insufficient excess reactivity. Last November the Institute for Nuclear Research (INR), which operates the SSR, received from the ANL RERTR program a shipment of 125 LEU pins fabricated by General Atomics and of the same geometry as the original fuel but with an enrichment of 19.7% 235U and a loading of 45 wt% U. Using 100 of these pins, four LEU clusters, each containing a 5 x 5 square array of fuel rods, were assembled. These four LEU clusters replaced the four most highly burned HEU elements in the SSR. The reactor resumed operations last February with a 35-element mixed HEU/LEU core configuration. In preparation for full power operation of the SSR with this mixed HEU/LEU core, a number of measurements were made. These included control rod calibrations, excess reactivity determinations, worths of experiment facilities, reaction rate distributions, and themocouple measurements of fuel temperatures as a function of reactor power. This paper deals with a comparison of some of these measured reactor parameters with corresponding analytical calculations.

  7. Analytical analyses of startup measurements associated with the first use of LEU fuel in Romania`s 14-MW TRIGA reactor

    SciTech Connect

    Bretscher, M.M.; Snelgrove, J.L.; Ciocanescu, M.

    1992-12-01

    The 14-MW TRIGA steady state reactor (SSR) is located in Pitesti, Romania. Beginning with an HEU core (10 wt% U), the reactor first went critical in November 1979 but was shut down ten years later because of insufficient excess reactivity. Last November the Institute for Nuclear Research (INR), which operates the SSR, received from the ANL RERTR program a shipment of 125 LEU pins fabricated by General Atomics and of the same geometry as the original fuel but with an enrichment of 19.7% 235U and a loading of 45 wt% U. Using 100 of these pins, four LEU clusters, each containing a 5 x 5 square array of fuel rods, were assembled. These four LEU clusters replaced the four most highly burned HEU elements in the SSR. The reactor resumed operations last February with a 35-element mixed HEU/LEU core configuration. In preparation for full power operation of the SSR with this mixed HEU/LEU core, a number of measurements were made. These included control rod calibrations, excess reactivity determinations, worths of experiment facilities, reaction rate distributions, and themocouple measurements of fuel temperatures as a function of reactor power. This paper deals with a comparison of some of these measured reactor parameters with corresponding analytical calculations.

  8. Study of the effect of {sup 135}Xe poison on the temperature coefficient of TRIGA fuel

    SciTech Connect

    Iorgulis, Constantin

    1992-07-01

    A study of the influence of {sup 135}Xe on the prompt negative temperature coefficient of the 14-MW Romanian TRIGA reactor has been performed. Because of its large absorption cross section below 0.1 eV, we expected that {sup 135}Xe might make a positive contribution to the temperature coefficient because the higher-energy neutrons are less likely to be absorbed by the Xe. This effect would be largest about 16 hours after reactor shutdown. In order to investigate this phenomenon, we have performed cell and core calculations for various fuel temperatures, burnups, and {sup 135}Xe levels. These calculations indeed show a positive contribution of {sup 135}Xe to the temperature coefficient, especially for high burnups, where little {sup 167}Er remains to absorb the higher-energy neutrons. Work is in progress to evaluate the effect of the smaller negative temperature coefficient on the consequences of reactivity insertion accidents in unfavorable situations of {sup 135}Xe poisoning of the Romanian TRIGA core. (author)

  9. The history and perspective of Romania-USA cooperation in the field of technologic transfer of TRIGA reactor concept

    SciTech Connect

    Ciocaanescu, M.; Ionescu, M.

    1996-08-01

    The cooperation between Romania and the USA in the field of technologic transfer of nuclear research reactor technology began with the steady state 14 MW{sub t} TRIGA reactor, installed at INR Pitesti, Romania. It is the first in the range of TRIGA reactors proposed as a materials testing reactor. The first criticality was reached in November 19, 1979 and first operation at 14 MW{sub t} level was in February 1980. The paper will present the short history of this cooperation and the perspective for a new cooperation for building a Nuclear Heating Plant using the TRIGA reactor concept for demonstration purpose. The energy crisis is a world-wide problem which affects each country in different ways because the resources and the consumption are unfairly distributed. World-wide research points out that the fossil fuel sources are not to be considered the main energy sources for the long term as they are limited.

  10. NRF TRIGA packaging

    SciTech Connect

    Clements, M.D.

    1995-11-01

    Training Reactor Isotopes, General Atomics (TRIGA{reg_sign}) Reactors are in use at four US Department of Energy (DOE) complex facilities and at least 23 university, commercial, or government facilities. The development of the Neutron Radiography Facility (NRF) TRIGA packaging system began in October 1993. The Hanford Site NRF is being shut down and requires an operationally user-friendly transportation and storage packaging system for removal of the TRIGA fuel elements. The NRF TRIGA packaging system is designed to remotely remove the fuel from the reactor and transport the fuel to interim storage (up to 50 years) on the Hanford Site. The packaging system consists of a cask and an overpack. The overpack is used only for transport and is not necessary for storage. Based upon the cask`s small size and light weight, small TRIGA reactors will find it versatile for numerous refueling and fuel storage needs. The NRF TRIGA packaging design also provides the basis for developing a certifiable and economical packaging system for other TRIGA reactor facilities. The small size of the NRF TRIGA cask also accommodates placing the cask into a larger certified packaging for offsite transport. The Westinghouse Hanford Company NRF TRIGA packaging, as described herein can serve other DOE sites for their onsite use, and the design can be adapted to serve university reactor facilities, handling a variety of fuel payloads.

  11. Romanian Basic Course.

    ERIC Educational Resources Information Center

    Defense Language Inst., Washington, DC.

    The "Romanian Basic Course," consisting of 89 lesson units in eight volumes, is designed to train native English language speakers to Level 3 proficiency in comprehension, speaking, reading, and writing Romanian (based on a 1-5 scale in which Level 5 is native speaker proficiency). Volume 1, which introduces basic sentences in dialog form with…

  12. Astronomy in Romanian universities

    NASA Astrophysics Data System (ADS)

    Barbosu, Mihail

    In this work we present characteristics of the Romanian higher education related to the study of Astronomy. In spite of Romanian economic problems, opportunities for Bachelor's degree, Master's degree (at "Babes-Bolyai" University of Cluj-Napoca) and Ph.D. degree are provided for students enrolled at the faculties of Mathematics or Physics. General regulations, description of courses, research resources and job opportunities are also described and discussed in this paper.

  13. Modern Romanian. Limba Romana.

    ERIC Educational Resources Information Center

    Augerot, James E.; Popescu, Florin D.

    This manual is intended for advanced university students in America who are learning Romanian as a third language. Part One is based upon an oral approach, each lesson containing a preparatory section in which the student is simultaneously introduced to pronunciation, intonation, and new semantic and syntactic structures. The second portion of the…

  14. Coseismic and early postseismic deformation of the 14 Mw=7.7 Tocopilla earthquake: Results from space-geodetic and seismological data

    NASA Astrophysics Data System (ADS)

    Motagh, M.; Anderssohn, J.; Krüger, F.; Schurr, B.; Walter, T. R.

    2008-12-01

    The November 14, 2007 Mw=7.7 earthquake nucleated at 15:40:53 (UTC time) on the west coast of northern Chile. Centred at 22.64°S and 70.61°W, about 40 km south-southeast of the town of Tocopilla, it destroyed about 1200 homes and left about 15% of the inhabitants homeless. The mainshock was felt strongly through much of northern Chile, as far north as La Paz and as far south as Santiago. The 2007 event took place in the central part of a large seismic gap that last ruptured in 1877 with an earthquake of magnitude 9. Here, we examine space-geodetic (InSAR & Ws-InSAR) and seismological data to study coseismic and early postseimic deformation of the 14 Mw=7.7 2008 Tocopilla earthquake, Chile. We propose a slip model that is consistent with both, geodetic and seismic dataset, and demonstrate that joint data analysis may significantly improve interpretability and physical understanding of the rupture pattern and earthquake dynamics.

  15. Extension of TRIGA reactor capabilities

    SciTech Connect

    Gietzen, A.J.

    1980-07-01

    The first TRIGA reactor went into operation at 10 kW about 22 years ago. Since that time 55 TRIGAs have been put into operation including steady-state powers up to 14,000 kW and pulsing reactors that pulse to 20,000,000 kW. Five more are under construction and a proposal will soon be submitted for a reactor of 25,000 kW. Along with these increases in power levels (and the corresponding fluxes) the experimental facilities have also been expanded. In addition to the installation of new TRIGA reactors with enhanced capabilities many of the older reactors have been modified and upgraded. Also, a number of reactors originally fueled with plate fuel were converted to TRIGA fuel to take advantage of the improved technical and safety characteristics, including the ability for pulsed operation. In order to accommodate increased power and performance the fuel has undergone considerable evolution. Most of the changes have been in the geometry, enrichment and cladding material. However, more recently further development on the UZrH alloy has been carried out to extend the uranium content up to 45% by weight. This increased U content is necessary to allow the use of less than 20% enrichment in the higher powered reactors while maintaining longer core lifetime. The instrumentation and control system has undergone remarkable improvement as the electronics technology has evolved so rapidly in the last two decades. The information display and the circuitry logic has also undergone improvements for enhanced ease of operation and safety. (author)

  16. TRIGA research reactor activities around the world

    SciTech Connect

    Chesworth, R.H.; Razvi, J.; Whittemore, W.L. )

    1991-11-01

    Recent activities at several overseas TRIGA installations are discussed in this paper, including reactor performance, research programs under way, and plans for future upgrades. The following installations are included: (1) 14,000-kW TRIGA at the Institute for Nuclear Research, Pitesti, Romania; (2) 2,000-kW TRIGA Mark II at the Institute of Nuclear Technology, Dhaka, Bangladesh; (3) 3,000-kW TRIGA conversion, Philippine Nuclear Research Institute, Quezon City, Philippines; and (4) other ongoing installations, including a 1,500-kW TRIGA Mark II at Rabat, Morocco, and a 1,000-kW conversion/upgrade at the Institute Asunto Nucleares, Bogota, Columbia.

  17. Radioactivity of spent TRIGA fuel

    NASA Astrophysics Data System (ADS)

    Usang, M. D.; Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P.

    2015-04-01

    Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive.

  18. Radioactivity of spent TRIGA fuel

    SciTech Connect

    Usang, M. D. Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P.

    2015-04-29

    Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive.

  19. Activation analysis using Cornell TRIGA

    SciTech Connect

    Hossain, Tim Z.

    1994-07-01

    A major use of the Cornell TRIGA is for activation analysis. Over the years many varieties of samples have been analyzed from a number of fields of interest ranging from geology, archaeology and textiles. More recently the analysis has been extended to high technology materials for applications in optical and semiconductor devices. Trace analysis in high purity materials like Si wafers has been the focus in many instances, while in others analysis of major/minor components were the goals. These analysis has been done using the delayed mode. Results from recent measurements in semiconductors and other materials will be presented. In addition the near future capability of using prompt gamma activation analysis using the Cornell cold neutron beam will be discussed. (author)

  20. English-Romanian Phrasebook with Useful Wordlist.

    ERIC Educational Resources Information Center

    Todeasa, Cornel, Ed.

    A phrasebook for Romanian-speaking refugees in the United States groups phrases in 19 units covering a wide range of situations and introducing the daily activities of American life. Two wordlists, one Romanian-English and one English-Romanian, provide the terms most frequently needed. The book is intended as a reference book for immediate use and…

  1. Romanian Scholarly Productivity: Recent History and Recommendations

    ERIC Educational Resources Information Center

    Ives, Bob; Badescu, Gabriel

    2015-01-01

    Romanian scholars, and others, have decried the quality and quantity of scholarly productivity from Romania. However, Romanian scholars face challenges of both tradition and resources as they try to westernize their higher education system. We analyzed data from two sources to compare Romanian scholarly productivity to that of other countries from…

  2. Creative Children in Romanian Society.

    ERIC Educational Resources Information Center

    Dinca, Margareta

    1999-01-01

    Romanian teachers and creative adolescents were interviewed to profile the creative adolescent, focusing on self-image and a description of social conditions contributing to creativity. Responses suggested that schools lack the means to stimulate creativity. Teachers recognize creativity but lack curricula to meet students' needs. Creative…

  3. Ballads of the Romanian Immigrants. Romanian Americans in Lake County, Indiana: An Ethnic Heritage Curriculum Project.

    ERIC Educational Resources Information Center

    Leuca, Mary, Comp.

    Twelve Romanian immigrant ballads with musical scores, Romanian lyrics, and English translations are presented. Following a description of early 20th Century Romanian immigrants in Lake County, Indiana, a pronunciation guide, descriptions of the ballads, and suggestions for classroom use are provided. English titles include "Lament from…

  4. Romanian-Serbian collaboration in Astronomy

    NASA Astrophysics Data System (ADS)

    Dimitrijević, Milan S.; Stavinschi, Magdalena

    2008-09-01

    In this contribution we present and analyze the collaboration of Romanian and Serbian astronomers. We also give the data on mutual visits of Romanian and Serbian astronomers, obtained by investigating the Guest book of Bucharest Astronomical Observatory and Annual Reports of Directors of Belgrade Astronomical Observatory published in various editions, as well as the history of four common meetings of Romanian and Serbian astronomers (Timisoara, Belgrade, Cluj-Napoca, Belgrade) organized by authors of this contribution.

  5. A Computer Code for TRIGA Type Reactors.

    Energy Science and Technology Software Center (ESTSC)

    1992-04-09

    Version 00 TRIGAP was developed for reactor physics calculations of the 250 kW TRIGA reactor. The program can be used for criticality predictions, power peaking predictions, fuel element burn-up calculations and data logging, and in-core fuel management and fuel utilization improvement.

  6. Decommissioning of the Northrop TRIGA reactor

    SciTech Connect

    Cozens, George B.; Woo, Harry; Benveniste, Jack; Candall, Walter E.; Adams-Chalmers, Jeanne

    1986-07-01

    An overview of the administrative and operational aspects of decommissioning and dismantling the Northrop Mark F TRIGA Reactor, including: planning and preparation, personnel requirements, government interfacing, costs, contractor negotiations, fuel shipments, demolition, disposal of low level waste, final survey and disposition of the concrete biological shielding. (author)

  7. Teaching Gender and Geography in Romanian Universities

    ERIC Educational Resources Information Center

    Voiculescu, Sorina

    2011-01-01

    The fall of communism in Central-Eastern Europe in 1989 brought major political, social, economic and cultural changes that reshaped the Romanian society as it transitioned from the totalitarian communist regime to a democratic one. The entire process of transition, eventuating in Romanian access to the European Union, brought important changes at…

  8. Optical Analysis of Some Romanian Marble

    NASA Astrophysics Data System (ADS)

    Pavelescu, G.; Ricman, C. T.; Ciuciu, J.; Savastru, D.; Nicolae, N.; Talianu, C.

    2007-04-01

    Characterization of some Romanian marble was done by fluorescence spectroscopy. Synchronous fluorescence spectroscopy (SFS) method was applied to obtain preliminary information on their fluorescence fingerprint. The characteristics of the fluorescence spectra (intensity, shape, bands, decay) for some sort of Romanian marble were analyzed in order to identify their nature and to discriminate the materials on clean and dirty states.

  9. NFR TRIGA package design review report

    SciTech Connect

    Clements, M.D.

    1994-08-26

    The purpose of this document is to compile, present and document the formal design review of the NRF TRIGA packaging. The contents of this document include: the briefing meeting presentations, package description, design calculations, package review drawings, meeting minutes, action item lists, review comment records, final resolutions, and released drawings. This design review required more than two meeting to resolve comments. Therefore, there are three meeting minutes and two action item lists.

  10. Monte Carlo modelling of TRIGA research reactor

    NASA Astrophysics Data System (ADS)

    El Bakkari, B.; Nacir, B.; El Bardouni, T.; El Younoussi, C.; Merroun, O.; Htet, A.; Boulaich, Y.; Zoubair, M.; Boukhal, H.; Chakir, M.

    2010-10-01

    The Moroccan 2 MW TRIGA MARK II research reactor at Centre des Etudes Nucléaires de la Maâmora (CENM) achieved initial criticality on May 2, 2007. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes for their use in agriculture, industry, and medicine. This study deals with the neutronic analysis of the 2-MW TRIGA MARK II research reactor at CENM and validation of the results by comparisons with the experimental, operational, and available final safety analysis report (FSAR) values. The study was prepared in collaboration between the Laboratory of Radiation and Nuclear Systems (ERSN-LMR) from Faculty of Sciences of Tetuan (Morocco) and CENM. The 3-D continuous energy Monte Carlo code MCNP (version 5) was used to develop a versatile and accurate full model of the TRIGA core. The model represents in detailed all components of the core with literally no physical approximation. Continuous energy cross-section data from the more recent nuclear data evaluations (ENDF/B-VI.8, ENDF/B-VII.0, JEFF-3.1, and JENDL-3.3) as well as S( α, β) thermal neutron scattering functions distributed with the MCNP code were used. The cross-section libraries were generated by using the NJOY99 system updated to its more recent patch file "up259". The consistency and accuracy of both the Monte Carlo simulation and neutron transport physics were established by benchmarking the TRIGA experiments. Core excess reactivity, total and integral control rods worth as well as power peaking factors were used in the validation process. Results of calculations are analysed and discussed.

  11. Romanian experience on packaging testing

    SciTech Connect

    Vieru, G.

    2007-07-01

    With more than twenty years ago, the Institute for Nuclear Research Pitesti (INR), through its Reliability and Testing Laboratory, was licensed by the Romanian Nuclear Regulatory Body- CNCAN and to carry out qualification tests [1] for packages intended to be used for the transport and storage of radioactive materials. Radioactive materials, generated by Romanian nuclear facilities [2] are packaged in accordance with national [3] and the IAEA's Regulations [1,6] for a safe transport to the disposal center. Subjecting these packages to the normal and simulating test conditions accomplish the evaluation and certification in order to prove the package technical performances. The paper describes the qualification tests for type A and B packages used for transport and storage of radioactive materials, during a period of 20 years of experience. Testing is used to substantiate assumption in analytical models and to demonstrate package structural response. The Romanian test facilities [1,3,6] are used to simulate the required qualification tests and have been developed at INR Pitesti, the main supplier of type A packages used for transport and storage of low radioactive wastes in Romania. The testing programme will continue to be a strong option to support future package development, to perform a broad range of verification and certification tests on radioactive material packages or component sections, such as packages used for transport of radioactive sources to be used for industrial or medical purposes [2,8]. The paper describes and contain illustrations showing some of the various tests packages which have been performed during certain periods and how they relate to normal conditions and minor mishaps during transport. Quality assurance and quality controls measures taken in order to meet technical specification provided by the design there are also presented and commented. (authors)

  12. 14. U.S. TRIGA users conference. Final program and summary of papers

    SciTech Connect

    1994-07-01

    The following papers were presented at the Conference: Early Development and Use of the TRIGA Reactor; Results of the MCNP Analysis of 20/20 LEU Fuel for the Oregon State University TRIGA Reactor; Upgradeable 2MW TRIGA Reactor Design for the Morocco Nuclear Energy Center McClellan Nuclear Radiation Center TRIGA Reactor: Four Years of Operations.

  13. 12. U.S. TRIGA users conference. Papers and abstracts

    SciTech Connect

    1990-07-01

    The Conference presentations were devoted to the following topics: new developments and improvements, including modifications of TRIGA reactors and equipment; experiments with TRIGA reactors (Neutron Radiography); radiochemistry, radioisotope production and beam irradiations (experiment applications, simulation); reactor physics - fuel utilization; reactor operation and maintenance experience; safety aspects, licensing and radiation protection.

  14. Fission product release from TRIGA-LEU reactor fuels

    SciTech Connect

    Baldwin, N.L.; Foushee, F.C.; Greenwood, J.S

    1980-07-01

    Due to present international concerns over nuclear proliferation, TRIGA reactor fuels will utilize only low-enriched uranium (LEU) (enrichment <20%). This requires increased total uranium loading per unit volume of fuel in order to maintain the appropriate fissile loading. Tests were conducted to determine the fractional release of gaseous and metallic fission products from typical uranium-zirconium hydride TRIGA fuels containing up to 45 wt-% uranium. These tests, performed in late 1977 and early 1978, were similar to those conducted earlier on TRIGA fuels with 8.5 wt-% U. Fission gas release measurements were made on prototypic specimens from room temperature to 1100 deg. C in the TRIGA King Furnace Facility. The fuel specimens were irradiated in the TRIGA reactor at a low power level. The fractional releases of the gaseous nuclides of krypton and xenon were measured under steady-state operating conditions. Clean helium was used to sweep the fission gases released during irradiation from the furnace into a standard gas collection trap for gamma counting. The results of these tests on TRIGA-LEU fuel agree well with data from the similar, earlier tests on TRIGA fuel. The correlation used to calculate the release of fission products from 8.5 wt-% U TRIGA fuel applies equally well for U contents up to 45 wt-%. (author)

  15. Perpetual transitions in Romanian healthcare.

    PubMed

    Spiru, Luiza; Traşcu, Răzvan Ioan; Turcu, Ileana; Mărzan, Mircea

    2011-12-01

    Although Romania has a long-lasting tradition in organized medical healthcare, in the last two decades the Romanian healthcare system has been undergoing a perpetual transition with negative effects on all parties involved. The lack of long-term strategic vision, the implementation of initiatives without any impact studies, hence the constant short-term approach from the policy makers, combined with the "inherited" low allocation from GDP to the healthcare system have contributed significantly to its current evolution. Currently, most measures taken are of the "fire-fighting" type, rather than looking to the broader, long time perspective. There should be no wonder then, that predictive and preventive services do not get the proper attention and support. Patient and physicians should step in and take action in regulating a system that was originally designed for them. But until this happens, the organizations with leadership skills and vision need to take action-and this has already started. PMID:23199172

  16. Romanian University Physics Teaching and Research (1860-1940).

    ERIC Educational Resources Information Center

    Constantinescu, Bogdan; Bugoi, Roxana

    1998-01-01

    Traces the evolution of physics teaching and research in Bucharest and Jassy, the two most important Romanian intellectual centers. Reports on three stages of historical development and selected biographies of Romanian scientists are included. (DDR)

  17. Fission-product release from TRIGA-LEU reactor fuels

    SciTech Connect

    Baldwin, N.L.; Foushee, F.C.; Greenwood, J.S.

    1980-11-01

    The release of fission products, both gaseous and volatile metals, from TRIGA fuel is important for the analysis of possible accident conditions related to reactor operation and the design of future TRIGA fuel systems. Because of present national concerns over nuclear proliferation, it has become clear that future reactor fuels will, of necessity, utilize low-enriched uranium (LEU, enrichment <20%). This will require increasing the total uranium loading per unit volume of the higher-loaded TRIGA fuels for the purpose of maintaining the appropriate fissile loading. Because of these new developments, tests were conducted to determine the fractional release of gaseous and metallic fission products from typical uranium-zirconium hydride TRIGA fuels containing 8.5 to 45 wt % uranium.

  18. TRIGA Mark II benchmark experiment; Part II: Pulse operation

    SciTech Connect

    Mele, I.; Ravnik, M.; Trkov, A. )

    1994-01-01

    Experimental results of pulse parameters and control rod worth measurements at TRIGA Mark 2 reactor in Ljubljana are presented. The measurements were performed with a completely fresh, uniform, and compact core. Only standard fuel elements with 12 wt% uranium were used. Special efforts were made to get reliable and accurate results at well-defined experimental conditions, and it is proposed to use the results as a benchmark test case for TRIGA reactors.

  19. Northrop Triga facility decommissioning plan versus actual results

    SciTech Connect

    Gardner, F.W.

    1986-01-01

    This paper compares the Triga facility decontamination and decommissioning plan to the actual results and discusses key areas where operational activities were impacted upon by the final US Nuclear Regulatory Commission (NRC)-approved decontamination and decommissioning plan. Total exposures for fuel transfer were a factor of 4 less than planned. The design of the Triga reactor components allowed the majority of the components to be unconditionally released.

  20. Romanian Educational Seismic Network Project

    NASA Astrophysics Data System (ADS)

    Tataru, Dragos; Ionescu, Constantin; Zaharia, Bogdan; Grecu, Bogdan; Tibu, Speranta; Popa, Mihaela; Borleanu, Felix; Toma, Dragos; Brisan, Nicoleta; Georgescu, Emil-Sever; Dobre, Daniela; Dragomir, Claudiu-Sorin

    2013-04-01

    Romania is one of the most active seismic countries in Europe, with more than 500 earthquakes occurring every year. The seismic hazard of Romania is relatively high and thus understanding the earthquake phenomena and their effects at the earth surface represents an important step toward the education of population in earthquake affected regions of the country and aims to raise the awareness about the earthquake risk and possible mitigation actions. In this direction, the first national educational project in the field of seismology has recently started in Romania: the ROmanian EDUcational SEISmic NETwork (ROEDUSEIS-NET) project. It involves four partners: the National Institute for Earth Physics as coordinator, the National Institute for Research and Development in Construction, Urban Planning and Sustainable Spatial Development " URBAN - INCERC" Bucharest, the Babeş-Bolyai University (Faculty of Environmental Sciences and Engineering) and the software firm "BETA Software". The project has many educational, scientific and social goals. The main educational objectives are: training students and teachers in the analysis and interpretation of seismological data, preparing of several comprehensive educational materials, designing and testing didactic activities using informatics and web-oriented tools. The scientific objective is to introduce into schools the use of advanced instruments and experimental methods that are usually restricted to research laboratories, with the main product being the creation of an earthquake waveform archive. Thus a large amount of such data will be used by students and teachers for educational purposes. For the social objectives, the project represents an effective instrument for informing and creating an awareness of the seismic risk, for experimentation into the efficacy of scientific communication, and for an increase in the direct involvement of schools and the general public. A network of nine seismic stations with SEP seismometers

  1. Important Developments in Romanian Propolis Research

    PubMed Central

    Mărghitaş, Liviu Al; Dezmirean, Daniel S.; Bobiş, Otilia

    2013-01-01

    The most important developments in propolis analysis and pharmacological properties are discussed. In order to help in the Romanian propolis standardization, different methodologies for chemical composition analysis (UV-VIS, HP-TLC, and HPLC-DAD) are reviewed using new approaches and software (fuzzy divisive hierarchical clustering approach and ChromQuest software) and compared with international studies made until now in propolis research. Practical applications of Romanian propolis in medicinal therapy and cosmetics are reviewed, and quality criteria for further standardization are proposed. PMID:23818918

  2. Problems of the Modern Romanian Astronomy: TELEROM

    NASA Astrophysics Data System (ADS)

    Grigore, Valentin; Minti, Harry; Vaduvescu, Ovidiu

    2011-06-01

    The TV broadcast discusses problems of the modernization of the Romanian astronomical infrastructure, the worst in Eastern Europe. It presents the TELEROM project which proposed to establish a new EU-funded robotic 1,3 m telescope, a project finally rejected by the Astronomical Institute of the Romanian Academy mainly due to the incompetence of the director of this Institute, Dr. Vasile Mioc. It is mentioned that this was the second very promising project failed under the same director, after the project ASTEROS in value of 15 million Euro to establish two modern telescopes was also lost in the recent years. The total cost of the TELEROM project was 1,5 million Euro, according to the agreement with the EU foundation for Regional Development (director Hanns Ruder Institut für Theoretische Astrophysik, Universität Tübingen, Germany - the TELEROM auto-dimissed project director). The facilities from this implementation were very promising in observations of Solar system objects (asteroids, near Earth asteroids, comets), few hundred millions of faint stars, quasars, exoplanets and galaxies. Initially, the director Vasile Mioc and the governing body of the Romanian Astronomical Institute intended to place the telescope in Romania in very bad astroclimatic conditions, namely in the old Feleac observatory, very close to the very highly polluted and quite clouded city of Cluj-Napoca. Many opposite considerations (Dr. Marian Doru Suran from Bucharest, many Romanian astronomers from the Diaspora and a group of 68 astronomers, professors, public outreach people and students from Romania and Diaspora supporting TELEROM) were totally disregarded! Due to refuse to place the telescope in very good astroclimatic conditions (in Canary Islands or Chile) and also due to the impossibility to establish a decent national astronomical observatory in Romania by the direction of the Institute in agreement with the State body of Romania ("Academia Romana" and "Autoritatea Nationala pentru

  3. 7. biennial U.S. TRIGA users' conference. Papers and abstracts

    SciTech Connect

    1980-07-01

    The conference covers the following topics: new developments in the TRIGA system; uses of microprocessors in control and monitoring and measurement of TRIGA performance parameters; safeguards, emergency planning, reactor standards; research facilities, fuel tests and calculations; TRIGA reactor parameters: emergency training.

  4. Romanian Approach to Media Portrayals of Disability

    ERIC Educational Resources Information Center

    Ciot, Melania-Gabriela; Van Hove, Geert

    2010-01-01

    There is a wide range of media representations of disability, but not just because of the societal stigma. They are a function of norms of journalism as well as biases among people with disabilities themselves. This article is a contribution to the issue of social representation of persons with disabilities from a Romanian perspective, which will…

  5. Romanian Scientific Abstracts, Volume 10 Number 3.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main numerical sequence. The December issue includes a subject index for the material included throughout the year. It also indicates, in an appended table, the numerical symbol of…

  6. Romanian Scientific Abstracts, Volume 10 Number 1.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main problems and is provided with an index and with key-words. The entries are recorded in numerical sequence. The December issue includes a subject index for the material included…

  7. Romanian Scientific Abstracts, Volume 10 Number 6.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main problems and is provided with an index and with key-words. The entries are recorded in numerical sequence. The December issue includes a subject index for the material included…

  8. Romanian Scientific Abstracts, Volume 10 Number 4.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main problems and is provided with an index and with key-words. The entries are recorded in numeric sequence. The December issue includes a subject index for the material included…

  9. Romanian Scientific Abstracts, Volume 10 Number 5.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main problems and is provided with an index and with key-words. The entries are recorded in numeric sequence. The December issue includes a subject index for the material included…

  10. Romanian Scientific Abstracts, Volume 9 Number 11.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main problems and is provided with an index and with key-words. The entries are recorded in numerical sequence. The December issue includes a subject index for the material included…

  11. Romanian Scientific Abstracts, Volume 9 Number 12.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main problems and is provided with an index and with key-words. T8e entries are recorded in numerical sequence. The December issue includes a subject index for the material included…

  12. Romanian Scientific Abstracts, Volume 10 Number 2.

    ERIC Educational Resources Information Center

    Caracas, Angela, Ed.

    The material included in the monthly issues of the "Romanian Scientific Abstracts" as bibliographic references or abstracts is arranged according to discipline and main problems and is provided with an index and with key-words. T entries are recorded in numerical sequence. The December issue includes a subject index for the material included…

  13. Palatalization in Romanian: Experimental and Theoretical Approaches

    ERIC Educational Resources Information Center

    Spinu, Laura

    2010-01-01

    Within the larger context of the Romance languages, Romanian stands alone in exhibiting a surface contrast between plain and palatalized consonants (that is, consonants with a secondary palatal articulation). While the properties of secondary palatalization are well known for language families in which the set of palatalized consonants is…

  14. A 5 MW TRIGA reactor design for radioisotope production

    SciTech Connect

    Veca, Anthony R.; Whittemore, William L.

    1994-07-01

    The production and preparation of commercial-scale quantities of radioisotopes has become an important activity as their medical and industrial applications continue to expand. There are currently various large multipurpose research reactors capable of producing ample quantities of radioisotopes. These facilities, however, have many competing demands placed upon them by a wide variety of researchers and scientific programs which severely limit their radioisotope production capability. A demonstrated need has developed for a simpler reactor facility dedicated to the production of radioisotopes on a commercial basis. This smaller, dedicated reactor could provide continuous fission and activation product radioisotopes to meet commercial requirements for the foreseeable future. The design of a 5 MW TRIGA reactor facility, upgradeable to 10 MW, dedicated to the production of industrial and medical radioisotopes is discussed. A TRIGA reactor designed specifically for this purpose with its demonstrated long core life and simplicity of operation would translate into increased radioisotope production. As an example, a single TRIGA could supply the entire US needs for Mo-99. The facility is based on the experience gained by General Atomics in the design, installation, and construction of over 60 other TRIGAs over the past 35 years. The unique uranium-zirconium hydride fuel makes TRIGA reactors inexpensive to build and operate, reliable in their simplicity, highly flexible due to unique passive safety, and environmentally friendly because of minimal power requirements and long-lived fuel. (author)

  15. Status of the TRIGA shipments to the INEEL from Europe

    SciTech Connect

    Mustin, T.; Stump, R.C.; Tyacke, M.J.

    1997-10-09

    This paper reports the activities underway by the US Department of Energy (DOE) for returning Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) from foreign research reactors (FRR) in four European countries to the Idaho National Engineering and Environmental Laboratory (INEEL). Those countries are Germany, Italy, Romania, and Slovenia. This is part of the ``Nuclear Weapons Nonproliferation Policy`` of returning research reactor SNF containing uranium enriched in the US. This paper describes the results of a pre-assessment trip in September, 1997, to these countries, including: history of the reactors and research being performed; inventory of TRIGA SNF; fuel types (stainless steel, aluminum, or Incoloy) and enrichments; and each country`s plans for returning their TRIGA SNF to the INEEL.

  16. TRIGA MARK-II source term

    NASA Astrophysics Data System (ADS)

    Usang, M. D.; Hamzah, N. S.; J. B., Abi M.; M. Z., M. Rawi; Abu, M. P.

    2014-02-01

    ORIGEN 2.2 are employed to obtain data regarding γ source term and the radio-activity of irradiated TRIGA fuel. The fuel composition are specified in grams for use as input data. Three types of fuel are irradiated in the reactor, each differs from the other in terms of the amount of Uranium compared to the total weight. Each fuel are irradiated for 365 days with 50 days time step. We obtain results on the total radioactivity of the fuel, the composition of activated materials, composition of fission products and the photon spectrum of the burned fuel. We investigate the differences of results using BWR and PWR library for ORIGEN. Finally, we compare the composition of major nuclides after 1 year irradiation of both ORIGEN library with results from WIMS. We found only minor disagreements between the yields of PWR and BWR libraries. In comparison with WIMS, the errors are a little bit more pronounced. To overcome this errors, the irradiation power used in ORIGEN could be increased a little, so that the differences in the yield of ORIGEN and WIMS could be reduced. A more permanent solution is to use a different code altogether to simulate burnup such as DRAGON and ORIGEN-S. The result of this study are essential for the design of radiation shielding from the fuel.

  17. TRIGA MARK-II source term

    SciTech Connect

    Usang, M. D. Hamzah, N. S. Abi, M. J. B. Rawi, M. Z. M. Rawi Abu, M. P.

    2014-02-12

    ORIGEN 2.2 are employed to obtain data regarding γ source term and the radio-activity of irradiated TRIGA fuel. The fuel composition are specified in grams for use as input data. Three types of fuel are irradiated in the reactor, each differs from the other in terms of the amount of Uranium compared to the total weight. Each fuel are irradiated for 365 days with 50 days time step. We obtain results on the total radioactivity of the fuel, the composition of activated materials, composition of fission products and the photon spectrum of the burned fuel. We investigate the differences of results using BWR and PWR library for ORIGEN. Finally, we compare the composition of major nuclides after 1 year irradiation of both ORIGEN library with results from WIMS. We found only minor disagreements between the yields of PWR and BWR libraries. In comparison with WIMS, the errors are a little bit more pronounced. To overcome this errors, the irradiation power used in ORIGEN could be increased a little, so that the differences in the yield of ORIGEN and WIMS could be reduced. A more permanent solution is to use a different code altogether to simulate burnup such as DRAGON and ORIGEN-S. The result of this study are essential for the design of radiation shielding from the fuel.

  18. TRIGA spent-fuel storage criticality analysis

    SciTech Connect

    Ravnik, M.; Glumac, B.

    1996-06-01

    A criticality safety analysis of a pool-type storage for spent TRIGA Mark II reactor fuel is presented. Two independent computer codes are applied: the MCNP Monte Carlo code and the WIMS lattice cell code. Two types of fuel elements are considered: standard fuel elements with 12 wt% uranium concentration and FLIP fuel elements. A parametric study of spent-fuel storage lattice pitch, fuel element burnup, and water density is presented. Normal conditions and postulated accident conditions are analyzed. A strong dependence of the multiplication factor on the distance between the fuel elements and on the effective water density is observed. A multiplication factor <1 may be expected for an infinite array of fuel rods at center-to-center distances >6.5 cm, regardless of the fuel element type and burnup. At shorter distances, the subcriticality can be ensured only by adding absorbers to the array of fuel rods even if the fuel rods were burned to {approximately}20% burnup. The results of both codes agree well for normal conditions. The results show that WIMS may be used as a complement to the Monte Carlo code in some parts of the criticality analysis.

  19. ORIGEN2 calculations supporting TRIGA irradiated fuel data package

    SciTech Connect

    Schmittroth, F.A.

    1996-09-20

    ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiography Facility. The calculations support storage and disposal and results include mass, activity,and decay heat. Comparisons with underwater dose-rate measurements were used to confirm and adjust the calculations.

  20. 78 FR 26811 - Dow Chemical Company, Dow TRIGA Research Reactor; License Renewal for the Dow Chemical TRIGA...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-08

    ...) published a notice in the Federal Register on July 20, 2012 (77 FR 42771), ``License Renewal for the Dow...: I. Correction In the Federal Register (FR) of July 20, 2012, in FR Doc. 2012- 17733, on page 42772... COMMISSION Dow Chemical Company, Dow TRIGA Research Reactor; License Renewal for the Dow Chemical...

  1. American Terms in the Romanian of Science and Technology.

    ERIC Educational Resources Information Center

    Berceanu, Vera

    Historical conditions determined that the Romanian language developed independently of the other Romance languages; the language thus remains behind in its development. In the eighteenth century the activity of the Transylvanian School of philologists established the Romanian language's own linguistic bases for the assimilation of borrowings from…

  2. Romanian Folk Dancing. Romanian Americans in Lake County, Indiana: An Ethnic Heritage Curriculum Project.

    ERIC Educational Resources Information Center

    Bogolia, Kathleen M.; Leuca, Mary, Ed.

    The booklet provides instructions for five Romanian folk dances. The dances include: the "Hora," one of the oldest, most widely known dances; the "Invirtita" and the "Hategana," Transylvanian celebration dances; the "Sirba," popular in all regions of Romania; and the "Caluserul" (the "Leaping Horse"), which dates back to the time when the Roman…

  3. Completed Decommissioning of the Research Reactor TRIGA Heidelberg We are specialised in Decommissioning a Research Reactor in Germany now

    SciTech Connect

    Juenger-Graef, B.; Hoever, K.; Moser, T.; Berthold, M.; Blenski, H.J.

    2006-07-01

    This paper describes the decommissioning of the TRIGA Heidelberg II reactor which was used until 1999, and of the TRIGA Heidelberg I reactor, which was for the last 20 years in a safe containment. (authors)

  4. TRIGA reactor facility at the Armed Forces Radiobiology Research Institute: A simplified technical description. revision. Technical report

    SciTech Connect

    Moore, M.L.

    1994-01-01

    This publication provides a simplified technical description of the TRIGA research reactor at AFRRI. Topics covered include general principles of reactor operation and a description of the TRIGA reactor and its unique features.

  5. Identification of leaking TRIGA fuel elements

    SciTech Connect

    Bennion, John S.; Crawford, Kevan C.; Gansauge, Todd C.; Sandquist, Gary M.

    1990-07-01

    The 100 kW TRIGA Mark I Nuclear Reactor at the University of Utah achieved initial criticality in October, 1975. Previously irradiated fuel consisting of stainless-steel- and aluminum-clad elements was acquired from the University of Arizona and the U.S. Army's Harry Diamond Laboratories in Adelphi, Maryland. Past core configurations have been comprised of both types of fuel with the aluminum-clad elements normally restricted to outer hexagonal rings of the core to provide a large safety margin between actual fuel temperature and limits set forth in the facility Technical Specifications. On October 20, 1987, trace cesium-137 contamination was discovered during routine analysis of the ion-exchange resin in the demineralizer circuit. The presence of Cs-137 indicated a possible clad defect resulting in the leakage of fission products. Reactor operations were allowed only to assist in identifying the source of the leakage. Pool water samples obtained following a two-hour operation at full power were spectroscopically analyzed and found to contain very small amounts of short-lived noble gases (e.g., Kr-85m, Kr-87, Kr-88, Xe-138) and their decay daughter products (e.g., Rb-88, Cs-138). Samples of the gaseous effluent from the facility collected in activated charcoal canisters showed no indication of fission product contamination. The small amount of activity released to the pool water suggested that a single defective element was responsible for the leakage. The instrumented fuel element and the aluminum-clad fuel were initially suspected as sources of the leakage. A simple scheme was devised to identify the defective element by exchanging four or five elements from the core with fuel in storage and then operating the reactor at 90 kW power for two hours. A pool water sample was then taken and analyzed to determine if the damaged element had been removed from the core. This process was repeated several times until all of the aluminum-clad fuel and several stainless

  6. High-Precision Mass Measurements At TRIGA-TRAP

    NASA Astrophysics Data System (ADS)

    Smorra, C.; Beyer, T.; Blaum, K.; Block, M.; Eberhardt, K.; Eibach, M.; Herfurth, F.; Ketelaer, J.; Knuth, K.; Nörtershäuser, W.; Nagy, Sz.

    2010-04-01

    In order to study neutron-rich nuclides far from the valley of stability as well as long-lived actinoids the double Penning-trap mass spectrometer TRIGA-TRAP has been recently installed at the research reactor TRIGA Mainz. Short-lived neutron-rich fission products are produced by thermal neutron-induced fission of an actinoid target installed close to the reactor core. A helium gas-jet system with carbon aerosol particles is used to extract the fission products to the experiment. The Penning trap system has already been commissioned. Off-line mass measurements are routinely performed using a recently developed laser ablation ion source, and the gas-jet system has been tested. An overview of the experiment and current status will be given.

  7. Operational characteristics of the new 12 wt% TRIGA fuel

    SciTech Connect

    Boyle, P.; Levine, S.H.

    1997-12-01

    It has been reported that an instrumented TRIGA fuel element, I-15, had higher than normal fuel temperatures. As shown in Fig. 1, one of the newest instrumented fuel elements, I-17, has fuel temperatures equal to/and or higher than that of I-15. Another new fuel element, I-16, behaves similarly to I-17, and this is before they have been pulsed (the first pulses increase the steady-state temperature). Thus, there is a significant increase in the measured fuel temperatures of the newest TRIGA fuel received from General Atomics. They are estimated to measure fuel temperatures that exceed 600{degrees}C when in the B-ring at 1 MW at their beginning of life (BOL). The purpose of this summary is to report on the measurements performed with these new fuel elements and to describe the effect that the new information is having on the future fuel management plans for the Penn State Breazeale Research Reactor.

  8. Implementation of an aerodynamic lens for TRIGA-SPEC

    NASA Astrophysics Data System (ADS)

    Grund, J.; Düllmann, Ch. E.; Eberhardt, K.; Nagy, Sz.; van de Laar, J. J. W.; Renisch, D.; Schneider, F.

    2016-06-01

    We report on the optimization of the gas-jet system employed to couple the TRIGA-SPEC experiment to the research reactor TRIGA Mainz. CdI2 aerosol particles suspended in N2 as carrier gas are used for an effective transport of fission products from neutron induced 235 U fission from the target chamber to a surface ion source. Operating conditions of the gas-jet were modified to enable the implementation of an aerodynamic lens, fitting into the limited space available in front of the ion source. The lens boosts the gas-jet efficiency by a factor of 4-10. The characterization of the gas-jet system as well as the design of the aerodynamic lens and efficiency studies are presented and discussed.

  9. TRIGA FUEL PHASE I AND II CRITICALITY CALCULATION

    SciTech Connect

    L. Angers

    1999-11-23

    The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA (Training, Research, Isotopes, General Atomic) reactor spent nuclear fuel (SNF) with Savannah River Site (SRS) high-level waste (HLW). The TRIGA SNF is loaded into a Department of Energy (DOE) standardized SNF canister which is centrally positioned inside a five-canister defense SRS HLW waste package (WP). The objective of the calculation is to investigate the criticality issues for the WP containing the five SRS HLW and DOE SNF canisters in various stages of degradation. This calculation will support the analysis that will be performed to demonstrate the viability of the codisposal concept for the Monitored Geologic Repository (MGR).

  10. Status of the TRIGA shipments to the INEEL from Asia

    SciTech Connect

    Tyacke, M.; George, W.; Petrasek, A.; Stump, R.C.; Patterson, J.

    1997-10-09

    This paper will report on preparations being made for returning Training, Research, Isotope, General Atomics (TRIGA) foreign research reactor (FRR) spent fuel from South Korea and Indonesia to the Idaho National Engineering and Environmental Laboratory (INEEL). The roles of US Department of Energy, INEEL, and NAC International in implementing a safe shipment are provided. Special preparations necessitated by making a shipment through a west coast port of the US to the INEEL will be explained. The institutional planning and actions needed to meet the unique political and operational environment for making a shipment from Asia to INEEL will be discussed. Facility preparation at both the INEEL and the FRRs is discussed. Cask analysis needed to properly characterize the various TRIGA configurations, compositions, and enrichments is discussed. Shipping preparations will include an explanation of the integrated team of spent fuel transportation specialists, and shipping resources needed to retrieve the fuel from foreign research reactor sites and deliver it to the INEEL.

  11. High-Precision Mass Measurements At TRIGA-TRAP

    SciTech Connect

    Smorra, C.; Eibach, M.; Beyer, T.; Blaum, K.; Block, M.; Herfurth, F.; Eberhardt, K.; Ketelaer, J.; Knuth, K.; Noertershaeuser, W.; Nagy, Sz.

    2010-04-30

    In order to study neutron-rich nuclides far from the valley of stability as well as long-lived actinoids the double Penning-trap mass spectrometer TRIGA-TRAP has been recently installed at the research reactor TRIGA Mainz. Short-lived neutron-rich fission products are produced by thermal neutron-induced fission of an actinoid target installed close to the reactor core. A helium gas-jet system with carbon aerosol particles is used to extract the fission products to the experiment. The Penning trap system has already been commissioned. Off-line mass measurements are routinely performed using a recently developed laser ablation ion source, and the gas-jet system has been tested. An overview of the experiment and current status will be given.

  12. Temperature feedback of TRIGA MARK-II fuel

    NASA Astrophysics Data System (ADS)

    Usang, M. D.; Minhat, M. S.; Rabir, M. H.; M. Rawi M., Z.

    2016-01-01

    We study the amount of temperature feedback on reactivity for the three types of TRIGA fuel i.. ST8, ST12 and LEU fuel, are used in the TRIGA MARK II reactor in Malaysia Nuclear Agency. We employ WIMSD-5B for the calculation of kin f for a single TRIGA fuel surrounded by water. Typical calculations of TRIGA fuel reactivity are usually limited to ST8 fuel, but in this paper our investigation extends to ST12 and LEU fuel. We look at the kin f of our model at various fuel temperatures and calculate the amount reactivity removed. In one instance, the water temperature is kept at room temperature of 300K to simulate sudden reactivity increase from startup. In another instance, we simulate the sudden temperature increase during normal operation where the water temperature is approximately 320K while observing the kin f at various fuel temperatures. For accidents, two cases are simulated. The first case is for water temperature at 370K and the other is without any water. We observe that the higher Uranium content fuel such as the ST12 and LEU have much smaller contribution to the reactivity in comparison to the often studied ST8 fuel. In fact the negative reactivity coefficient for LEU fuel at high temperature in water is only slightly larger to the negative reactivity coefficient for ST8 fuel in void. The performance of ST8 fuel in terms of negative reactivity coefficient is cut almost by half when it is in void. These results are essential in the safety evaluation of the reactor and should be carefully considered when choices of fuel for core reconfiguration are made.

  13. Computational analysis of irradiation facilities at the JSI TRIGA reactor.

    PubMed

    Snoj, Luka; Zerovnik, Gašper; Trkov, Andrej

    2012-03-01

    Characterization and optimization of irradiation facilities in a research reactor is important for optimal performance. Nowadays this is commonly done with advanced Monte Carlo neutron transport computer codes such as MCNP. However, the computational model in such calculations should be verified and validated with experiments. In the paper we describe the irradiation facilities at the JSI TRIGA reactor and demonstrate their computational characterization to support experimental campaigns by providing information on the characteristics of the irradiation facilities. PMID:22154389

  14. TRIGA: Telecommunications Protocol Processing Subsystem Using Reconfigurable Interoperable Gate Arrays

    NASA Technical Reports Server (NTRS)

    Pang, Jackson; Pingree, Paula J.; Torgerson, J. Leigh

    2006-01-01

    We present the Telecommunications protocol processing subsystem using Reconfigurable Interoperable Gate Arrays (TRIGA), a novel approach that unifies fault tolerance, error correction coding and interplanetary communication protocol off-loading to implement CCSDS File Delivery Protocol and Datalink layers. The new reconfigurable architecture offers more than one order of magnitude throughput increase while reducing footprint requirements in memory, command and data handling processor utilization, communication system interconnects and power consumption.

  15. Steady-State Axial Temperature and Flow Velocity in Triga Channel.

    Energy Science and Technology Software Center (ESTSC)

    2007-02-28

    Version 00 TRISTAN-IJS is a computer program for calculating steady-state axial temperature distribution and flow velocity through a vertical coolant channel in low power TRIGA reactor core, cooled by natural circulation. It is designed for steady-state thermohydraulic analysis of TRIGA research reactors operating at a low power level of 1-2 MW.

  16. An RFQ cooler and buncher for the TRIGA-SPEC experiment

    NASA Astrophysics Data System (ADS)

    Beyer, T.; Blaum, K.; Block, M.; Düllmann, Ch. E.; Eberhardt, K.; Eibach, M.; Frömmgen, N.; Geppert, C.; Gorges, C.; Grund, J.; Hammen, M.; Kaufmann, S.; Krieger, A.; Nagy, Sz.; Nörterhäuser, W.; Renisch, D.; Smorra, C.; Will, E.

    2014-01-01

    A linear Paul trap for cooling of ion beams, the former cooler for emittance elimination radiofrequency quadrupole (RFQ) at MISTRAL/ISOLDE, has been installed and commissioned at the TRIGA-SPEC experiment located at the research reactor TRIGA Mainz. It is connected to a hot-surface-ionization ion source and a subsequent mass separator for ionization and pre-separation of neutron-rich fission products as delivered from the reactor. The capability of accumulating and bunching ion beams has been implemented to provide low-emittance ion pulses of 250 ns width containing up to 106 ions. A technical description of the upgraded RFQ as well as its characterization with stable ions is presented. Its installation allows delivery of low-emittance ion bunches to the two branches of the TRIGA-SPEC experiment, namely TRIGA-TRAP and TRIGA-LASER.

  17. Proposed modification of an instrumented TRIGA fuel element so that it may be handled with a standard TRIGA fuel handling tool

    SciTech Connect

    Doane, Harry J.

    1992-07-01

    Instrumented fuel elements whose thermocouples are no longer functional are still a useful source of reactor fuel. Their usefulness is hampered somewhat by the extension tubing that must extend above water level to keep the thermocouple extension leads dry and to keep pool water from interacting with the gas tight lead seal which is made below the lower coupling in the extension tubing. This facility proposes to modify an instrumented TRIGA fuel element by removing the extension tubing at the lower coupling and attaching to it a top end fixture that is normally supplied with a standard TRIGA fuel element. This would then allow movement of the modified fuel element with a standard TRIGA fuel handling tool. This paper will present the considerations involved in performing this modification and the presenter will solicit any useful information that might be contributed by attendees of the TRIGA Owners' Conference. (author)

  18. [Dutch-Romanian cooperation in the area of family practice].

    PubMed

    van Es, J C

    2001-10-27

    During the years 1992-2000, there was a cooperative programme between the Romanian general practitioners' association (Societatea Nationala de Medicina Generala) in Romania and the Dutch Foundation for the Advancement of Quality in Healthcare in Romania. A succession of programmes were developed and carried out, which were financed by the Dutch government. The purpose of the cooperative programme was to support the development of Romanian general practice in terms of quality and structure. In the first programme, financed by the Dutch Ministry of Health, Welfare and Sport, about 200 Romanian general practitioners received continuing education. This was followed by a social transformation programme (MATRA) that had two parts: (a) the general practitioners association was supported and advised with respect to improving its organisational efficiency and (b) about 50 carefully selected Romanian general practitioners were trained, in post-academic research, management or teaching. The Romanian authorities accredited these trainees as teachers. The co-operation is being continued in 2001 with the setting up of a sentinel station programme in which 100 Romanian general practitioners collect relevant, representative data on health, illness and practice. PMID:11715598

  19. Development of the ageing management database of PUSPATI TRIGA reactor

    NASA Astrophysics Data System (ADS)

    Ramli, Nurhayati; Maskin, Mazleha; Tom, Phongsakorn Prak; Husain, Nurfazila; Farid, Mohd Fairus Abd; Ramli, Shaharum; Adnan, Amirul Syazwan; Abidin, Nurul Husna Zainal

    2016-01-01

    Since its first criticality in 1982, PUSPATI TRIGA Reactor (RTP) has been operated for more than 30 years. As RTP become older, ageing problems have been seen to be the prominent issues. In addressing the ageing issues, an Ageing Management (AgeM) database for managing related ageing matters was systematically developed. This paper presents the development of AgeM database taking into account all RTP major Systems, Structures and Components (SSCs) and ageing mechanism of these SSCs through the system surveillance program.

  20. Hydrogen and Oxygen Gas Production in the UT TRIGA Reflector

    SciTech Connect

    D. S. O'Kelly

    2000-11-12

    In December 1999, The University of Texas at Austin (UT) reported an unusual condition associated with the annular graphite reflector surrounding the Nuclear Engineering Teaching Laboratory (NETL) TRIGA reactor. The aluminum container encapsulating the graphite showed signs of bulging or swelling. Further, during an investigation of this occurrence, bubbles were detected coming from a weld in the aluminum. The gas composition was approximately 2:1 hydrogen to oxygen. After safety review and equipment fabrication, the reflector was successfully vented and flooded. The ratio of the gases produced is unusual, and the gas production mechanism has not yet been explained.

  1. TRIGA high wt -% LEU fuel development program. Final report

    SciTech Connect

    West, G.B.

    1980-07-01

    The principal purpose of this work was to investigate the characteristics of TRIGA fuel where the contained U-235 was in a relatively high weight percent (wt %) of LEU (low enriched uranium - enrichment of less than 20%) rather than a relatively low weight percent of HEU (high enriched uranium). Fuel with up to 45 wt % U was fabricated and found to be acceptable after metallurgical examinations, fission product retention tests and physical property examinations. Design and safety analysis studies also indicated acceptable prompt negative temperature coefficient and core lifetime characteristics for these fuels.

  2. Resource Guide: Romanian Americans in Lake County, Indiana: An Ethnic Heritage Curriculum Project.

    ERIC Educational Resources Information Center

    Leuca, Mary

    A resource guide suitable for secondary level for teaching about Romanian Americans and their contributions is presented. Following two essays which describe the country of Romania and the story of Romanian Americans in Lake County, Indiana, four sections trace the development of the Romanian community. Section I discusses the history and causes…

  3. Examples of Practice: An Intercultural Approach to Translate Romanian Children's Folklore into Spanish

    ERIC Educational Resources Information Center

    Oprica, Dana

    2016-01-01

    Due to the great number of Romanian pupils in Spanish public school, the local administration organises extra-curricular Romanian courses in order to preserve the Romanian language and culture. This is a way to contribute to build and consolidate a bicultural and bilingual profile of the young people. Besides, it is also an opportunity to align…

  4. Transport of fission products with a helium gas-jet at TRIGA-SPEC

    NASA Astrophysics Data System (ADS)

    Eibach, M.; Beyer, T.; Blaum, K.; Block, M.; Eberhardt, K.; Herfurth, F.; Geppert, C.; Ketelaer, J.; Ketter, J.; Krämer, J.; Krieger, A.; Knuth, K.; Nagy, Sz.; Nörtershäuser, W.; Smorra, C.

    2010-02-01

    A helium gas-jet system for the transport of fission products from the research reactor TRIGA Mainz has been developed, characterized and tested within the TRIGA-SPEC experiment. For the first time at TRIGA Mainz carbon aerosol particles have been used for the transport of radionuclides from a target chamber with high efficiency. The radionuclides have been identified by means of γ-spectroscopy. Transport time, efficiency as well as the absolute number of transported radionuclides for several species have been determined. The design and the characterization of the gas-jet system are described and discussed.

  5. Analysis of cocked fuel elements in the AFRRI TRIGA Mark-F reactor

    SciTech Connect

    Sholtis, Joseph A. Jr.

    1982-07-01

    The Armed Forces Radiobiology Research Institute (AFRRI) TRIGA Mark-F pulsing reactor has experienced eight cocked fuel elements during the period 5 November 1974 through 17 February 1982. Although there are no adverse health and safety consequences associated with their occurrence and there is no credible potential for system damage, cocked TRIGA fuel elements do cause inconvenience to the reactor staff and a temporary delay in operations. This paper presents the history of cocked TRIGA fuel elements at AFRRI, discusses possible mechanisms for their occurrence, and outlines a plan to isolate and ultimately determine their actual cause.

  6. Modification of the Core Cooling System of TRIGA 2000 Reactor

    NASA Astrophysics Data System (ADS)

    Umar, Efrizon; Fiantini, Rosalina

    2010-06-01

    To accomplish safety requirements, a set of actions has to be performed following the recommendations of the IAEA safety series 35 applied to research reactor. Such actions are considered in modernization of the old system, improving the core cooling system and safety evaluations. Due to the complexity of the process and the difficulty in putting the apparatus in the reactor core, analytical and experimental study on the determination of flow and temperature distribution in the whole coolant channel are difficult to be done. In the present work, a numerical study of flow and temperature distribution in the coolant channel of TRIGA 2000 has been carried out using CFD package. For this study, simulations were carried out on 3-D tested model. The model consists of the reactor tank, thermal and thermalizing column, reflector, rotary specimen rack, chimney, fuel element, primary pipe, diffuser, beam tube and a part of the core are constructed by 1.50 million unstructured tetrahedral cell elements. The results show that for the initial condition (116 fuel elements in the core) and for the inlet temperature of 24°C and the primary velocity of 5.6 m/s, there no boiling phenomena occur in the coolant channel. Due to this result, it is now possible to improve the core cooling system of TRIGA 2000 reactor. Meanwhile, forced flow from the diffuser system only affected the flow pattern in the outside of chimney and put on a small effect to the fluid flow's velocity in the inside of chimney.

  7. Modification of the Core Cooling System of TRIGA 2000 Reactor

    SciTech Connect

    Umar, Efrizon; Fiantini, Rosalina

    2010-06-22

    To accomplish safety requirements, a set of actions has to be performed following the recommendations of the IAEA safety series 35 applied to research reactor. Such actions are considered in modernization of the old system, improving the core cooling system and safety evaluations. Due to the complexity of the process and the difficulty in putting the apparatus in the reactor core, analytical and experimental study on the determination of flow and temperature distribution in the whole coolant channel are difficult to be done. In the present work, a numerical study of flow and temperature distribution in the coolant channel of TRIGA 2000 has been carried out using CFD package. For this study, simulations were carried out on 3-D tested model. The model consists of the reactor tank, thermal and thermalizing column, reflector, rotary specimen rack, chimney, fuel element, primary pipe, diffuser, beam tube and a part of the core are constructed by 1.50 million unstructured tetrahedral cell elements. The results show that for the initial condition (116 fuel elements in the core) and for the inlet temperature of 24 deg. C and the primary velocity of 5.6 m/s, there no boiling phenomena occur in the coolant channel. Due to this result, it is now possible to improve the core cooling system of TRIGA 2000 reactor. Meanwhile, forced flow from the diffuser system only affected the flow pattern in the outside of chimney and put on a small effect to the fluid flow's velocity in the inside of chimney.

  8. Tritium level along Romanian Black Sea Coast

    SciTech Connect

    Varlam, C.; Stefanescu, I.; Popescu, I.; Faurescu, I.

    2008-07-15

    Establishing the tritium level along the Romanian Black Sea Coast, after 10 years of exploitation of the nuclear power plant from Cernavoda, is a first step in evaluating its impact on the Black Sea ecosystem. The monitoring program consists of tritium activity concentration measurement in sea water and precipitation from Black Sea Coast between April 2005 and April 2006. The sampling points were spread over the Danube-Black Sea Canal - before the locks Agigea and Navodari, and Black Sea along the coast to the Bulgarian border. The average tritium concentration in sea water collected from the sampling locations had the value of 11.1 {+-} 2.1 TU, close to tritium concentration in precipitation. Although an operating nuclear power plant exists in the monitored area, the values of tritium concentration in two locations are slightly higher than those recorded elsewhere. To conclude, it could be emphasized that until now, Cernavoda NPP did not had any influence on the tritium concentration of the Black Sea Shore. (authors)

  9. Design Verification Report Neutron Radiography Facility (NRF) TRIGA Fuel Storage Systems

    SciTech Connect

    CARRELL, R.D.

    2002-01-31

    This report outlines the methods, procedures, and outputs developed during the Neutron Radiography Facility (NRF) Training, Research and Isotope Production, General Atomics (TRIGA) fuel storage system design and fabrication.

  10. Environmental Assessment: Relocation and storage of TRIGA{reg_sign} reactor fuel, Hanford Site, Richland, Washington

    SciTech Connect

    1995-08-01

    In order to allow the shutdown of the Hanford 308 Building in the 300 Area, it is proposed to relocate fuel assemblies (101 irradiated, three unirradiated) from the Mark I TRIGA Reactor storage pool. The irradiated fuel assemblies would be stored in casks in the Interim Storage Area in the Hanford 400 Area; the three unirradiated ones would be transferred to another TRIGA reactor. The relocation is not expected to change the offsite exposure from all Hanford Site 300 and 400 Area operations.

  11. A combined wet/dry sipping cell for investigating failed TRIGA fuel elements

    SciTech Connect

    Hammer, J.; Gallhammer, H.; Bock, H.

    1988-07-01

    Investigation for a failed TRIGA fuel element is performed with the help of a combined wet/dry sipping cell, which has been designed and fabricated at the Atominstitut Vienna. In this sipping cell a TRIGA fuel element can be studied for fission product release, both at normal and at elevated temperatures. This report describes the design features of the sipping cell and the fission product identification procedure with the help of a high purity Germanium detector and a multichannel analyzer.

  12. Code System to Calculate Mixed Cores in TRIGA Mark II Research Reactor.

    Energy Science and Technology Software Center (ESTSC)

    2001-08-29

    Version 00 TRIGLAV is a computer program for reactor calculations of mixed cores in a TRIGA Mark II research reactor. It can be applied for fuel element burn-up calculations, for power and flux distributions calculations and for reactivity predictions. The TRIGLAV program requires the WIMS-D4 program with the original WIMS cross-section library extended for TRIGA reactor specific nuclides. This package includes the code TRIGAC, which is a new version of TRIGAP.

  13. TRIGA-SPEC: the prototype of MATS and LaSpec

    NASA Astrophysics Data System (ADS)

    Kaufmann, S.; Beyer, T.; Blaum, K.; Block, M.; Düllmann, Ch E.; Eberhardt, K.; Eibach, M.; Geppert, C.; Gorges, C.; Grund, J.; Hammen, M.; Krämer, J.; Nagy, Sz; Nörtershäuser, W.; Renisch, D.; Schneider, F.; Wendt, K.

    2015-04-01

    Investigation of short-lived nuclei is a challenging task that MATS and LaSpec will handle at the low energy branch of Super-FRS at FAIR. The groundwork for those experiments is laid-out already today at the TRIGA-SPEC facility as a powerful development platform located at the research reactor TRIGA Mainz. The latest status, new developments and first results of commissioning runs are presented here.

  14. Anglicisms in the Romanian business and technology vocabulary

    NASA Astrophysics Data System (ADS)

    Todea, L.; Demarcsek, R.

    2016-08-01

    Multinational companies in Romania have imposed the use of the predominant language, in most cases - English, in professional communication. In contexts related to workplace communication, the main motivation for foreign borrowings is the need to denote concepts and activities. The article focuses on the English language as a wide source for a great number of innovations both at the lexical and the morphological level in the Romanian vocabulary related to business and technology. The aim of the paper is to demonstrate that Romanian language displays a natural disposition towards adopting and adapting foreign words, especially borrowed English terms, in the field of computer science and business without endangering its identity.

  15. Astronomical researches in Poincaré's and Romanian works

    NASA Astrophysics Data System (ADS)

    Stavinschi, M.; Mioc, V.

    2005-09-01

    Henri Poincaré was not only a honorary member of the Romanian Academy, but also an important collaborator of many Romanian mathematicians and astronomers. It is sufficient to mention Spiru Haret, the first doctor in mathematics at Sorbonne, or Nicolae Coculescu, the first director of the Astronomical Observatory of Bucharest. The 150th anniversary of the birth of the illustrious French personality offered us a good opportunity to study the relations he and two other Poincaré, Raymond and Lucien, had with Romania.

  16. The Romanian privilege in French medicine and anti-Semitism.

    PubMed

    Evleth, D

    1998-08-01

    This paper reviews a special privilege given to Romanian medical students over other foreign medical students coming to study in France from the 1850s to the 1930s. It shows how, because of changing circumstances in Romania itself, this privilege evolved from benefiting small numbers of Christian students, who generally returned home after their studies, to benefiting large numbers of Jewish students, many of whom remained in France to practise medicine. It also shows how this evolution fed into medical anti-Semitism in France which discriminated specifically against these Romanian students as Jews, a phenomenon which was distinct from the French medical xenophobia directed against all foreign students. PMID:11620428

  17. Analysis of some Romanian fruit juices by ICP-MS

    NASA Astrophysics Data System (ADS)

    Dehelean, A.; Magdas, D. A.

    2013-11-01

    The present study was carried out to evaluate the heavy metal content of 21 Romanian single strength fruit (plum, apple, sour cherry) juices. The samples were collected from five Romanian areas namely: Alba, Maramures, Cluj, Salaj and Moldova. The results indicated macro (Na, Mg, Ca, P) and micro (Fe, Zn, Ni, Cr, Cd, Pb, etc) elements in the selected samples. The determination was performed by ICP-MS. Our results for fruit juice were compared with allowable limits for drinking water in the United Kingdom (NS30).

  18. Assessment results of the Indonesian TRIGA SNF to be shipped to INEEL

    SciTech Connect

    Jefimoff, J.; Robb, A.K.; Wendt, K.M.; Syarip, I.; Alfa, T.

    1997-10-09

    This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination performed by technical personnel from the Idaho National Engineering and Environmental Laboratory (INEEL) at the Bandung and Yogyakarta research reactor facilities in Indonesia. The examination was required before the SNF would be accepted for transportation to and storage at the INEEL. This paper delineates the Initial Preparations prior to the Indonesian foreign research reactor (FRR) fuel examination. The technical basis for the examination, the TRIGA SNF Acceptance Criteria, and the physical condition required for transportation, receipt and storage of the TRIGA SNF at the INEEL is explained. In addition to the initial preparations, preparation descriptions of the Work Plan For TRIGA Fuel Examination, the Underwater Examination Equipment used, and personnel Examination Team Training are included. Finally, the Fuel Examination and Results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. Lessons learned from all the activities completed to date is provided in an addendum. The initial preparations included: (1) coordination between the INEEL, FRR or Badan Tenaga Atom Nasional (BATAN), DOE-HQ, and the US State Department and Embassy; (2) incorporating Savannah River Site (SRS) FRR experience and lessons learned; (3) collecting both FRR facility and spent fuel data, and issuing a radionuclide report (Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels) needed for transportation and fuel acceptance at the INEEL; and (4) preexamination work at the research reactor for the fuel examination.

  19. Stable isotopes determination in some Romanian wines.

    PubMed

    Magdas, Dana Alina; Cuna, Stela; Cristea, Gabriela; Ionete, Roxana Elena; Costinel, Diana

    2012-06-01

    This paper presents a study concerning the isotopic fingerprint ((18)O and (13)C) of some wines prepared from relevant Romanian grape varieties (e.g. Feteasca Alba (FA), Feteasca Regala (FR) and Cabernet Sauvignon (CS)) obtained in different vintage years (2002, 2003, 2004, 2007 and 2008). These wines were obtained from different vineyards having a significant role in the wine market: Cotesti, Tohani, Stefanesti, Aiud, Cotnari, Bucium, Murfatlar, Bujoru, Dragasani and Valea Calugareasca. Several observations related to the dependence of isotope ratios on geographical origin and climatic conditions were drawn. The authentic wines obtained from the FA grape variety from six different vineyards showed δ(18)O values in the range of+3.28 (Cotesti region - 45 °38'N/27 °04'E) to-2.60 ‰ (Aiud region - 46 °19'N/23 °45'E). The δ(13)C values were very similar for all the samples with an average of about-26 ‰. The difference between the δ(18)O values was due to the different climatic zones, which have an influence on the δ(18)O values of wine water. For the wine variety CS obtained from the Dealu Mare-Tohani vineyard, production years 2003 and 2004, a greater difference in the δ(18)O values of wine water ranging from 1.89 (in 2004) to 5.35 ‰ (in 2003) was noted. This difference is explained by the different mean annual temperatures in 2003 and 2004. PMID:22397311

  20. Reactor instrumentation renewal of the TRIGA reactor Vienna, Austria

    SciTech Connect

    Boeck, H.; Weiss, H.; Hood, W.E.; Hyde, W.K.

    1992-07-01

    The TRIGA Mark-II reactor at the Atominstitut in Vienna, Austria is replacing its twenty-four year old instrumentation system with a microprocessor based control system supplied by General Atomics. Ageing components, new governmental safety requirements and a need for state of the art instrumentation for training students has spurred the demand for new reactor instrumentation. In Austria a government appointed expert is assigned the responsibility of reviewing the proposed installation and verifying all safety aspects. After a positive review, final assembly and checkout of the instrumentation system may commence. The instrumentation system consists of three basic modules: the control system console, the data acquisition console and the NH-1000 wide range channel. Digital communications greatly reduce interwiring requirements. Hardwired safety channels are independent of computer control, thus, the instrumentation system in no way relies on any computer intervention for safety function. In addition, both the CSC and DAC computers are continuously monitored for proper operation via watchdog circuits which are capable of shutting down the reactor in the event of computer malfunction. Safety channels include two interlocked NMP-1000 multi-range linear channels for steady state mode, an NPP-1000 linear safety channel for pulse mode and a set of three independent fuel temperature monitoring channels. The microprocessor controlled wide range NM- 1000 digital neutron monitor (fission chamber based) functions as a startup/operational channel, and provides all power level related Interlocks. The Atominstitut TRIGA reactor is configured for four modes of operation: manual mode, automatic mode (servo control), pulsing mode and square wave mode. Control of the standard control rods is via stepping motor control rod drives, which offers the operator the choice of which control rods are operated by the servo system in automatic and square wave model. (author)

  1. New fuel management plan for the Penn State TRIGA

    SciTech Connect

    Hughes, D.; Boyle, P.; Levine, S.H.

    1996-12-31

    The Pennsylvania State University (PSU) Breazeale TRIGA has utilized 12 wt% U fuel in the core since July 1992, when six 12 wt% U fuel elements were loaded to replace the depleted 8.5 wt% U fuel in the centermost ring, the B ring. This reload increased the cold k{sub eff} from 1.03 to 1.05, the cold k{sub eff} of 1.03 being the minimum k{sub eff} that will permit 1-MW operation for a sustained period. In the next fuel reload, this 12 wt% U fuel is to be moved outward to the adjacent ring, the C ring, and six fresh 12 wt% U fuel elements are to be added to the B ring. It was determined that using the 12 wt% U in place of 8.5 wt% U fuel reduced fuel costs by a factor of 6, and continuing this use of six 12 wt% U fuel elements for each reload maintained the lower fuel costs. This reloading technique worked successfully, requiring only 26 additional 12 wt% U elements to be loaded into the core during the last 23 yr. Recently, however, a new instrumented 12 wt% U fuel element read much higher temperatures than all previous similar fuel elements. Its measured fuel temperature at 1 MW is 585{degrees}C. As a result, the PSU TRIGA now operates at or below 60% full power to prevent this element from reaching fuel temperatures well above 500{degrees}C. The purpose of this paper is to describe a new fuel management strategy developed to use 12 wt% U fuel, which permits 1-MW operation and limits the maximum fuel temperature to {approx}500{degrees}C.

  2. Tri-Gas Pressurization System Testing and Modeling for Cryogenic Applications

    NASA Technical Reports Server (NTRS)

    Taylor, B.; Polsgrove, R.; Stephens, J.; Hedayat, A.

    2014-01-01

    The use of Tri-gas in rocket propulsion systems is somewhat of a new technology. This paper defines Tri-gas as a mixture of gases composed largely of helium with a small percentage of a stoichiometric mixture of hydrogen and oxygen. When exposed to a catalyst the hydrogen and oxygen in the mixture combusts, significantly raising the temperature of the mixture. The increase in enthalpy resulting from the combustion process significantly decreases the required quantity of gas needed to pressurize the ullage of the vehicle propellant tanks. The objective of this effort was to better understand the operating characteristics of Tri-gas in a pressurization system with low temperature applications. In conjunction with ongoing programs at NASA Marshall Space Flight Center, an effort has been undertaken to evaluate the operating characteristics of Tri-gas through modeling and bench testing. Through improved understanding of the operating characteristics, the risk of using this new technology in a launch vehicle propulsion system was reduced. Bench testing of Tri-gas was a multistep process that targeted gas characteristics and performance aspects that pose a risk to application in a pressurization system. Pressurization systems are vital to propulsion system performance. Keeping a target ullage pressure in propulsions tanks is necessary to supply propellant at the conditions and flow rates required to maintain desired engine functionality. The first component of testing consisted of sampling Tri-gas sources that had been stagnant for various lengths of time in order to determine the rate at which stratification takes place. Second, a bench test was set up in which Tri-gas was sent through a catalyst bed. This test was designed to evaluate the performance characteristics of Tri-gas, under low temperature inlet temperatures, in a flight-like catalyst bed reactor. The third, most complex, test examined the performance characteristics of Tri-gas at low temperature temperatures

  3. Individualism and collectivism: what differences between Portuguese and Romanian adolescents?

    PubMed

    Ciochină, Laura; Faria, Luísa

    2009-11-01

    This article presents the results of a series of preliminary comparisons, between the Portuguese and Romanian cultural contexts, on the individualism-collectivism (IND/COL) cultural dimension. The IND/COL was evaluated with the Individualism-Collectivism Questionnaire - ICQ -, constructed in New Zealand by Shulruf, Hattie and Dixon (2003, Anonymous Questionnaire of Self-Attitudes - AQSA), and adapted to the Portuguese and Romanian contexts by Ciochină and Faria (2007), using studies of confirmatory factor analysis. The ICQ composed by 26 items, 15 evaluating the IND scale--with three subscales (Uniqueness, Competition and Responsibility)--, and 11 evaluating the COL scale--with two subscales (Harmony and Advice)--, was administered to 395 subjects, 200 Portuguese and 195 Romanian, 10th and 12th graders. On the whole, in the Portuguese and Romanian samples, the multivariate and univariate statistical analyses evidenced the existence of two independent variables--gender and cultural context--, with significant effects, main and of interaction, on the scales and subscales of the ICQ. The results were discussed taking into consideration the specificities of the educational systems in the two cultural contexts, which are inevitably shaped by socio-cultural factors characteristic of the two countries considered in the present study--Portugal and Romania. PMID:19899656

  4. Exploring Sources of Variation in Romanian Science Achievement

    ERIC Educational Resources Information Center

    Istrate, Olimpius; Noveanu, Gabriela; Smith, Thomas M.

    2006-01-01

    The shift from a centrally-controlled to a market-oriented economy in the early 1990s put pressure on the Romanian education system to reform both the curriculum and methods of instruction employed in primary and secondary education. At least part of the pressure to implement educational reforms came from the relatively poor performance of…

  5. Loss of Infinitival Complementation in Romanian Diachronic Syntax

    ERIC Educational Resources Information Center

    Jordan, Maria

    2009-01-01

    For the most part, my study is a descriptive analysis of infinitival complement clauses and the corresponding subjunctive clauses in Romanian, that is, obligatory control (OC) structures. OC is a relation of obligatory coreferentiality between a matrix argument (controller) and the null subject of the subordinate (controlee) of the same sentence.…

  6. Fit for a Purpose? The Romanian System of VET

    ERIC Educational Resources Information Center

    West, John; Serban, Madlen

    2007-01-01

    The Romanian system of initial vocational education and training is examined from three different points of view: its relevance to the labour market; its relationship with other parts of the national education system; and its evolution from the past to the future. While there are some major current mismatches between the school system and the…

  7. Post-Institutional Autistic Syndrome in Romanian Adoptees

    ERIC Educational Resources Information Center

    Hoksbergen, Rene; ter Laak, Jan; Rijk, Kathinka; van Dijkum, Cor; Stoutjesdijk, Felicia

    2005-01-01

    Romanian adoptees have a background of severe neglect. International research has shown that this can give rise to symptoms of autistic behavior. Rutter "et al." (1999, "Journal of Child Psychology Psychiatry," 40 (4), 537-549.) refers to "quasi-autistic patterns", and Federici (1998, "Help for the hopeless child: A guide for families."…

  8. Development of Professional Identity in Romanian Business Students

    ERIC Educational Resources Information Center

    Glaser-Segura, Daniel A.; Mudge, Suzanne; Bratianu, Constantin; Dumitru, Ionela

    2010-01-01

    Purpose: This study aims to focus on the role of learning activities on the development of Romanian students making the change from academia to the workplace, specifically focusing on the role of three learning activities: classroom teaching pedagogies ("in-vitro"); field experiences ("in-situ"); and self-development experiential activities.…

  9. Romanians Abroad: A Snapshot of Highly Skilled Migration

    ERIC Educational Resources Information Center

    Ferro, Anna

    2004-01-01

    This paper is about the experience of labour migration among skilled Romanians, mainly Information Technology workers and highly qualified researchers. It is based on a questionnaire survey where, among other elements, the researcher investigated the push-pull aspects of qualified migration and the strategies of labour migration. This paper…

  10. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-28

    ... COMMISSION Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115... No. R-115, for the University of Illinois Advanced TRIGA Reactor (ATR). The NRC has terminated the..., Facility Operating License No. R-115 is terminated. The above referenced documents may be examined,...

  11. New records of Protura (Entognatha, Arthropoda) from Romania, with an identification key to the Romanian species

    PubMed Central

    Shrubovych, Julia; Fiera, Cristina

    2016-01-01

    Abstract The Romanian Protura were studied based on 175 specimens collected from Romania, along with bibliographic data. The main publication on the Romanian proturans was written by M.A. Ionescu (1951), who described 13 species mainly from soil and forest litter from 15 collecting points. The current paper represents the first study at a national level. Faunal data on Protura were obtained from 22 sites, mostly from forests of the Romanian Carpathians and also from a peri-urban area of Bucharest, which had not been studied before. As a result, the Romanian Protura fauna now consists of 27 known taxa in 6 genera and 4 families. Of the 27 taxa, 15 species are new records for Romanian fauna. An identification key to the Romanian Protura species is provided. PMID:26865814

  12. New records of Protura (Entognatha, Arthropoda) from Romania, with an identification key to the Romanian species.

    PubMed

    Shrubovych, Julia; Fiera, Cristina

    2016-01-01

    The Romanian Protura were studied based on 175 specimens collected from Romania, along with bibliographic data. The main publication on the Romanian proturans was written by M.A. Ionescu (1951), who described 13 species mainly from soil and forest litter from 15 collecting points. The current paper represents the first study at a national level. Faunal data on Protura were obtained from 22 sites, mostly from forests of the Romanian Carpathians and also from a peri-urban area of Bucharest, which had not been studied before. As a result, the Romanian Protura fauna now consists of 27 known taxa in 6 genera and 4 families. Of the 27 taxa, 15 species are new records for Romanian fauna. An identification key to the Romanian Protura species is provided. PMID:26865814

  13. An analysis of decommissioning costs for the AFRRI TRIGA reactor facility

    SciTech Connect

    Forsbacka, Matt

    1990-07-01

    A decommissioning cost analysis for the AFRRI TRIGA Reactor Facility was made. AFRRI is not at this time suggesting that the AFRRI TRIGA Reactor Facility be decommissioned. This report was prepared to be in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations which requires the assurance of availability of future decommissioning funding. The planned method of decommissioning is the immediate decontamination of the AFRRI TRIGA Reactor site to allow for restoration of the site to full public access - this is called DECON. The cost of DECON for the AFRRI TRIGA Reactor Facility in 1990 dollars is estimated to be $3,200,000. The anticipated ancillary costs of facility site demobilization and spent fuel shipment is an additional $600,000. Thus the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for this cost estimate is a study of the decommissioning costs of a similar reactor facility that was performed by Battelle Pacific Northwest Laboratory (PNL) as provided in USNRC publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA. (author)

  14. Neutron and gamma radiography of UO{sub 2} and TRIGA fuel elements

    SciTech Connect

    Robinson, A.H.; Gao, Y.C.; Johnson, A.G.; Ringle, J.C.

    1982-07-01

    The Oregon State TRIGA Reactor neutron radiography facility has been used to produce both neutron and gamma radiographs of reactor fuel. In this paper a comparison of the applicability of neutron and gamma radiography to both UO{sub 2} fuel pins and TRIGA fuel elements is made. In the case of UO{sub 2} fuel, conventional thermal neutron radiography produces excellent quality radiographs. These radiographs may be used to detect various defects in the fuel such as enrichment differences, cracks, end-capping, inclusions, etc. For TRIGA fuel elements, conventional thermal neutron radiography will not show the internal structure. This is due to the high hydrogen content of the fuel. These elements are typically 8.5 w/o uranium in Zr-H{sub 1.7}; the density of hydrogen in the fuel being about 80 percent that of water. Further, while epithermal radiography significantly improves the radiographs, defects may go undetected. As an alternative to neutron radiography, high energy gamma radiographs of TRIGA fuel elements have been taken using the same facility. The gamma spectrum emitted by the reactor core is sufficiently high in energy that very good radiographs may be obtained with this technique. These radiographs show excellent detail for the internal structure of the TRIGA fuel. (author)

  15. Thermal hydraulics modeling of the US Geological Survey TRIGA reactor

    NASA Astrophysics Data System (ADS)

    Alkaabi, Ahmed K.

    The Geological Survey TRIGA reactor (GSTR) is a 1 MW Mark I TRIGA reactor located in Lakewood, Colorado. Single channel GSTR thermal hydraulics models built using RELAP5/MOD3.3, RELAP5-3D, TRACE, and COMSOL Multiphysics predict the fuel, outer clad, and coolant temperatures as a function of position in the core. The results from the RELAP5/MOD3.3, RELAP5-3D, and COMSOL models are similar. The TRACE model predicts significantly higher temperatures, potentially resulting from inappropriate convection correlations. To more accurately study the complex fluid flow patterns within the core, this research develops detailed RELAP5/MOD3.3 and COMSOL multichannel models of the GSTR core. The multichannel models predict lower fuel, outer clad, and coolant temperatures compared to the single channel models by up to 16.7°C, 4.8°C, and 9.6°C, respectively, as a result of the higher mass flow rates predicted by these models. The single channel models and the RELAP5/MOD3.3 multichannel model predict that the coolant temperatures in all fuel rings rise axially with core height, as the coolant in these models flows predominantly in the axial direction. The coolant temperatures predicted by the COMSOL multichannel model rise with core height in the B-, C-, and D-rings and peak and then decrease in the E-, F-, and G-rings, as the coolant tends to flow from the bottom sides of the core to the center of the core in this model. Experiments at the GSTR measured coolant temperatures in the GSTR core to validate the developed models. The axial temperature profiles measured in the GSTR show that the flow patterns predicted by the COMSOL multichannel model are consistent with the actual conditions in the core. Adjusting the RELAP5/MOD3.3 single and multichannel models by modifying the axial and cross-flow areas allow them to better predict the GSTR coolant temperatures; however, the adjusted models still fail to predict accurate axial temperature profiles in the E-, F-, and G-rings.

  16. Interpretation of TRIGA reactivity transients with RELAP5/PARCS coupled-code

    SciTech Connect

    Bandini, G.; Meloni, P.; Polidori, M.

    2006-07-01

    In the frame of future experiments to carried out upon TRIGA reactors, which aim to verify the real feasibility of the ADS (Accelerator Driven System) concept, it is essential to build a numerical tool able to simulate the dynamic behaviour of the reactor in subcritical configuration. This model developed to support the design of subcritical experiments and the safety analysis of the reactor, as a first step has to be assessed against the experimental data available for the critical reactor. To this purpose the thermal-hydraulic/ neutronic numerical model based on the RELAP5/PARCS coupled-code is been tested against the experimental reactivity transients conducted on the RC1-TRIGA reactor at the ENEA Casaccia Research Center in forecast of the TRADE (TRIGA Accelerator Driven Experiment) subcritical experience. The results of the calculations already performed show a qualitative good agreement with the experimental data and allow to address the future developments and improvements of the numerical model. (authors)

  17. A Romanian therapeutic approach to peripheral nerve injury.

    PubMed

    Zegrea, I; Chivu, Laura Ioana; Albu, Mădălina Georgiana; Zamfirescu, D; Chivu, R D; Ion, Daniela Adriana; Lascăr, I

    2012-01-01

    The study of nerve regeneration and functional recovery of the injured peripheral nerves represents a worldwide subject of clinical and scientific research. Our team aimed to obtain the first guide for nerve regeneration, bioartificial and biodegradable, using exclusively Romanian resources and having the advantages of price and quality, over the imported nerve conduits already used in clinical practice. First steps of this project consisted in obtaining the prototype of nerve guide conduit and its' testing in vitro and in vivo. Tests of physicochemical characterization, FTIR (Fourier Transform Infrared) spectrometry, thermal analysis (differential calorimetry, thermo-gravimetry), electron microscopy, water absorption and enzymatic degradation of the obtained prototype were followed by in vivo testing. The first results, obtained on a group of Brown Norway rats who suffered experimental lesions of 1 cm at the level of left sciatic nerve, which have then been repaired using the Romanian conduit prototype, are favorable in terms of biocompatibility, biodegradable capacity and support of nerve regeneration. PMID:22732806

  18. The frequency of HLA alleles in the Romanian population.

    PubMed

    Constantinescu, Ileana; Boșcaiu, Voicu; Cianga, Petru; Dinu, Andrei-Antoniu; Gai, Elena; Melinte, Mihaela; Moise, Ana

    2016-03-01

    Knowledge of human leukocyte antigen (HLA) allele frequencies is essential for bone marrow and kidney donor searches. The Romanian Caucasian population is heterogeneous and information on HLA polymorphism has not been well studied. We characterized the HLA genetic profile and allele frequencies of regional populations in Romania. HLA-A, B and DRB1 alleles were examined in 8252 individuals, belonging to the four main regions of Romania. The most common alleles found in the Romanian population are the following: HLA-A*01, A*02, A*03, A*11, A*24; HLA-B*18, B*35, B*44, B*51 and HLA-DRB1*01, DRB1*03, DRB1*07, DRB1*11, DRB1*13, DRB1*15, DRB1*16. More than half of the alleles are non-homogeneously spread in Romania. These results provide a starting point for future analyses of genetic heterogeneity in Romania. PMID:26711124

  19. TRIGA Mark II Criticality Benchmark Experiment with Burned Fuel

    SciTech Connect

    Persic, Andreja; Ravnik, Matjaz; Zagar, Tomaz

    2000-12-15

    The experimental results of criticality benchmark experiments performed at the Jozef Stefan Institute TRIGA Mark II reactor are presented. The experiments were performed with partly burned fuel in two compact and uniform core configurations in the same arrangements as were used in the fresh fuel criticality benchmark experiment performed in 1991. In the experiments, both core configurations contained only 12 wt% U-ZrH fuel with 20% enriched uranium. The first experimental core contained 43 fuel elements with average burnup of 1.22 MWd or 2.8% {sup 235}U burned. The last experimental core configuration was composed of 48 fuel elements with average burnup of 1.15 MWd or 2.6% {sup 235}U burned. The experimental determination of k{sub eff} for both core configurations, one subcritical and one critical, are presented. Burnup for all fuel elements was calculated in two-dimensional four-group diffusion approximation using the TRIGLAV code. The burnup of several fuel elements was measured also by the reactivity method.

  20. The scientific activity of the Romanian Astronomical Society during 1992

    NASA Astrophysics Data System (ADS)

    Alexescu, Matei

    1992-04-01

    The author is overviewing the main activities of the members of the Romanian Astronomical Society during 1992. The main goals include: 1)Observations of solar spots, 2)Proper motions inside solar spots groups, 3)Observations of Mars,Jupiter and Saturn, 4)Photometric and astrometric observations of the asteroid 3674 ERBIS-BUEUL (the work to be given by the Astronomical Institute), 5)Observations of meteors (SARM)

  1. Behavior of 12 wt% TRIGA fuel after many years of operation

    SciTech Connect

    Levine, S.H.; Boyle, P.

    1997-12-01

    In July 1972, six 12 wt% Uzr-H TRIGA fuel elements were loaded into the B-ring, the innermost ring, of the Penn State Breazeale Research Reactor (PSBR) to increase its k{sub eff}. Of these initial six fuel elements, three remain in the core, and the other three fuel elements had to be removed from the core. The purpose of this summary is to present operational-type data on the 12 wt% Uzr-H TRIGA fuel elements that have been in the PSBR during the past 25 yr and to postulate reasons for the structural change of those removed from the core.

  2. TRIGA Mark II benchmark experiment; Part I: Steady-state operation

    SciTech Connect

    Mele, I.; Ravnik, M.; Trkov, A. )

    1994-01-01

    The experimental results of startup tests after reconstruction and modification of the TRIGA Mark II reactor in Ljubljana are presented. The experiments were performed with a completely fresh, compact, and uniform core. The operating conditions were well defined and controlled, so that the results can be used as a benchmark test case for TRIGA reactor calculations. Both steady-state and pulse mode operation were tested. In this paper, the following steady-state experiments are treated: critical core and excess reactivity, control rod worths, fuel element reactivity worth distribution, fuel temperature distribution, and fuel temperature reactivity coefficient.

  3. Neutron fluence and energy reproducibility of a 2-dollar TRIGA reactor Pulse

    SciTech Connect

    Payne, Rosara F.; Drader, Jessica A.; Friese, Judah I.; Greenwood, Lawrence R.; Hines, Corey C.; Metz, Lori A.; Kephart, Jeremy D.; King, Matthew D.; Pierson, Bruce D.; Smith, Jeremy D.; Wall, Donald E.

    2009-10-01

    Washington State University’s 1 MW TRIGA reactor has a long history of utilization for neutron activation analysis (NAA). TRIGA reactors have the ability to pulse, reach supercritical (k>1) for short bursts of time. At this high power and fast time the energy spectrum and neutron fluence are largely uncharacterized. The pulse neutron energy spectrum and fluence were determined by the activation of Cu, Au, Co, Fe, and Ti. These analyses were completed with and without Cd shielding to determine reproducibility between pulses. The applications and implications of the neutron energy and fluence reproducibility to the use of pulsed NAA will be discussed.

  4. The Romanian-English Contrastive Analysis Project; Contrastive Studies in Phonetics and Phonology, Vol. 4.

    ERIC Educational Resources Information Center

    Center for Applied Linguistics, Arlington, VA.

    The fourth volume in this series contains nine contrastive studies in phonetics and phonology. They are: "Remarks on the Physical Manifestation of Internal Open Juncture in the English of Romanians," by Andrei Avram; "The Back Vowels of Romanian and English--A Contrastive Study," by Laurentia Dascalu; "Remarks on the English Diphthongs and…

  5. Quality Improvement of Business Education in Romanian Universities: The Student as Customer and Client

    ERIC Educational Resources Information Center

    Glaser-Segura, Daniel A.; Mudge, Suzanne; Bratianu, Constantin; Jianu, Ionela; Valcea, Sorin

    2007-01-01

    This study frames the quality transition of Romanian business education embracing the role of students as clients and customers. In the first part of the study, responses from ninety-four fourth-year Romanian students provided a statistically significant gap between the level of importance of business competences and their level of preparation.…

  6. Comparative Study on Romanian School Science Curricula and the Curriculum of TIMSS 2007 Testing

    ERIC Educational Resources Information Center

    Ciascai, Liliana

    2009-01-01

    The results of Romanian school students in Science PISA and TIMSS testings have been and continue to be systematically slack. In the present paper we intend to do a comparative analysis of Science curriculum TIMSS 2007 and Romanian Science school curricula of 4th and 8th grades. This analysis, based on Bloom's taxonomy of cognitive domain,…

  7. Romanian, Spanish and US Secondary Science Teacher Perceptions of Threats to the Biosphere

    ERIC Educational Resources Information Center

    Robinson, Michael; Naumescu, Adrienne Kozan; Ives, Bob

    2009-01-01

    This paper presents the data from a current study involving 41 Romanian secondary science teachers and a previously published study that compared 89 Spanish and 42 US secondary science teachers. All three groups were convenience samples who answered a two part questionnaire that was given in English, Spanish or Romanian, depending on the sample.…

  8. The Holocaust as Reflected in Communist and Post-Communist Romanian Textbooks

    ERIC Educational Resources Information Center

    Barbulescu, Ana; Degeratu, Laura; Gusu, Cosmina

    2013-01-01

    Romanian history textbooks were mostly silent about the Holocaust during the Communist era. The authors reconstructed the different models of remembering the Holocaust that are present in post-Communist Romanian textbooks. The analysis revealed the existence of six different models of recollecting this history. The six models of representing the…

  9. East European Linguistics Studies Project No. 3: The Development of Romanian Grammar Pamphlets.

    ERIC Educational Resources Information Center

    Augerot, James E., Ed.

    This report contains 10 chapters, each of which deals with a particular Romanian grammatical category and exercises. The texts are intended for use by the continuing student with some knowledge of basic Romanian. Areas covered include determiners, intonation and stress, verb conjugation, prepostions, possessive and dative cases, pronouns, syntax,…

  10. An Integrated Marine Propulsion System Utilising TRIGA{sup TM} Fuel

    SciTech Connect

    Manach, G.; Monnez, J-P.; Freeman, M.J.; Newell, A.; Brushwood, J.M.; Thompson, A.; Collins, C.; Scholes, N.; Hamilton, P.J.; Beeley, P.A.

    2004-07-01

    This paper describes the reactor physics, shielding, thermal hydraulics, reactor dynamics and safety studies conducted to develop a proposed Integrated Marine Propulsion System (IMPS) utilising TRIGA{sup TM} type uranium zirconium hydride fuel. The study has demonstrated that the IMPS plant is feasible and meets the design safety principles and safety criteria imposed on the study. (authors)

  11. 10. biennial U.S. TRIGA users' conference. Papers and abstracts

    SciTech Connect

    1986-07-01

    The conference cover the following main topics for TRIGA reactors: reactor instrumentation and measurements of reactor parameters, reactor operation and modifications, design innovation and service works, fast neutron spectrum, fuel examination, neutron flux, heat transfer, accidents analysis, corrosion problems, fuel failures and fuel management, mechanical problems and maintenance.

  12. A combined gamma scanning and optical inspection system for spent TRIGA fuel

    SciTech Connect

    Boeck, H.; Allmer, G.

    1990-07-01

    A multipurpose lead container is used to investigate both the burn-up and the mechanical condition of standard TRIGA fuel elements. Especially in view of ageing reactor cores, this equipment is important to determine the further use of a specific fuel element and, therefore, saves operational costs.

  13. 11. biennial U.S. TRIGA users' conference. Papers and abstracts

    SciTech Connect

    1988-07-01

    The Conference was devoted to different aspects of TRIGA reactors design, operation and applications. The main topics concerned fuel elements, control rod drive system; modelling of corrosion damage and other chemical and material studies; neutron flux measurements and spectrum; irradiation devices; fuel element failures; neutron radiography etc.

  14. The U-ZrH{sub x} alloy: Its properties and use in TRIGA fuel

    SciTech Connect

    Simnad, M.T.

    1980-07-01

    The uranium-zirconium-hydride fuel is an integral fuel-moderator system. Development of the UZr-hydride fuel technology has been under way at General Atomic since 1957. During this period over 6000 fuel elements have been fabricated for the TRIGA reactors. Over 25,000 pulses have been performed with the TRIGA fuel elements at General Atomic. The TRIGA fuel was developed around the concept of inherent safety. The development and the characteristics of the TRIGA fuels are described in this paper. The fabrication techniques have been developed to the point where the production of fuel bodies containing controlled amounts of hydrogen and burnable poison (erbium) has been carried out in sizes up to 1.5 in. in diameter. The instrumented fuel elements have been designed to determine the temperatures in the fuels and claddings and to record the gas pressures in the fuel elements, under both steady- state and pulsed operations. The physical, mechanical and corrosion properties of the fuel are presented, along with empirical correlations relating irradiation behavior and fission product retention to temperature, composition, burnup, and neutron flux and fluence. (author)

  15. Analysis of decommissioning costs for the AFRRI TRIGA reactor facility. Technical report

    SciTech Connect

    Forsbacka, M.; Moore, M.

    1989-12-01

    This report provides a cost analysis for decommissioning the Armed Forces Radiobiology Research Institute (AFRRI) TRIGA reactor facility. AFRRI is not suggesting that the AFRRI TRIGA reactor facility be decommissioned. This report was prepared in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations, which requires that funding for the decommissioning of reactor facilities be available when licensed activities cease. The planned method of decommissioning is complete decontamination (DECON) of the AFRRI TRIGA reactor site to allow for restoration of the site to full public access. The cost of DECON in 1990 dollars is estimated to be $3,200,000. The anticipated ancillary costs of facility site demobilization and spent fuel shipment will be an additional $600,000. Thus, the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for developing this cost estimate was a study of the decommissioning costs of similar reactor facility performed by Battelle Pacific Northwest Laboratory, as provided in U.S. Nuclear Regulatory Commission publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA reactor facility.

  16. Solar eclipses recorded in old Romanian chronicles and notes

    NASA Astrophysics Data System (ADS)

    Stavinschi, Magda; Mioc, Vasile; Débarbat, Suzanne

    Many solar eclipses observed trough history on Romanian territory have been recorded by the witnesses in chronicles and notes. About 100 such records, covering five hundred years (between 1.I.1386 and 6.III.1867), were collected and the respective eclipses were identified. There are records to be noted for the beautiful description of the phenomenon (6.III.1867). There are also records which prove a remarkable accuracy as regards the moments of the eclipse (5.IX.1793, 19.XI.1816). The importance of the latter for astronomy is obvious. Many records provide rich details about various characteristic aspects: the evolution of the phenomenon during the partial eclipse (25.VII.1748, 11.II.1804), the apparition of the stars in the sky during the totality phase (17.VI.1433, 12.VIII.1654, 25.VII.1748), sight damage affecting the imprudent spectators (22.VI.1656), the reactions of the spectators: fright, collective panic (23.IX.1699). Lots of records connect the celestial event with terrestrial calamities, natural (earthquakes, plague, invasions of grasshoppers, floods) or social (wars, kingdom changes). The solar eclipses of 16.III.1485, 12.VIII.1654, 12.V.1706, 28.VII.1851 constitute such examples. Finally, there are records which prove the astronomical cares of certain scientists of the time. For instance, three eclipses which occurred in 1628 (6.I, 1.VII, 24.XII), all invisible in Romania, were recorded by a Romanian 17th century scientist, Stefan Bachner, on the corresponding pages of a calendar for 1559. All these records prove that the celestial phenomena benefitted from particular and constant interest from the Romanian people throughout their history.

  17. Slovenian-Romanian bilateral intercomparison on tritium samples.

    PubMed

    Glavič-Cindro, D; Varlam, C; Faurescu, D; Vagner, I; Logar, J Kožar

    2014-05-01

    A Slovenian laboratory from the Jožef Stefan Institute (JSI) and a Romanian laboratory from the National Research and Development Institute for Cryogenics and Isotopic Technologies (ICIT) performed bilateral intercomparisons of tritium determination in environmental samples. On the basis of the results, the measurement and analysis methods were compared. Comparability and traceability were confirmed with the results from international radioactivity proficiency test exercises organized by IAEA and NPL where both laboratories participated. New knowledge gained leads to harmonized, precise and traceable results of low level tritium environmental samples measurements. PMID:24332881

  18. Fragmented Romanian Sociology: Growth and Structure of the Collaboration Network

    PubMed Central

    Hâncean, Marian-Gabriel; Perc, Matjaž; Vlăsceanu, Lazăr

    2014-01-01

    Structural patterns in collaboration networks are essential for understanding how new ideas, research practices, innovation or cooperation circulate and develop within academic communities and between and within university departments. In our research, we explore and investigate the structure of the collaboration network formed by the academics working full-time within all the 17 sociology departments across Romania. We show that the collaboration network is sparse and fragmented, and that it constitutes an environment that does not promote the circulation of new ideas and innovation within the field. Although recent years have witnessed an increase in the productivity of Romanian sociologists, there is still ample room for improvement in terms of the interaction infrastructure that ought to link individuals together so that they could maximize their potentials. We also fail to discern evidence in favor of the Matthew effect governing the growth of the network, which suggests scientific success and productivity are not rewarded. Instead, the structural properties of the collaboration network are partly those of a core-periphery network, where the spread of innovation and change can be explained by structural equivalence rather than by interpersonal influence models. We also provide support for the idea that, within the observed network, collaboration is the product of homophily rather than prestige effects. Further research on the subject based on data from other countries in the region is needed to place our results in a comparative framework, in particular to discern whether the behavior of the Romanian sociologist community is unique or rather common. PMID:25409180

  19. Romanian medical exposure to ionising radiation in 2012.

    PubMed

    Girjoaba, O; Cucu, A

    2015-07-01

    Medical exposure, the main source of artificial exposure, shows an increasing trend in the last years, manifested both by increasing the number of examinations with ionising radiation and by increasing the patient dose level. Annual results obtained for medical exposure to ionising radiation based on the data collected from Romanian hospitals are useful for the update of the national database and optimisation of diagnostic procedures in radiology and nuclear medicine. Medical exposure level is expressed in terms of annual collective dose and is evaluated from annual frequencies and the average effective dose per procedure for different types of radiological and nuclear medicine procedures. The Romanian hospitals reported during 2012 a number of 5,505,792 radiological examinations and 17,088 diagnostic procedures of nuclear medicine. Based on the data reported, the average effective doses and their contributions to the collective dose were evaluated. The main contributions to the collective dose of the radiological procedures are registered for CT abdomen and pelvis region, followed by thorax CT and head CT examinations. The next positions are fluoroscopic examination of the thorax and gastrointestinal disease and radiographic examination of the lumbar spine and thorax, which in spite of their low effective dose have an important contribution to the collective dose due to the large number of examinations. For nuclear medicine procedures, major contributions to collective dose are given by bone scintigraphy, followed by PET-CT and thyroid scintigraphy. PMID:25848102

  20. Present and perspectives in Romanian triticale breeding program.

    PubMed

    Ittu, Gheorghe; Saulescu, Nicolae; Ittu, Mariana; Mustatea, Pompiliu

    2014-01-01

    Triticale is grown in Romania, mainly, in the hilly regions on the acid poor fertile soils and covers, yearly, around 100-130 thousands ha or 1.5% from the arable land. Since 1971, when the breeding program has been started, up to present, it has been developed an adapted triticale germplasm for the Romanian environmental conditions and 12 new varieties have been registered. Genetic progress for yield, estimated over a 27 years, is by 46 kg ha(1) year(1) or 0.80% year(1), similarly with those realized in the most dynamic triticale breeding programs of the world. The improving of yields has been achieved by an increased number of kernels per spikes, plumpness of kernels, test weight and reduction of the plant height by introduction in the Romanian triticale germplasm of RhtB1b (Rht1) and Ddw1 (Hl) genes. The genetic gain for reduction of plant height, in this period, was estimated at 1.16 cm yr(1). Further progress regarding yield stability under conditions of global climatic changes, a broader genetic diversity for preharvest sprouting (PHS), drought tolerance, earliness, high canopy albedo, diseases resistance, especially for fusarium head blight (low DON content in kernels), leaf rust and BYDV, is required. PMID:26072586

  1. Genetic characterization of some Romanian red wine grapevine varieties

    NASA Astrophysics Data System (ADS)

    Ghetea, Ligia Gabriela; Motoc, Rozalia Magda; Niculescu, Ana-Maria; Litescu, Simona Carmen; Duma, Virgil-Florin; Popescu, Carmen Florentina

    2008-04-01

    In our study we have considered three of the most valuable Romanian red wine grapevine cultivars: Feteasca neagra, Feteasca alba and Novac. We have chosen to study grapevine because grapes and wine are an important part of a healthy diet, and because red grapes have the highest content of proanthocyanidins, that act as antioxidants (free radical scavengers) in the human body. Proanthocyanidins possess anti-mutagenic, anti-tumor, anti-viral activities and they present many other confirmed or potential benefits. Genotyping method was applied in order to asses the genetic profile at 14 microsatellite loci, for two cultivars: Feteasca neagra and Feteasca alba. In order to achieve this, the HPLC-DAD method was used. The content of anthocyans in grape skin from two cultivars - Feteasca neagra and Novac - was measured. Microsatellite markers have been certified as powerful tools for assessing genetic identities and genetic relationships between grapevine gene pools. Genetic characterization of grapevine cultivars can certify their authenticity and purity, two features that have a direct effect on the quality and value of the finished product, the wine. In our country, this is the first attempt in order to establish a genetic profile for valuable Romanian origin grapevine varieties. In some of the 14 microsatellitic loci, Feteasca neagra and Feteasca alba cultivars presented allele size variants different from the values cited in the literature, proving that these cultivars belong to a geographical distinct gene pool. The content of anthocyans in Feteasca neagra grape skin was significantly higher than in Novac.

  2. Performance of the solid deuterium ultra-cold neutron source at the pulsed reactor TRIGA Mainz

    NASA Astrophysics Data System (ADS)

    Karch, J.; Sobolev, Yu.; Beck, M.; Eberhardt, K.; Hampel, G.; Heil, W.; Kieser, R.; Reich, T.; Trautmann, N.; Ziegner, M.

    2014-04-01

    The performance of the solid deuterium ultra-cold neutron (UCN) source at the pulsed reactor TRIGA Mainz with a maximum peak energy of 10MJ is described. The solid deuterium converter with a volume of cm3 (8mol), which is exposed to a thermal neutron fluence of n/cm2, delivers up to 240000 UCN ( m/s) per pulse outside the biological shield at the experimental area. UCN densities of 10 cm3 are obtained in stainless-steel bottles of 10 L. The measured UCN yields compare well with the predictions from a Monte Carlo simulation developed to model the source and to optimize its performance for the upcoming upgrade of the TRIGA Mainz into a user facility for UCN physics.

  3. NASA Marshall Space Flight Center Tri-gas Thruster Performance Characterization

    NASA Technical Reports Server (NTRS)

    Dorado, Vanessa; Grunder, Zachary; Schaefer, Bryce; Sung, Meagan; Pedersen, Kevin

    2013-01-01

    Historically, spacecraft reaction control systems have primarily utilized cold gas thrusters because of their inherent simplicity and reliability. However, cold gas thrusters typically have a low specific impulse. It has been determined that a higher specific impulse can be achieved by passing a monopropellant fluid mixture through a catalyst bed prior to expulsion through the thruster nozzle. This research analyzes the potential efficiency improvements from using tri-gas, a mixture of hydrogen, oxygen, and an inert gas, which in this case is helium. Passing tri-gas through a catalyst causes the hydrogen and oxygen to react and form water vapor, ultimately heating the exiting fluid and generating a higher specific impulse. The goal of this project was to optimize the thruster performance by characterizing the effects of varying several system components including catalyst types, catalyst lengths, and initial catalyst temperatures.

  4. Natural and mixed convection in the cylindrical pool of TRIGA reactor

    NASA Astrophysics Data System (ADS)

    Henry, R.; Tiselj, I.; Matkovič, M.

    2016-05-01

    Temperature fields within the pool of the JSI TRIGA MARK II nuclear research reactor were measured to collect data for validation of the thermal hydraulics computational model of the reactor tank. In this context temperature of the coolant was measured simultaneously at sixty different positions within the pool during steady state operation and two transients. The obtained data revealed local peculiarities of the cooling water dynamics inside the pool and were used to estimate the coolant bulk velocity above the reactor core. Mixed natural and forced convection in the pool were simulated with a Computational Fluid Dynamics code. A relatively simple CFD model based on Unsteady RANS turbulence model was found to be sufficient for accurate prediction of the temperature fields in the pool during the reactor operation. Our results show that the simple geometry of the TRIGA pool reactor makes it a suitable candidate for a simple natural circulation benchmark in cylindrical geometry.

  5. Validation of neutron flux redistribution factors in JSI TRIGA reactor due to control rod movements.

    PubMed

    Kaiba, Tanja; Žerovnik, Gašper; Jazbec, Anže; Štancar, Žiga; Barbot, Loïc; Fourmentel, Damien; Snoj, Luka

    2015-10-01

    For efficient utilization of research reactors, such as TRIGA Mark II reactor in Ljubljana, it is important to know neutron flux distribution in the reactor as accurately as possible. The focus of this study is on the neutron flux redistributions due to control rod movements. For analyzing neutron flux redistributions, Monte Carlo calculations of fission rate distributions with the JSI TRIGA reactor model at different control rod configurations have been performed. Sensitivity of the detector response due to control rod movement have been studied. Optimal radial and axial positions of the detector have been determined. Measurements of the axial neutron flux distribution using the CEA manufactured fission chambers have been performed. The experiments at different control rod positions were conducted and compared with the MCNP calculations for a fixed detector axial position. In the future, simultaneous on-line measurements with multiple fission chambers will be performed inside the reactor core for a more accurate on-line power monitoring system. PMID:26141293

  6. Analysis of safety limits of the Moroccan TRIGA MARK II research reactor

    NASA Astrophysics Data System (ADS)

    Erradi, L.; Essadki, H.

    2001-06-01

    The main objective of this study is to check the ability of the Moroccan TRIGA MARK II research reactor, designed to use natural convection cooling, to operate at its nominal power (2 MW) with sufficient safety margins. The neutronic analysis of the core has been performed using Leopard and Mcrac codes and the parameters of interest were the power distributions, the power peaking factors and the core excess reactivity. The thermal hydraulic analysis of the TRIGA core was performed using the French code FLICA designed for transient and study state situations. The main safety related parameters of the core have been evaluated with special emphasises on the following: maximum fuel temperature, minimum DNBR and maximum void fraction. The obtained results confirm the designer predictions except for the void fraction.

  7. Transport model based on three-dimensional cross-section generation for TRIGA core analysis

    SciTech Connect

    Kriangchaiporn, N.; Ivanov, K.; Haghighat, A.; Sears, C. F.

    2006-07-01

    The development of a three-dimensional (3-D) transport model for TRIGA core analysis based on the discrete ordinates (S{sub n}) method has been conducted. The effective fine- and broad- group structures for the TRIGA cross-section libraries were selected based on CPXSD (Contribution and Point-wise Cross-Section Driven) methodology. Different 3-D pin/core configurations are used to verify and validate the selected effective group structures. Thirteen-group structure was finally selected to be used for core analysis. The results agree with continuous energy cross-section Monte Carlo calculations for eigenvalues and normalized pin power distributions, which are used as a reference in this research. (authors)

  8. Experimental power density distribution benchmark in the TRIGA Mark II reactor

    SciTech Connect

    Snoj, L.; Stancar, Z.; Radulovic, V.; Podvratnik, M.; Zerovnik, G.; Trkov, A.; Barbot, L.; Domergue, C.; Destouches, C.

    2012-07-01

    In order to improve the power calibration process and to benchmark the existing computational model of the TRIGA Mark II reactor at the Josef Stefan Inst. (JSI), a bilateral project was started as part of the agreement between the French Commissariat a l'energie atomique et aux energies alternatives (CEA) and the Ministry of higher education, science and technology of Slovenia. One of the objectives of the project was to analyze and improve the power calibration process of the JSI TRIGA reactor (procedural improvement and uncertainty reduction) by using absolutely calibrated CEA fission chambers (FCs). This is one of the few available power density distribution benchmarks for testing not only the fission rate distribution but also the absolute values of the fission rates. Our preliminary calculations indicate that the total experimental uncertainty of the measured reaction rate is sufficiently low that the experiments could be considered as benchmark experiments. (authors)

  9. Verifying the Asymmetric Multiple Position Neutron Source (AMPNS) method using the TRIGA reactor

    SciTech Connect

    Kim, Soon-Sam; Leyine, S.H.

    1984-07-01

    A new experimental/analytical method has been developed using the Penn State Breazeale (TRIGA) reactor, to measure the k{sub eff} of a damaged core, e.g., the TMI-2 core, and unfold its k{sub infinity} distribution. This new method, the Asymmetric Multiple Position Neutron Source (AMPNS) method, uses the response of several neutron detectors in fixed positions around the core periphery (and possibly in the core) when a neutron source is placed sequentially in different discrete core positions. Experiments have been performed with the Penn State Breazeale TRIGA Reactor (PSBR) and analyzed with appropriate neutron calculations, using PSU-LEOPARD and EXTERMINATOR-II (EXT-II), to verify the method.

  10. Conceptual design of fuel transfer cask for Reactor TRIGA PUSPATI (RTP)

    NASA Astrophysics Data System (ADS)

    Muhamad, Shalina Sheik; Hamzah, Mohd Arif Arif B.

    2014-02-01

    Spent fuel transfer cask is used to transfer a spent fuel from the reactor tank to the spent fuel storage or for spent fuel inspection. Typically, the cask made from steel cylinders that are either welded or bolted closed. The cylinder is enclosed with additional steel, concrete, or other material to provide radiation shielding and containment of the spent fuel. This paper will discuss the Conceptual Design of fuel transfer cask for Reactor TRIGA Puspati (RTP).

  11. Production of {sup 99}Mo using LEU and molybdenum targets in a 1 MW Triga reactor

    SciTech Connect

    Mo, S.C.

    1993-12-31

    The production of {sup 99}Mo using Low Enriched Uranium (LEU) and natural molybdenum targets in a 1 MW Triga reactor is investigated. The successive linear programming technique is applied to minimize the target loadings for different yield constraints. The irradiation time is related to the kinetics of the growth and decay of {sup 99}Mo. The feasibility of a neutron generated based {sup 99}Mo production system is discussed.

  12. Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments.

    PubMed

    Ćalić, Dušan; Žerovnik, Gašper; Trkov, Andrej; Snoj, Luka

    2016-01-01

    The main aim of this paper is the development and validation of a 3D computational model of TRIGA research reactor using Serpent 2 code. The calculated parameters were compared to the experimental results and to calculations performed with the MCNP code. The results show that the calculated normalized reaction rates and flux distribution within the core are in good agreement with MCNP and experiment, while in the reflector the flux distribution differ up to 3% from the measurements. PMID:26516989

  13. Analysis of JSI TRIGA MARK II reactor physical parameters calculated with TRIPOLI and MCNP.

    PubMed

    Henry, R; Tiselj, I; Snoj, L

    2015-03-01

    New computational model of the JSI TRIGA Mark II research reactor was built for TRIPOLI computer code and compared with existing MCNP code model. The same modelling assumptions were used in order to check the differences of the mathematical models of both Monte Carlo codes. Differences between the TRIPOLI and MCNP predictions of keff were up to 100pcm. Further validation was performed with analyses of the normalized reaction rates and computations of kinetic parameters for various core configurations. PMID:25576735

  14. Fundamental approach to TRIGA steady-state thermal-hydraulic CHF analysis.

    SciTech Connect

    Feldman, E.; Nuclear Engineering Division

    2008-03-30

    Methods are investigated for predicting the power at which critical heat flux (CHF) occurs in TRIGA reactors that rely on natural convection for primary flow. For a representative TRIGA reactor, two sets of functions are created. For the first set, the General Atomics STAT code and the more widely-used RELAP5-3D code are each employed to obtain reactor flow rate as a function of power. For the second set, the Bernath correlation, the 2006 Groeneveld table, the Hall and Mudawar outlet correlation, and each of the four PG-CHF correlations for rod bundles are used to predict the power at which CHF occurs as a function of channel flow rate. The two sets of functions are combined to yield predictions of the power at which CHF occurs in the reactor. A combination of the RELAP5-3D code and the 2006 Groeneveld table predicts 67% more CHF power than does a combination of the STAT code and the Bernath correlation. Replacing the 2006 Groeneveld table with the Bernath CHF correlation (while using the RELAP5-3D code flow solution) causes the increase to be 23% instead of 67%. Additional RELAP5-3D flow-versus-power solutions obtained from Reference 1 and presented in Appendix B for four specific TRIGA reactors further demonstrates that the Bernath correlation predicts CHF to occur at considerably lower power levels than does the 2006 Groeneveld table. Because of the lack of measured CHF data in the region of interest to TRIGA reactors, none of the CHF correlations considered can be assumed to provide the definitive CHF power. It is recommended, however, to compare the power levels of the potential limiting rods with the power levels at which the Bernath and 2006 Groeneveld CHF correlations predict CHF to occur.

  15. Conceptual design of fuel transfer cask for Reactor TRIGA PUSPATI (RTP)

    SciTech Connect

    Muhamad, Shalina Sheik; Hamzah, Mohd Arif Arif B.

    2014-02-12

    Spent fuel transfer cask is used to transfer a spent fuel from the reactor tank to the spent fuel storage or for spent fuel inspection. Typically, the cask made from steel cylinders that are either welded or bolted closed. The cylinder is enclosed with additional steel, concrete, or other material to provide radiation shielding and containment of the spent fuel. This paper will discuss the Conceptual Design of fuel transfer cask for Reactor TRIGA Puspati (RTP)

  16. STRUCTURAL CALCULATIONS FOR THE CODISPOSAL OF TRIGA SPENT NUCLEAR FUEL IN A WASTE PACKAGE

    SciTech Connect

    S. Mastilovic

    1999-07-28

    The purpose of this analysis is to determine the structural response of a TRIGA Department of Energy (DOE) spent nuclear fuel (SNF) codisposal canister placed in a 5-Defense High Level Waste (DHLW) waste package (WP) and subjected to a tipover design basis event (DBE) dynamic load; the results will be reported in terms of displacements and stress magnitudes. This activity is associated with the WP design.

  17. Conversion and evaluation of the THOR reactor core to TRIGA fuel elements

    SciTech Connect

    Li, S.-H.; Shiau, L.-C.

    1990-07-01

    The THOR reactor is a pool type 1 MW research reactor and has been operated since 1961. The original MTR fuel elements have been gradually replaced by TRIGA fuel elements since 1977 and the conversion completed in 1987. The calculations were performed for various core configurations by using computer codes, WIMS/CITATION. The computing results have been evaluated and compared with the core measurements after the fuel conversion. The analysis results are in good correspondence with the measurements. (author)

  18. Fluid Flow Characteristic Simulation of the Original TRIGA 2000 Reactor Design Using Computational Fluid Dynamics Code

    NASA Astrophysics Data System (ADS)

    Fiantini, Rosalina; Umar, Efrizon

    2010-06-01

    Common energy crisis has modified the national energy policy which is in the beginning based on natural resources becoming based on technology, therefore the capability to understanding the basic and applied science is needed to supporting those policies. National energy policy which aims at new energy exploitation, such as nuclear energy is including many efforts to increase the safety reactor core condition and optimize the related aspects and the ability to build new research reactor with properly design. The previous analysis of the modification TRIGA 2000 Reactor design indicates that forced convection of the primary coolant system put on an effect to the flow characteristic in the reactor core, but relatively insignificant effect to the flow velocity in the reactor core. In this analysis, the lid of reactor core is closed. However the forced convection effect is still presented. This analysis shows the fluid flow velocity vector in the model area without exception. Result of this analysis indicates that in the original design of TRIGA 2000 reactor, there is still forced convection effects occur but less than in the modified TRIGA 2000 design.

  19. Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

    NASA Astrophysics Data System (ADS)

    Zakaria, Norasalwa; Mustafa, Muhammad Khairul Ariff; Anuar, Abul Adli; Idris, Hairul Nizam; Ba'an, Rohyiza

    2014-02-01

    Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning of nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future.

  20. Transport model based on three-dimensional cross-section generation for TRIGA core analysis

    NASA Astrophysics Data System (ADS)

    Kriangchaiporn, Nateekool

    This dissertation addresses the development of a reactor core physics model based on 3-D transport methodology utilizing 3-D multigroup fuel lattice cross-section generation and core calculation for PSBR. The proposed 3-D transport calculation scheme for reactor core simulations is based on the TORT code. The methodology includes development of algorithms for 2-D and 3-D cross-section generation. The fine- and broad-group structures for the TRIGA cross-section generation problems were developed based on the CPXSD (Contributon and Point-wise Cross-Section Driven) methodology that selects effective group structure. Along with the study of cross section generation, the parametric studies for SN calculations were performed to evaluate the impact of the spatial meshing, angular, and scattering order variables and to obtain the suitable values for cross-section collapsing of the TRIGA cell problem. The TRIGA core loading 2 is used to verify and validate the selected effective group structures. Finally, the 13 group structure was selected to use for core calculations. The results agree with continuous energy for eigenvalues and normalized pin power distribution. The Monte Carlo solutions are used as the references.

  1. Role of decommissioning plan and its progress for the PUSPATI TRIGA Reactor

    SciTech Connect

    Zakaria, Norasalwa Mustafa, Muhammad Khairul Ariff Anuar, Abul Adli Idris, Hairul Nizam Ba'an, Rohyiza

    2014-02-12

    Malaysian nuclear research reactor, the PUSPATI TRIGA Reactor, reached its first criticality in 1982, and since then, it has been serving for more than 30 years for training, radioisotope production and research purposes. Realizing the age and the need for its decommissioning sometime in the future, a ground basis of assessment and an elaborative project management need to be established, covering the entire process from termination of reactor operation to the establishment of final status, documented as the Decommissioning Plan. At international level, IAEA recognizes the absence of Decommissioning Plan as one of the factors hampering progress in decommissioning of nuclear facilities in the world. Throughout the years, IAEA has taken initiatives and drawn out projects in promoting progress in decommissioning programmes, like CIDER, DACCORD and R2D2P, for which Malaysia is participating in these projects. This paper highlights the concept of Decommissioning plan and its significances to the Agency. It will also address the progress, way forward and challenges faced in developing the Decommissioning Plan for the PUSPATI TRIGA Reactor. The efforts in the establishment of this plan helps to provide continual national contribution at the international level, as well as meeting the regulatory requirement, if need be. The existing license for the operation of PUSPATI TRIGA Reactor does not impose a requirement for a decommissioning plan; however, the renewal of license may call for a decommissioning plan to be submitted for approval in future.

  2. Neutron flux characterisation of the Pavia TRIGA Mark II research reactor for radiobiological and microdosimetric applications.

    PubMed

    Alloni, D; Prata, M; Salvini, A; Ottolenghi, A

    2015-09-01

    Nowadays the Pavia TRIGA reactor is available for national and international collaboration in various research fields. The TRIGA Mark II nuclear research reactor of the Pavia University offers different in- and out-core neutron irradiation channels, each characterised by different neutron spectra. In the last two years a campaign of measurements and simulations has been performed in order to guarantee a better characterisation of these different fluxes and to meet the demands of irradiations that require precise information on these spectra in particular for radiobiological and microdosimetric studies. Experimental data on neutron fluxes have been collected analysing and measuring the gamma activity induced in thin target foils of different materials irradiated in different TRIGA experimental channels. The data on the induced gamma activities have been processed with the SAND II deconvolution code and finally compared with the spectra obtained with Monte Carlo simulations. The comparison between simulated and measured spectra showed a good agreement allowing a more precise characterisation of the neutron spectra and a validation of the adopted method. PMID:25958412

  3. NATCRCTR: One-dimensional thermal-hydraulics analysis code for natural-circulation TRIGA reactors

    SciTech Connect

    Feltus, M.A.; Rubinaccio, G.

    1996-12-31

    The Pennsylvania State University nuclear engineering department is evaluating the upgrade of the Reed College (Portland, Oregon) TRIGA reactor from 250 kW to 1 MW in two areas: thermal-hydraulics and steady-state neutronics analysis. This analysis was initiated as a cooperative effort between Penn State and Reed College as a training project for two International Atomic Energy Agency (IAEA) fellows from Ghana. The two Ghanaian IAEA fellows were assisted by G. Rubinaccio, an undergraduate, who undertook the task of writing the new computer programs for the thermal-hydraulic and physics evaluation as a three-credit special design project course. The Reed College TRIGA, which has a fixed graphite radial reflector, is cooled by natural circulation, without external cross-flow; whereas, the Penn State Breazeale Reactor has significant crossflow into its sides. To model the Reed TRIGA, the NATCRCTR program has been developed from first principles using the following assumptions: 1. The core is surrounded by the fixed reflector structure, which acts as a one-dimensional channel. 2. The core inlet temperature distribution is constant at the core bottom. 3. The axial heat flux distribution is a chopped cosine shape. 4. The heat transfer in the fuel is primarily in the radial directions. 5. A small gap between the fuel and cladding exists. The NATCRCTR code is used to find the peak centerline fuel, gap, and cladding surface temperatures, based on assumed flux and engineering peaking factors.

  4. Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation

    SciTech Connect

    Winston, P.L.; Sterbentz, J.W.

    2002-07-01

    Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculated values as a means to validate the reported element burnups. A newly installed and functional gamma-ray detection subsystem of the In-Cell Examination System was used to perform the measurements and is described in some detail. The analytical methodology used to calculate the corresponding dose rates is presented along with the calculated values. Comparison of the measured and calculated dose rates for the TRIGA fuel elements indicates good agreement (less than a factor of 2 difference). The intent of the subsystem is to measure the gross gamma dose rate and correlate the measurement to a calculated dose rate based on the element s known burnup and other pertinent spent fuel information. Although validation of the TRIGA elements' burnup is of primary concern in this paper, the measurement and calculational techniques can be used to either validate an element's reported burnup or provide a burnup estimate for an element with an unknown burnup. (authors)

  5. Fluid Flow Characteristic Simulation of the Original TRIGA 2000 Reactor Design Using Computational Fluid Dynamics Code

    SciTech Connect

    Fiantini, Rosalina; Umar, Efrizon

    2010-06-22

    Common energy crisis has modified the national energy policy which is in the beginning based on natural resources becoming based on technology, therefore the capability to understanding the basic and applied science is needed to supporting those policies. National energy policy which aims at new energy exploitation, such as nuclear energy is including many efforts to increase the safety reactor core condition and optimize the related aspects and the ability to build new research reactor with properly design. The previous analysis of the modification TRIGA 2000 Reactor design indicates that forced convection of the primary coolant system put on an effect to the flow characteristic in the reactor core, but relatively insignificant effect to the flow velocity in the reactor core. In this analysis, the lid of reactor core is closed. However the forced convection effect is still presented. This analysis shows the fluid flow velocity vector in the model area without exception. Result of this analysis indicates that in the original design of TRIGA 2000 reactor, there is still forced convection effects occur but less than in the modified TRIGA 2000 design.

  6. Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation

    SciTech Connect

    Winston, Philip Lon; Sterbentz, James William

    2001-04-01

    Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculated values as a means to validate the reported element burnups. A newly installed and functional gamma-ray detection subsystem of the In-Cell Examination System was used to perform the measurements and is described in some detail. The analytical methodology used to calculate the corresponding dose rates is presented along with the calculated values. Comparison of the measured and calculated dose rates for the TRIGA fuel elements indicates good agreement (less than a factor of 2 difference). The intent of the subsystem is to measure the gross gamma dose rate and correlate the measurement to a calculated dose rate based on the element s known burnup and other pertinent spent fuel information. Although validation of the TRIGA elements’ burnup is of primary concern in this paper, the measurement and calculational techniques can be used to either validate an element’s reported burnup or provide a burnup estimate for an element with an unknown burnup.

  7. Acculturation preference profiles of Spaniards and Romanian immigrants: the role of prejudice and public and private acculturation areas.

    PubMed

    Rojas, Antonio J; Navas, Marisol; Sayans-Jiménez, Pablo; Cuadrado, Isabel

    2014-01-01

    The main goal of this study was to identify acculturation preference profiles using cluster analysis in public and private areas of culture in the host and immigrant populations, and to find out the relationship between these profiles and prejudice levels. Four hundred and ninety-nine Spaniards and 500 Romanians participated in a survey. The sampling of Spaniards was multistage random and the sampling of Romanians was by quota. The results confirm our predictions. Romanians who are less prejudiced against Spaniards prefer assimilation in public areas and integration in private areas. Romanians who are more prejudiced against Spaniards prefer integration in public areas and separation in private areas. Spaniards who are less prejudiced against Romanians prefer integration in both public and private areas. Spaniards who are more prejudiced against Romanians prefer assimilation in both areas. PMID:25154117

  8. Stable isotopes determination in some Romanian fruit juices.

    PubMed

    Magdas, Dana Alina; Puscas, Romulus

    2011-09-01

    The characterisation of 45 Romanian single-strength fruit juices (apples, pears, plums and grapes) collected from different Transylvanian areas by means of stable isotope approach are presented and discussed in this study. We measured (2)H/(1)H, (18)O/(16)O ratios from water juice and (13)C/(12)C from pulp and compared these results with those already reported in the literature for single-strength juices, in order to see how the geographical and climatic conditions of Transylvania and the meteorological peculiarities of the year 2010 influence the isotopic composition of the investigated fruit juices. The δ(13)C mean values that we found for apple pulp picked up from different Transylvanian areas show slight differences, probably due to the environmental conditions of the plants. No significant correlation either between the variety of apple or the geographical origin and δ(13)C value was established. PMID:21892892

  9. Extra curricular photonics education in Romanian high schools

    NASA Astrophysics Data System (ADS)

    Sporea, Dan; Sporea, Adelina; Timus, Clementina

    2007-08-01

    In the frame of the European Union funded Comenius project "Hands-on Science", a network of very active high schools was created, aiming to attract students towards science study by offering them the possibility to learn and to express themselves through experiments. On the other side, our Institute coordinates the project "Science Education and Training in a Knowledge-Based Society - SET 2010", project supported by the Romanian Ministry of Education and Research, which targets the same audience by different means. The paper addresses some of the results of these two projects as they are linked with photonics teaching in high schools through extra curricular activities such as science clubs, science fairs, and national contests for high school students. The project results were introduced to the public at various conferences: ETOP Conference, France), NATO Advanced Workshop, Hungary), Hands-on Science Conference, Greece), Euroscience Forum, Germany), Communicating European Research, Belgium).

  10. Ambient seismic noise cross-correlations at Romanian broadband stations

    NASA Astrophysics Data System (ADS)

    Grecu, Bogdan; Tataru, Dragos; Neagoe, Cristian; Panza, Giuliano; Raileanu, Victor; Radulian, Mircea; Popa, Mihaela; Ionescu, Constantin

    2010-05-01

    In the last years the National Institute for Earth Physics (NIEP), Romania, has developed its real-time broadband seismic network. At present, NIEP operates 34 stations with both broadband velocity sensors (CMG3ESP, CMG40T, KS2000, STS2) and accelerometer sensors (2gEpi). The data are continuously recorded and transmitted to the Romanian Data Centre where Antelope 4.11 is running for acquisition and processing. The density of the stations produces 560 inter-station pairs for ambient noise cross-correlation analysis. In this study, we used seismic data recorded during a period of 12 months, between January 2009 and December 2009. A nonlinear procedure is applied to lower the influence of the earthquake-related signals and to obtain a symmetric noise cross-correlation function (for details see Cho et al., 2007). The results show good cross-correlation functions for almost all pair of stations. As the vertical components of ambient noise are cross-correlated, only the fundamental mode of the Rayleigh wave is obtained. The FTAN analysis is used to extract the group velocities from the estimated dispersive waves at periods between 6 and 30 sec. This work provides very useful data for future tomographic studies in Romania at crustal level, considering that new data from other broadband stations deployed on the Romanian territory will become available. References: Cho, K.H., R. B. Herrmann, C. J. Ammon and K. Lee. Imaging the Upper Crust of the Korean Peninsula by Surface-Wave Tomography, Bulletin of the Seismological Society of America (2007) 97, 198-207.

  11. Updates of the prevalence of problem gambling in Romanian teenagers.

    PubMed

    Lupu, Viorel; Todirita, Izabela Ramona

    2013-03-01

    The aim of this study was to find out what is the prevalence of pathological in Romanian teenagers. We questioned one thousand thirty-two teenagers in Cluj-Napoca and Harghita counties. Participants completed a questionnaire with 40 items including gamblers anonymous twenty questions. The sample included teenagers aged 11-19 years; 65.57% were male and 34.43% were female. The subjects were divided into three groups: non-gambling/recreational gambling or occasional gambling (0-1 positive answers -Level 1)-753 subjects (72.96%) [316 females and 437 males]; problem gambling (2-6 points-Level 2)-243 subjects (23.54%) [43 females and 200 males]; pathological gambling (above 7 points-Level 3)-36 subjects (3.48%) [3 females and 33 males]. The mean age of pathological gamblers was 16.48 years. Gender differences were as expected, males engaging in pathological gambling (91.66% from pathological gamblers) more than females did (8.33% from pathological gamblers). Data revealed that the most encountered games practiced weekly were sport bets and slot machines in the case of 36.11% of the pathological gamblers; lotto, internet casino and pool bets each with 25%, followed by roulette and black-jack with 22.22%.From those who reported practicing gambling at a pathological level 66.66% engaged in alcohol consumption, 13.88% illicit drug use and 19.44% licit drugs. Just 16.66% smoke cigarettes. Data revealed higher rates of prevalence in Romanian teenagers than in other Central and Eastern European countries. A prevalence study at a national level should be designed. PMID:22350682

  12. Linking landslide susceptibility to sediment yield in the Romanian Carpathians

    NASA Astrophysics Data System (ADS)

    Broeckx, Jente; Vanmaercke, Matthias; Bǎlteanu, Dan; Chendeş, Viorel; Sima, Mihaela; Enciu, Petru; Poesen, Jean

    2016-04-01

    Recent studies revealed the importance of seismic activity in explaining regional patterns of catchment sediment yield (SY). This relation is often explained by the fact that seismic activity induces landslides that contribute to SY. Nevertheless, only a few studies focused on the effects of landslides on SY and even fewer studies have explored the potential of landslide susceptibility as a predictor for SY. The objective of this study is therefore to explore the potential of landslide susceptibility maps to explain the spatial variation of SY in the Romanian Carpathians, a region with moderate to high seismicity. 133 catchments, covering 63% of Romania, for which SY was measured during a period of at least 10 years and for which SY was not significantly affected by upstream reservoirs, were compiled and selected. 78 of these catchments were 'less disturbed', being covered for at least 50% by forest and semi-natural areas and confined to the Carpathian mountains. Landslide susceptibility in each catchment was assessed, using an earlier published state of the art landslide susceptibility map of Romania. Mean landslide susceptibility for each catchment shows a highly significant correlation with SY (r² = 0.44). This indicates that landslides are an important contributor to SY in Romania and suggests that regional and national landslide susceptibility maps can indeed be a useful tool to predict SY. Nevertheless, the susceptibility map did not explain much more of the observed variance in SY than some other individual catchment characteristics such as seismicity (r² = 0.40) and lithology (r² = 0.33). Also taking into account the spatial patterns of landslide susceptibility within the catchment did not significantly improve the observed correlations. Surprisingly, topography showed a nonsignificant correlation with SY, which can be attributed to the overwhelming effect of seismicity and lithology. Overall, our results suggest that seismicity is indeed a highly

  13. Environmental dose rate distribution along the Romanian Black Sea shore

    NASA Astrophysics Data System (ADS)

    Duliu, Octavian G.; Margineanu, Romul M.; Blebea-Apostu, Ana-Maria; Gomoiu, Claudia; Bercea, Sorin

    2013-04-01

    The radiometric investigation of the natural radioactivity dose rate distribution along the most important Romanian Black Sea tourist resorts showed values between 34 and 54 nSv/h, lower than the 59 nSv/h, the average background reported for the entire Romanian territory. At the same time we have noticed that the experimental dose rates monotonously increase northward, reaching a maximum in the vicinity of Vadu and Corbu beaches, both on the southern part of the Chituc sandbank. Concurrent gamma ray spectrometric measurements, performed at the Slanic-Prahova Low-Background Radiation Laboratory for sand samples collected from the same location, have shown that the natural radionuclides have a major contribution to background radiation while anthropogenic Cs-137 plays, 26 years after Chernobyl catastrophe, a negligible role. The experimental values of activity concentrations of all radionuclides present in sand samples were used to calculate the corresponding values of dose rates to which, by adding the contribution of cosmic rays, we have obtained values coincident, within experimental uncertainties, with the experimental ones. At the same time, on Chituc sandbank, a transverse profile of dose rate distribution revealed the presence of some local maxima, two to thee times higher then the average ones. Subsequent gamma ray spectrometry showed an increased content of natural radionuclides, most probably due to a local accumulation of heavy minerals, a common occurrence in the vicinity of river deltas, in our case the Danube Delta. In such a way, the monitoring of local dose rate distribution could be very useful not only in attesting the environmental quality of various resorts and beaches, but also, in signaling the presence of heavy minerals, with beneficent economic consequences.

  14. Conflict of interest from a Romanian geneticist's perspective.

    PubMed

    Ispas, Ioana

    2002-07-01

    This paper examines Romanian bioethics regulations for biomedical sciences, looking in particular at the genetics area as a source for conflict of interest. The analysis is focused on the organizational level, national regulations, the sources for generating conflicts of interest, and management of conflicts. Modern biotechnology and gene technology are among the key technologies of the twenty-first century. The application of gene technology for medical and pharmaceutical purposes is widely accepted by society, but the same cannot be said of the development and application of gene technology in agriculture and food processing. Because the use of a technology in the production and processing of food is regarded more sceptically than in the production of biomedical products, there can be areas of conflict in many cases when communication is undertaken about gene technology in the agro-food sector. Ethical concerns play an important factor in this, but a society's attitude to a developing technology is an amalgam of many effects which are beyond ethics as such. This paper contains a study carried out by the author for the Romanian Association for Consumer Protection about the attitudes of consumers towards genetically modified (GM) foods. This study revealed that in Romania more than 98% of consumers did not know anything about GM foods and frequently were confused about the definitions of these terms. In conclusion, it is necessary to say that there is a low level of knowledge regarding biotechnology in Romania and this is an important reason why there is neither public acceptance of gene technology products nor is there a rejection. PMID:12353364

  15. High-temperature Chemical Compatibility of As-fabricated TRIGA Fuel and Type 304 Stainless Steel Cladding

    SciTech Connect

    Dennis D. Keiser, Jr.; Jan-Fong Jue; Eric Woolstenhulme; Kurt Terrani; Glenn A. Moore

    2012-09-01

    Chemical interaction between TRIGA fuel and Type-304 stainless steel cladding at relatively high temperatures is of interest from the point of view of understanding fuel behavior during different TRIGA reactor transient scenarios. Since TRIGA fuel comes into close contact with the cladding during irradiation, there is an opportunity for interdiffusion between the U in the fuel and the Fe in the cladding to form an interaction zone that contains U-Fe phases. Based on the equilibrium U-Fe phase diagram, a eutectic can develop at a composition between the U6Fe and UFe2 phases. This eutectic composition can become a liquid at around 725°C. From the standpoint of safe operation of TRIGA fuel, it is of interest to develop better understanding of how a phase with this composition may develop in irradiated TRIGA fuel at relatively high temperatures. One technique for investigating the development of a eutectic phase at the fuel/cladding interface is to perform out-of-pile diffusion-couple experiments at relatively high temperatures. This information is most relevant for lightly irradiated fuel that just starts to touch the cladding due to fuel swelling. Similar testing using fuel irradiated to different fission densities should be tested in a similar fashion to generate data more relevant to more heavily irradiated fuel. This report describes the results for TRIGA fuel/Type-304 stainless steel diffusion couples that were annealed for one hour at 730 and 800°C. Scanning electron microscopy with energy- and wavelength-dispersive spectroscopy was employed to characterize the fuel/cladding interface for each diffusion couple to look for evidence of any chemical interaction. Overall, negligible fuel/cladding interaction was observed for each diffusion couple.

  16. Development of TRIGA-based experimental device for fiber optics in-core instrumentation testing for VHTRs

    SciTech Connect

    Johns, J. M.; Tsvetkov, P. V.

    2012-07-01

    Given the harsh environments of high temperature reactors, new in-core instrumentation has to be developed, since existing approaches may fail prematurely in VHTRs. The paper discusses ongoing efforts to support progress of suitable advanced in-core instrumentation technologies and develop an experimental approach for evaluation of their performance within VHTRs via emulation of VHTR in-core conditions in TRIGA reactors. Successful completion of the presented computational analysis concludes the first phase of the project. As demonstrated, it is proposed to use a high temperature furnace with fluence equivalency in operating TRIGA reactors. (authors)

  17. Use of Romanian Seismic Network to monitor nuclear explosions

    NASA Astrophysics Data System (ADS)

    Ghica, Daniela; Neagoe, Cristian; Grecu, Bogdan; Popa, Mihaela

    2014-05-01

    During the last decade, three underground nuclear tests were conducted by the Democratic People's Republic of Korea (DPRK): on October 9, 2006, May 25, 2009, and February 12, 2013. The magnitude of the events, estimated by International Data Centre (IDC) as 4.1, 4.5 and 4.9, indicates that the latest was more powerful than its predecessors. We analyze seismic signals generated by the DPRK tests and recorded with Romanian Seismic Network (RSN). The location estimates performed at Romania National Data Centre (NDC) using RSN data, were compared with those obtained at IDC. As a consequence of the global superior coverage with seismic stations included in the International Monitoring System, IDC locations are better constrained. The signals generated by 2006 DPRK nuclear test were observed on 8 RSN stations, the 2009 test on 33, and the 2013 test on 47. This continuous increase is due to the rise in the number of stations installed during last five years, as well as to the larger magnitude of the 2013 test. The recent development of RSN has enabled NDC to locate the events with more accuracy, based on the higher-quality parameters estimated from data processing. For all three events, a high signal coherency is observed for the data recorded by the Romanian seismic array, BURAR, reconfirming the superiority of the arrays to single stations for detecting and characterizing signals from nuclear explosions. Array processing techniques are applied for signal detection and to estimate the slowness vector (back-azimuth and apparent velocity). The comparison of vertical displacement seismograms recorded at RSN stations shows a remarkably similarity of the signals generated by the three events analyzed. The records are nearly identical, except that the amplitude is directly proportional to the event magnitude. Spectrograms of the recorded RSN data were examined, showing that the nuclear explosions produce seismic signals with a high energy in the 0.5 to 2.0 Hz frequency range

  18. 3D Landslides Susceptibility Analysis in Romanian Subcarpathians

    NASA Astrophysics Data System (ADS)

    Sandric, Ionuc; Ilinca, Viorel; Chitu, Zenaida; Jurchescu, Marta

    2015-04-01

    Most of the present day studies make use the 2.5D raster data formats for the landslide susceptibility analysis at regional scales. This data format has some disadvantages when geological and lithological settings are spatial discretized, hence these disadvantages propagate in the landslides susceptibility analysis and especially where only surface lithology is used. The main disadvantage when using 3D data models for the assessment of landslide susceptibility at regional scales is represented by the quality of the geological and lithological information that is available for a depth of no more than 100m. In order to mitigate this, a sufficient number of boreholes is required and sometimes is not available. In order to overcome the lack of borehole data, our approach was to make use of the present-day geological maps at scales ranging from 1:25,000 to 1:50,000 and to generate a geological 3D model up to a depth of 100m. The geological model was generated based on expert knowledge interpretations and geological cross sections provided on these geological maps. Using the 3D geological model a more complex 3D model was generated for the landslide susceptibility analysis that also contains information from other predictor factors like slope gradient, land-cover and land-use. For the landslide susceptibility analysis instead of using map algebra equations on classic pixel based data sets, the equations were adapted for 3D data models and map algebra equations on voxels. The test sites are located in the areas of Romanian Subcarpathians. The Romanian Subcarpathians are located to the exterior of the Carpathians. They consist of a large variety of rocks, flysch-type deposits in the inner part and molasse deposits in the outer part, ranging from a Cretacic-Paleogene to a Quaternary age. While some parts of the Subcarpathians have a basic geology, with a monoclinal geological structure, other parts like the Curvature Subcarpathians, present acomplex folded and faulted

  19. Value and Benefits of European Student Mobility for Romanian Students: Experiences and Perspectives of Participants in the ERASMUS Programme

    ERIC Educational Resources Information Center

    Salajan, Florin D.; Chiper, Sorina

    2012-01-01

    This article reports on the experiences and perspectives of Romanian students participating in the ERASMUS Programme, regarding the benefits and value of academic mobility. It situates their accounts in the framework of internationalization and Europeanization processes occurring in Romanian higher education. The study draws on primary data…

  20. The recognition of Gheorghe Bilaşcu’s contributions in the Romanian history of dentistry

    PubMed Central

    BÂRSU, CRISTIAN

    2013-01-01

    Prof. Dr. Gheorghe Bilaşcu (1863–1926) was one of the founders of the Romanian Faculty of Medicine in Cluj. At this Faculty, in 1919/1920 he created the department and the clinic of dentistry. These two achievements were accomplished for the first time in Romania. Normally, his contribution should have been appreciated both during his life and after his death. Also, his name would be expected to be present in the large majority of Romanian medico-historians dictionaries, treatises, papers etc. Unfortunately, his posthumous appreciation was not as Bilaşcu would have deserved. In our paper we present the recognition of Gh. Bilaşcu’s contributions in the Romanian history of dentistry between 1926–2013. We divided this period into three intervals: from 1926 to 1948, the communist era, and after the anticommunist revolution (1990-present). In the first interval the achievements of Bilaşcu in the field of dentistry were very much appreciated and they were mentioned in a correct way in different medico-historical sources of information. During the communist era the name of Bilaşcu was omitted in some dictionaries, courses etc. After 1990, the important role of Bilaşcu in Romanian dentistry was put into its important place in the majority of Romanian history of medicine sources of information. PMID:26527965

  1. Fuel behavior comparison for a research reactor

    NASA Astrophysics Data System (ADS)

    Negut, Gh.; Mladin, M.; Prisecaru, I.; Danila, N.

    2006-06-01

    The paper presents the behavior and properties analysis of the low enriched uranium fuel, which will be loaded in the Romanian TRIGA 14 MW steady state research reactor compared with the original high enriched uranium fuel. The high and low enriched uranium fuels have similar thermal properties, but different nuclear properties. The research reactor core was modeled with both fuel materials and the reactor behavior was studied during a reactivity insertion accident. The thermal hydraulic analysis results are compared with that obtained from the safety analysis report for high enriched uranium fuel core. The low enriched uranium fuel shows a good behavior during reactivity insertion accident and a revised safety analysis report will be made for the low enriched uranium fuel core.

  2. Monte Carlo Simulation of the TRIGA Mark II Benchmark Experiment with Burned Fuel

    SciTech Connect

    Jeraj, Robert; Zagar, Tomaz; Ravnik, Matjaz

    2002-03-15

    Monte Carlo calculations of a criticality experiment with burned fuel on the TRIGA Mark II research reactor are presented. The main objective was to incorporate burned fuel composition calculated with the WIMSD4 deterministic code into the MCNP4B Monte Carlo code and compare the calculated k{sub eff} with the measurements. The criticality experiment was performed in 1998 at the ''Jozef Stefan'' Institute TRIGA Mark II reactor in Ljubljana, Slovenia, with the same fuel elements and loading pattern as in the TRIGA criticality benchmark experiment with fresh fuel performed in 1991. The only difference was that in 1998, the fuel elements had on average burnup of {approx}3%, corresponding to 1.3-MWd energy produced in the core in the period between 1991 and 1998. The fuel element burnup accumulated during 1991-1998 was calculated with the TRIGLAV in-house-developed fuel management two-dimensional multigroup diffusion code. The burned fuel isotopic composition was calculated with the WIMSD4 code and compared to the ORIGEN2 calculations. Extensive comparison of burned fuel material composition was performed for both codes for burnups up to 20% burned {sup 235}U, and the differences were evaluated in terms of reactivity. The WIMSD4 and ORIGEN2 results agreed well for all isotopes important in reactivity calculations, giving increased confidence in the WIMSD4 calculation of the burned fuel material composition. The k{sub eff} calculated with the combined WIMSD4 and MCNP4B calculations showed good agreement with the experimental values. This shows that linking of WIMSD4 with MCNP4B for criticality calculations with burned fuel is feasible and gives reliable results.

  3. Assessment results of the South Korea TRIGA SNF to be shipped to INEEL

    SciTech Connect

    Cole, C.M.; Dirk, W.J.; Cottam, R.E.; Paik, S.T.

    1997-10-09

    This paper describes the Training, Research, Isotope, General Atomics (TRIGA) spent nuclear fuel (SNF) examination at the Seoul and the Taejon Research Reactor Facilities in South Korea. The examination was required before the SNF would be accepted for transportation and storage at the INEEL. The results of the aluminum and stainless steel clad TRIGA fuel examination have been summarized. A description of the examination team training, the examination work plan and examination equipment is also included. This paper also explains the technical basis for the examination and physical condition criteria used to determine what, if any, additional packaging would be required for transportation and for the receipt and storage of the fuel at the INEEL. This paper delineates the preparation activities prior to the fuel examinations and includes (1) collecting spent fuel data; (2) preparatory work by the Korean Atomic Energy Research Institute (KAERI) for fuel examination: (3) preparation of a radionuclide report, Radionuclide Mass Inventory, Activity, Decay Heat, and Dose Rate Parametric Data for TRIGA Spent Nuclear Fuels needed to provide input data for transportation and fuel acceptance at the Idaho National Engineering and Environmental Laboratory (INEEL); (4) gathering FRR Facility data; and (5) coordination between the INEEL and KAERI. Included, are the unanticipated conditions encountered in the unloading of fuel from the dry storage casks in Taejon in preparation for examination, a description of the damaged condition of the fuel removed from the casks, and the apparent cause of the damages. Lessons learned from all the activities are also addressed. A brief description of the preparatory work for the shipment of the spent fuel from Korea to INEEL is included.

  4. Determination of the irradiation field at the research reactor TRIGA Mainz for BNCT.

    PubMed

    Nagels, S; Hampel, G; Kratz, J V; Aguilar, A L; Minouchehr, S; Otto, G; Schmidberger, H; Schütz, C; Vogtländer, L; Wortmann, B

    2009-07-01

    For the application of the BNCT for the excorporal treatment of organs at the TRIGA Mainz, the basic characteristics of the radiation field in the thermal column as beam geometry, neutron and gamma ray energies, angular distributions, neutron flux, as well as absorbed gamma and neutron doses must be determined in a reproducible way. To determine the mixed irradiation field thermoluminescence detectors (TLD) made of CaF(2):Tm with a newly developed energy-compensation filter system and LiF:Mg,Ti materials with different (6)Li concentrations and different thicknesses as well as thin gold foils were used. PMID:19380234

  5. Monte Carlo design for a new neutron collimator at the ENEA Casaccia TRIGA reactor.

    PubMed

    Burgio, N; Rosa, R

    2004-10-01

    The TRIGA RC-1 1MW reactor operating at ENEA Casaccia Center is currently being developed as a second neutron imaging facility that shall be devoted to computed tomography as well as neutron tomography. In order to reduce the gamma-ray content in the neutron beam, the reactor tangential piercing channel was selected. A set of Monte Carlo simulation was used to design the neutron collimator, to determine the preliminary choice of the materials to be employed in the collimator design. PMID:15246415

  6. Cryostat system for investigation on new neutron moderator materials at reactor TRIGA PUSPATI

    NASA Astrophysics Data System (ADS)

    Dris, Zakaria bin; Mohamed, Abdul Aziz bin; Hamid, Nasri A.; Azman, Azraf; Ahmad, Megat Harun Al Rashid Megat; Jamro, Rafhayudi; Yazid, Hafizal

    2016-01-01

    A simple continuous flow (SCF) cryostat was designed to investigate the neutron moderation of alumina in high temperature co-ceramic (HTCC) and polymeric materials such as Teflon under TRIGA neutron environment using a reflected neutron beam from a monochromator. Cooling of the cryostat will be carried out using liquid nitrogen. The cryostat will be built with an aluminum holder for moderator within stainless steel cylinder pipe. A copper thermocouple will be used as the temperature sensor to monitor the moderator temperature inside the cryostat holder. Initial measurements of neutron spectrum after neutron passing through the moderating materials have been carried out using a neutron spectrometer.

  7. Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications.

    PubMed

    Akan, Zafer; Türkmen, Mehmet; Çakir, Tahir; Reyhancan, İskender A; Çolak, Üner; Okka, Muhittin; Kiziltaş, Sahip

    2015-05-01

    This paper aims to describe the modification of the radial beam port of ITU (İstanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au-Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented. PMID:25746919

  8. Technical Specifications for the Neutron Radiography Facility (TRIGA Mark 1 Reactor). Revision 6

    SciTech Connect

    Tomlinson, R.L.; Perfect, J.F.

    1988-04-01

    These Technical Specifications state the limits under which the Neutron Radiography Facility, with its associated TRIGA Mark I Reactor, is operated by the Westinghouse Hanford Company for the US Department of Energy. These specifications cover operation of the Facility for the purpose of examination of specimens (including contained fissile material) by neutron radiography, for the irradiation of specimens in the pneumatic transfer system and approved in-core or in-pool irradiation facilities and operator training. The Final Safety Analysis Report (TC-344) and its supplements, and these Technical Specifications are the basic safety documents of the Neutron Radiography Facility.

  9. Unique applications of research reactors with TRIGA UZrH[sub x] fuel

    SciTech Connect

    Whittemore, W.L. )

    1993-01-01

    The TRIGA reactor fuel (UZrH[sub x]) in research reactors provides significant safety features that have permitted varied and unique applications. The safety features include a very large, prompt, negative temperature coefficient of reactivity; very high safety limit for fuel temperature (1150[degrees]C); and large fission product retention even for unclad fuel. The recognized safety of these reactors has permitted them to be located as appropriate on university campuses in buildings housing lecture halls and in hospitals. It has also facilitated installation of in-core or near-core experiments and facilities, including liquid hydrogen or other cryogenic neutron sources.

  10. Neutronics analysis of the proposed 25-MW leu TRIGA Multipurpose Research Reactor

    SciTech Connect

    Nurdin, M.; Bretscher, M.M.; Snelgrove, J.L.

    1982-01-01

    More than two years ago the government of Indonesia announced plans to purchase a research reactor for the Puspiptek Research Center in Serpong Indonesia to be used for isotope production, materials testing, neutron physics measurements, and reactor operator training. Reactors using low-enriched uranium (LEU) plate-type and rod-type fuel elements were considered. This paper deals with the neutronic evaluation of the rod-type 25-MW LEU TRIGA Multipurpose Research Reactor (MPRR) proposed by the General Atomic Company of the United States of America.

  11. Quality assessment of Romanian bottled mineral water and tap water.

    PubMed

    M Carstea, Elfrida; Levei, Erika A; Hoaghia, Maria-Alexandra; Savastru, Roxana

    2016-09-01

    This study reports the evaluation of bottled mineral water characteristics using fluorescence spectroscopy (synchronous fluorescence scans and emission spectra) and physico-chemical analyses. Samples from 14 still mineral water brands were compared to 11 tap waters collected from two Romanian cities. Correlation and factor analyses were undertaken to understand the relationships between the individual components. The concentration of major and minor ions showed great variation between the bottled mineral water samples highlighting the diversity of the water intakes, while in the case of tap water the chemical composition was relatively similar for samples collected in the same city. Fluorescence data showed that the mineral water contained low quantities of organic matter. The humic fraction was dominant in all samples, while the microbial fraction was low in most samples. Synchronous fluorescence scans provided more information, regarding the composition of organic matter, compared to emission spectra. The study evidenced the correlation between fluorescence parameters and major elements and highlighted the potential of using fluorescence for qualitative evaluation of the bottled mineral water quality, as a screening method before undertaking complex analyses. PMID:27526046

  12. Isotopic and elemental determination in some romanian apple fruit juices.

    PubMed

    Magdas, Dana Alina; Dehelean, Adriana; Puscas, Romulus

    2012-01-01

    H, C, O stable isotope ratios and the content of some heavy elements of 31 Romanian single-strength organic apple juices collected from four Transylvanian areas are discussed in this study. The aim of this study was to measure the ²H/¹H, ¹⁸O/¹⁶O, ¹³C/¹²C ratios of these juices and their elemental profile and to establish a database of authentic values to be used for adulteration and authenticity testing. Our results have shown mean values of δ¹⁸O = -4.2‰ and δDδ-46.5‰, respectively, for apples from Transylvania and at the same time the mean value of δ¹³C = -28.2‰. The content of Cd, Pb, U, Zn, As was below the acceptable limits stipulated in US-EPA standard for drinking water. Cu and Cr limits exceeded for one single juice; Ni content for some apple juices from Maramures, Alba, and Cluj was higher than the acceptable value. PMID:22666164

  13. Isotopic and Elemental Determination in Some Romanian Apple Fruit Juices

    PubMed Central

    Magdas, Dana Alina; Dehelean, Adriana; Puscas, Romulus

    2012-01-01

    H, C, O stable isotope ratios and the content of some heavy elements of 31 Romanian single-strength organic apple juices collected from four Transylvanian areas are discussed in this study. The aim of this study was to measure the 2H/1H, 18O/16O, 13C/12C ratios of these juices and their elemental profile and to establish a database of authentic values to be used for adulteration and authenticity testing. Our results have shown mean values of δ18O = −4.2‰ and δDδ−46.5‰, respectively, for apples from Transylvania and at the same time the mean value of δ13C = −28.2‰. The content of Cd, Pb, U, Zn, As was below the acceptable limits stipulated in US-EPA standard for drinking water. Cu and Cr limits exceeded for one single juice; Ni content for some apple juices from Maramures, Alba, and Cluj was higher than the acceptable value. PMID:22666164

  14. The identity of Romanian amber (rumanite) with Baltic amber (succinite).

    SciTech Connect

    Stout, E. C.; Beck, C. W.; Anderson, K. B.; Chemistry; Vassar Coll.

    2000-11-01

    Romanian amber (rumanite) has been considered to be a separate species of fossil resin for more than a century. While earlier investigators held it to be very similar to succinite (Baltic amber), modern scholars have assigned it a distinctly different botanical origin. We have found that almost all of the constituents of the ether-soluble fractions of 13 specimens of authentic rumanite identified by gas chromatography-mass spectrometry have previously been reported in the soluble fraction of succinite, including succinic acid and its monoterpene esters. Additionally and significantly, the soluble fraction of rumanite contains a number defunctionalized compounds that do not preexist in succinite, but that are produced by pyrolysis of whole succinite or of its insoluble polymeric fraction. Simultaneous methylation pyrolysis-gas chromatography-mass spectrometry of the polymeric fraction of seven of the rumanite specimens yielded further copious amounts of dimethyl succinate, a number of diterpene resin acid methyl esters, and additional defunctionalized compounds known to be pyrolysis products of succinite. The evidence shows conclusively that the botanical origin of rumanite is not distinct from that of succinite. Rather, rumanite is a succinite that has suffered partial thermal degradation in the course of the folding of the Oligocene Kliwa sandstone formation in which it is most commonly found.

  15. Chromosomal Polymorphisms Involved in Reproductive Failure in the Romanian Population

    PubMed Central

    Mierla, D; Stoian, V

    2012-01-01

    Cytogenetic heteromorphisms are described as variations at specific chromosomal regions with no impact on phenotype. The purpose of this study was to investigate the effects of these chromosomal polymorphisms involved in reproductive failure in the Romanian population. One thousand eight hundred and nine infertile patients, who were referred to Life Memorial Hospital, Bucharest, Romania, between January 2008 and April 2011, were investigated in this retrospective study. The frequency of chromosomal polymorphic variations was calculated for these patients. The control group is represented by 1116 fetuses investigated by amniocentesis between January 2009 and April 2011. In this study 122 (6.74%) infertile patients and 63 fetuses (5.65%) showed chromosomal polymorphic variations. The differences between the two groups was not statistically significant (p <0.242) but there was statistical significance for some specific chromosomal polymorphisms [inv(9),1qh+, 9qh+, fra(17)]. Some chromosomal polymorphic variations appear to be associated with reproductive failure. The statistically significantly higher incidence of heterochromatic variations found in infertile individuals emphasizes the need to assess their role in infertility and subfertility. PMID:24052728

  16. Romanian Experience in The Conditioning of Radium Sources

    SciTech Connect

    Dogaru, Gh.; Dragolici, F.; Rotarescu, Gh.; Nicu, M.

    2008-07-01

    Ra{sup 226} first radionuclide separated from pitchblende in 1898 by Pierre and Marie Curie was successfully used in medicine, industry as in other fields being the only one available radionuclide till 1940 when were produced other radionuclides in accelerators. On long term the use of Ra{sup 226} sealed sources are not any more safe due to: the high specific activity, long half live, decays in Rn{sup 226} gas which increases the internal pressure of capsule leading in time to the leakage, the salts as raw materials from which the sealed sources are manufactured are soluble, there is a leak of information and records on the manufacture and operation. Based on this consideration in Romania regulatory authority did not authorized any more the use of these sealed sources [1]. The paper presents some aspects from Romanian experience related to the collection and conditioning of radium sealed sources. Data relating the radium inventory as well as the arrangements made in order to create a workshop for the conditioning of radium sources are presented. (authors)

  17. Seasonal variations in mood and behavior in Romanian postgraduate students.

    PubMed

    Soriano, Joseph J; Ciupagea, Constantin; Rohan, Kelly J; Neculai, Dorin B; Yousufi, Samina M; Guzman, Alvaro; Postolache, Teodor T

    2007-01-01

    To our knowledge, this paper is the first to estimate seasonality of mood in a predominantly Caucasian sample, living in areas with hot summers and a relative unavailability of air conditioning. As a summer pattern of seasonal depression was previously associated with a vulnerability to heat exposure, we hypothesized that those with access to air conditioners would have a lower rate of summer seasonal affective disorder (SAD) compared to those without air conditioning. A convenience sample of 476 Romanian postgraduate students completed the Seasonal Pattern Assessment Questionnaire (SPAQ), which was used to calculate a global seasonality score (GSS) and to estimate the rates of winter- and summer-type SAD. The ratio of summer- vs. winter-type SAD was compared using multinomial probability distribution tests. We also compared the ratio of summer SAD in individuals with vs. without air conditioners. Winter SAD and winter subsyndromal SAD (S-SAD) were significantly more prevalent than summer SAD and summer S-SAD. Those with access to air conditioners had a higher, rather than a lower, rate of summer SAD. Our results are consistent with prior studies that reported a lower prevalence of summer than winter SAD in Caucasian populations. Finding an increased rate of summer SAD in the minority of those with access to air conditioners was surprising and deserves replication. PMID:17619773

  18. Ion beam analysis of golden threads from Romanian medieval textiles

    NASA Astrophysics Data System (ADS)

    Balta, Z. I.; Csedreki, L.; Furu, E.; Cretu, I.; Huszánk, R.; Lupu, M.; Török, Z.; Kertész, Z.; Szikszai, Z.

    2015-04-01

    In this study, metal threads from Romanian religious embroideries and precious velvet brocades dated from 15th to 18th century were analyzed by using IBA methods (PIXE and RBS) which, in comparison to the traditional analytical techniques (XRF, EDS), allowed the detection of their structures and accurate identification of the trace elements (detection limits of few tens of ppm). PIXE results confirmed that both types of the metal threads studied - wires and strips - have layered structures being made of fine silver, refined by cupellation, and gilded most probably with pure gold, and not of Au-Ag alloy, or gilded Ag-Cu alloy or Au-Ag-Cu alloy, as resulted from the previously performed SEM-EDS analysis. Trace elements of historical interest like lead, mercury and bismuth have been also possible to be detected by PIXE. The resulting elemental maps allowed us to identify the areas from which the metal thread structure and quantitative composition could be accurately determined. RBS measurements revealed that the gilding layer is separated from the silver bulk by an interface layer resulting through atomic diffusion of silver into the gold, which lead to the conclusion that the methods used for gilding were probably either the diffusion bonding or the fire gilding. The gilding layers thicknesses were estimated by PIXE with the GUPIX software and also determined from RBS measurements.

  19. Pressurized heavy water reactor fuel behaviour in power ramp conditions

    NASA Astrophysics Data System (ADS)

    Ionescu, S.; Uţă, O.; Pârvan, M.; Ohâi, D.

    2009-03-01

    In order to check and improve the quality of the Romanian CANDU fuel, an assembly of six CANDU fuel rods has been subjected to a power ramping test in the 14 MW TRIGA reactor at INR. After testing, the fuel rods have been examined in the hot cells using post-irradiation examination (PIE) techniques such as: visual inspection and photography, eddy current testing, profilometry, gamma scanning, fission gas release and analysis, metallography, ceramography, burn-up determination by mass spectrometry, mechanical testing. This paper describes the PIE results from one out of the six fuel rods. The PIE results concerning the integrity, dimensional changes, oxidation, hydriding and mechanical properties of the sheath, the fission-products activity distribution in the fuel column, the pressure, volume and composition of the fission gas, the burn-up, the isotopic composition and structural changes of the fuel enabled the characterization of the behaviour of the Romanian CANDU fuel in power ramping conditions performed in the TRIGA materials testing reactor.

  20. Acrylamide in Romanian food using HPLC-UV and a health risk assessment.

    PubMed

    Oroian, Mircea; Amariei, Sonia; Gutt, Gheorghe

    2015-01-01

    The aim of this study was to investigate the level of acrylamide from coffee, potato chips and French fries in Romanian food. According to the European Food Safety Authority, coffee beans, potato chips and French fries have the highest levels of acrylamide. For this survey, 50 samples of coffee beans, 50 samples of potato chips and 25 samples of French fries were purchased from different producers from the Romanian market. Acrylamide levels have been quantified using high-performance liquid chromatography with a diode array detector (HPLC-DAD) method, using water as mobile phase. Health risk assessment was achieved by computing the average daily intake, hazard quotient, cumulative risk, carcinogenic risk and cancer risk. For coffee, potato chips and French fries, acrylamide was not shown to pose a health risk in Romanian food. PMID:25753750

  1. 76 FR 69296 - University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of Renewed...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-08

    ... published in the Federal Register on July 21, 2011 (76 FR 43733-43737). The NRC received no request for a..., 2011 (76 FR 60091-60094), and concluded that renewal of the facility operating license will not have a... COMMISSION University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of...

  2. A system model to integrate the “Green Manufacturing” concept in Romanian manufacturing organisation

    NASA Astrophysics Data System (ADS)

    Tilină, D. I.; Zapciu, M.; Mohora, C.

    2015-11-01

    In Romania, the large majorities of the manufacturing companies consume natural resources and energy in an unsustainable manner. Over the years, the emissions of greenhouse gases have led not only to many environmental problems but also to important social and economic problems. A real solution to help the Romanian manufacturing companies to adapt to the new legislative requirements is the green manufacturing implementation. Considering the current situation, the purpose of this paper is to present a model that will integrate the green manufacturing concept at the organizational level based on the practices identified in the Romanian manufacturing companies at the operational level in the context of sustainable development.

  3. Startup experience at the University of Texas TRIGA Mark II Reactor

    SciTech Connect

    Bauer, Thomas L.; Wehring, Bernard W.

    1992-07-01

    After eight years of singular effort, the UT-TRIGA Mark II research reactor was licensed and is fully operational. This reactor is the focus of a new reactor laboratory facility which is located at the Balcones Research Center, a north Austin campus of The University of Texas at Austin. The UT-TRIGA reactor is licensed for 1.1 MW steady power operation and 3 dollar pulsing. A startup program was implemented upon receipt of the facility license on January 17, 1992. Several facility features are unique to this startup. Among these were the use of fuel with various burnup and a digital control system. The reactor laboratory staff with assistance from a General Atomics instrumentation engineer performed all phases of the startup program. Core loading began in February 1992 with final testing completed in May 1992. Several unusual problems were encountered during this time. Experiment authorizations have been written to resume Neutron Activation Analysis programs and isotope production. Several neutron beam tube experiments are in the design and test phase. (author)

  4. Radionuclide mass inventory, activity, decay heat, and dose rate parametric data for TRIGA spent nuclear fuels

    SciTech Connect

    Sterbentz, J.W.

    1997-03-01

    Parametric burnup calculations are performed to estimate radionuclide isotopic mass and activity concentrations for four different Training, Research, and Isotope General Atomics (TRIGA) nuclear reactor fuel element types: (1) Aluminum-clad standard, (2) Stainless Steel-clad standard, (3) High-enrichment Fuel Life Improvement Program (FLIP), and (4) Low-enrichment Fuel Life Improvement Program (FLIP-LEU-1). Parametric activity data are tabulated for 145 important radionuclides that can be used to generate gamma-ray emission source terms or provide mass quantity estimates as a function of decay time. Fuel element decay heats and dose rates are also presented parametrically as a function of burnup and decay time. Dose rates are given at the fuel element midplane for contact, 3.0-feet, and 3.0-meter detector locations in air. The data herein are estimates based on specially derived Beginning-of-Life (BOL) neutron cross sections using geometrically-explicit TRIGA reactor core models. The calculated parametric data should represent good estimates relative to actual values, although no experimental data were available for direct comparison and validation. However, because the cross sections were not updated as a function of burnup, the actinide concentrations may deviate from the actual values at the higher burnups.

  5. Fundamental approach to TRIGA steady-state thermal-hydraulic CHF analysis

    SciTech Connect

    Feldman, E.E.

    2008-07-15

    Methods are investigated for predicting the power at which critical heat flux (CHF) occurs in TRIGA reactors that rely on natural convection for primary flow. For a representative TRIGA reactor, two sets of functions are created. For the first set, the General Atomics STAT code and the more widely-used RELAP5-3D code are each employed to obtain reactor flow rate as a function of power. For the second set, the Bernath correlation, the 2006 Groeneveld table, the Hall and Mudawar outlet correlation, and each of the four PG-CHF correlations for rod bundles are used to predict the power at which CHF occurs as a function of channel flow rate. The two sets of functions are combined to yield predictions of the power at which CHF occurs in the reactor. A combination of the RELAP5-3D code and the 2006 Groeneveld table predicts 67% more CHF power than does a combination of the STAT code and the Bernath correlation. (author)

  6. Cross sections for fuel depletion and radioisotope production calculations in TRIGA reactors

    SciTech Connect

    Aguilar, H.F.; Mazon, R.R.

    1994-07-01

    For TRIGA Reactors, the fuel depletion and isotopic inventory calculations, depends on the computer code and in the cross sections of some important actinides used. Among these we have U-235, U-238, Pu-239, Pu-240 and Pu-241. We choose ORIGEN2, a code with a good reputation in this kind of calculations, we observed the cross sections for these actinides in the libraries that we have (PWR's and BWR), the fission cross section for U-235 was about 50 barns. We used a PWR library and our results were not satisfactory, specially for standard elements. We decided to calculate cross sections more suitable for our reactor, for that purpose we simulate the standard and FLIP TRIGA cells with the transport code WIMS. We used the fuel average flux and COLAPS (a home made program), to generate suitable cross sections for ORIGEN2, by collapsing the WIMS library cross sections of these nuclides. For the radioisotope production studies using the Central Thimble, we simulate the A and B rings and used the A average flux to collapse cross sections. For these studies, the required nuclides sometimes are not present in WIMS library, for them we are planning to process the ENDF/B data, with NJOY system, and include the cross sections to WIMS library or to collapse them using the appropriate average-flux and the program COLAPS. (author)

  7. Reduced enrichment neutronics evaluation for Texas A and M's TRIGA reactor

    SciTech Connect

    Rajalakshmi, M.J.; Reuscher, J.A. )

    1990-06-01

    The Texas A and M Nuclear Science Center reactor (NSCR) designed by General Atomics (GA) uses a fuel-life improvement program TRIGA fuel element. It is composed of 8.5 wt% uranium in U-ZrH{sub 1.6}-Er fuel with a {sup 235}U enrichment of 70 at.% and 1.5 wt% of erbium. The US Nuclear Regulatory Commission requires that the enrichment not exceed 20 at.% for the next loading, provided the fuel is available. To meet this requirement GA has developed shrouded four-rod clusters using low-enriched U-ZrH{sub 1.6}-Er fuel for TRIGA cores operating at powers up to 2 MW. This fuel contains 20 wt% of uranium with an enrichment of 20 at.% and 0.5 wt% of erbium and a homogeneous mixture of hydrogen moderator. Thermal-hydraulic calculations show the feasibility of operating the NSCR at 2 MW. The objective of this study is to assess the ability of the NSCR to operate at 2 MW using the reduced-enrichment fuel. This study also covers a three-dimensional neutronics analysis of the NSCR core using the new fuel. Results obtained are compared with results obtained with another candidate fuel, BeO-UO{sub 2}-Er.

  8. Electron versus proton accelerator driven sub-critical system performance using TRIGA reactors at power

    SciTech Connect

    Carta, M.; Burgio, N.; D'Angelo, A.; Santagata, A.; Petrovich, C.; Schikorr, M.; Beller, D.; Felice, L. S.; Imel, G.; Salvatores, M.

    2006-07-01

    This paper provides a comparison of the performance of an electron accelerator-driven experiment, under discussion within the Reactor Accelerator Coupling Experiments (RACE) Project, being conducted within the U.S. Dept. of Energy's Advanced Fuel Cycle Initiative (AFCI), and of the proton-driven experiment TRADE (TRIGA Accelerator Driven Experiment) originally planned at ENEA-Casaccia in Italy. Both experiments foresee the coupling to sub-critical TRIGA core configurations, and are aimed to investigate the relevant kinetic and dynamic accelerator-driven systems (ADS) core behavior characteristics in the presence of thermal reactivity feedback effects. TRADE was based on the coupling of an upgraded proton cyclotron, producing neutrons via spallation reactions on a tantalum (Ta) target, with the core driven at a maximum power around 200 kW. RACE is based on the coupling of an Electron Linac accelerator, producing neutrons via photoneutron reactions on a tungsten-copper (W-Cu) or uranium (U) target, with the core driven at a maximum power around 50 kW. The paper is focused on analysis of expected dynamic power response of the RACE core following reactivity and/or source transients. TRADE and RACE target-core power coupling coefficients are compared and discussed. (authors)

  9. Ecological state of the Romanian Black Sea littoral lacustrine ecosystems

    NASA Astrophysics Data System (ADS)

    Gomoiu, M.-T.

    2009-04-01

    The author uses the results of his own researches as well as data from specialty literature to assess the ecological state of some typical lacustrine ecosystems considered, about 50 years ago, of major importance by their functions, services and researches, for the human populations in the settlements nearby. Based on this assessment the author recommends a few criteria which can be taken into account when programs of integrated management of these coastal ecosystems are initiated. The paper focuses on the study cases regarding the following major ecosystems: 1. Razelm-Sinoie Lagoon Complex - tightly linked to the Danube River and Delta systems, 2. Taşaul Lake - interfered in the last two decades by a branch of the DanubeRiver - Black Sea Canal and 3. Techirghiol Lake - for a long time under the sea level, a hyperhaline lake with therapeutic, sapropelic mud, disturbed by huge quantities of freshwaters infiltrated from the irrigation system. At present, the state of the lacustrine ecosystems at the Romanian Black Sea Coast can be characterized, mainly, by the following aspects: · Increase in the quantities of nutrients and chemical toxicants; · Rise in the level and frequency of eutrophication and pollution phenomena; · Drastic reduction of specific diversity; · Simplification of communities' structure - biocoenosis homogeneity; · Decrease in numerical abundance and biomass of benthic populations and consequently, low biofilter power by the decrease of the filter-feeder populations; · Worsening of the qualitative and the quantitative state of the biological benthic resources; · Thriving opportunistic forms (e.g. the worms causing sediment bioturbation); · Invasion by some exotic species, with harmful, unexpected consequences; · All populations undergo quantitative fluctuations; · Decrease in the fish population and in the use values of lacustrine assets, with strong impact on the welfare of the human society. Almost all pressure forms associated with the

  10. Romanian MRE Rocket Engines Program - An Early Endeavor

    NASA Astrophysics Data System (ADS)

    Rugescu, R. E.

    2002-01-01

    (MRE) was initiated in the years '60 of the past century at the Chair of Aerospace Sciences "Elie Carafoli" from the "Politehnica" University in Bucharest (PUB). Consisting of theoretical and experimental investigations in the form of computational methods and technological solutions for small size MRE-s and the concept of the test stand for these engines, the program ended in the construction of the first Romanian liquid rocket motors. Hermann Oberth and Dorin Pavel, were known from 1923, no experimental practice was yet tempted, at the time level of 1960. It was the intention of the developers at PUB to cover this gap and initiate a feasible, low-cost, demonstrative program of designing and testing experimental models of MRE. The research program was oriented towards future development of small size space carrier vehicles for scientific applications only, as an independent program with no connection to other defense programs imagined by the authorities in Bucharest, at that time. Consequently the entire financial support was assured by "Politehnica" university. computerized methods in the thermochemistry of heterogeneous combustion, for both steady and unsteady flows with chemical reactions and two phase flows. The research was gradually extended to the production of a professional CAD program for steady-state heat transfer simulations and the loading capacity analyses of the double wall, cooled thrust chamber. The resulting computer codes were run on a 360-30 IMB machine, beginning in 1968. Some of the computational methods were first exposed at the 9th International Conference on Applied Mechanics, held in Bucharest between June 23-27, 1969. hot testing of a series of storable propellant, variable thrust, variable geometry, liquid rocket motors, with a maximal thrust of 200N. A remotely controlled, portable test bad, actuated either automatically or manually and consisting of a 6-modules construction was built for this motor series, with a simple 8 analog

  11. Building an educational seismic network in Romanian schools

    NASA Astrophysics Data System (ADS)

    Zaharia, Bogdan; Tataru, Dragos; Grecu, Bogdan; Ionescu, Constantin; Bican-Brisan, Nicoleta; Neagoe, Cristian

    2014-05-01

    Understanding the earthquake phenomena and their effects is an important step toward the education of population and aims to raise the awareness about the earthquake risk and possible mitigation actions. In this sense, The Romanian Educational Seismic Network project represents an efficient communication tool, allowing teaching and learning about the earthquakes and seismic wave impact through experimental practices and educational activities. The seismic network consist of nine SEP seismometers installed in high-schools from the most important seismic areas (Vrancea, Banat, Făgăraş, Dobrogea), vulnerable cities (Bucharest, Iasi) or high populated places (Cluj, Sibiu, Timisoara, Zalău) and is coordinated by the National Institute of Earth Physics from Bucharest. Once installed, the seismic network is the starting point of activities for students through an e-learning platform. Some objectives are aimed: - To train students and teachers how to make analysis and interpretation of seismological data; - To make science more interesting for students; - To improve the participation rates in physical sciences for students; - To raise awareness of geoscience as a scientific discipline for pre-university students; - To promote the installation and effective use of educational seismographs and seismic data; - To reinforce and develop relationships between participating schools and research institutes; - To create an earthquake database this will be used by students and teachers for educational purposes. Different types of practical activities using educational seismometer, designed by researchers for students, are described in educational materials and in the web platform project. Also we encourage the teachers from the participating schools to share their experiences and produce new didactic tools for the classroom. This collaborative work could illustrate the conjugated efforts of researchers and teachers for a better education and awareness of the risk culture

  12. University of Illinois nuclear pumped laser program. [experiments with a TRIGA pulsed reactor with a broad pulse and a low peak flux

    NASA Technical Reports Server (NTRS)

    Miley, G. H.

    1979-01-01

    The development of nuclear pumped lasers with improved efficiency, energy storage capability, and UF6 volume pumping is reviewed. Results of nuclear pumped laser experiments using a TRIGA-type pulsed reactor are outlined.

  13. Evaluation of a Peer-Led Smoking Prevention Programme for Romanian Adolescents

    ERIC Educational Resources Information Center

    Lotrean, L. M.; Dijk, F.; Mesters, I.; Ionut, C.; De Vries, H.

    2010-01-01

    The goal of this study was to assess the effects of a school-based smoking prevention programme that used both a video and peer-led discussion groups among Romanian junior high school students aged 13-14 years. The programme embraced the social influence approach and concentrated on enhancing self-efficacy and the acquisition of cigarette refusal…

  14. Entrepreneurial University: Concurrent Practices in the US Business Higher Education System A Romanian Fulbright Scholar's View

    ERIC Educational Resources Information Center

    Paunescu, Carmen

    2006-01-01

    The paper addresses a model of entrepreneurial university embraced by American business schools as perceived by a Romanian Fulbright scholar. The purpose of this study was to highlight the practices pursued by the US entrepreneurial universities in their journey towards increasing performance excellence and strengthening the prestige of the…

  15. Copiii Din Romania Despre Drepturile Omului (Romanian Children about Human Rights). Children's Album.

    ERIC Educational Resources Information Center

    Georgescu, Dakmara

    This album addresses how civic education should be taught in Romanian schools. Civic education, like any other form of education, must be gradual and adapted to the specifics of the respective age. The album can be used by any person involved in developing future citizens. The document includes drawings and texts made by students who were apart of…

  16. A Critical Multicultural Analysis of a Romanian Textbook Taught in Elementary International Language Programs

    ERIC Educational Resources Information Center

    Stoilescu, Dorian

    2014-01-01

    This case study proposes a critical multicultural analysis of a Romanian language textbook used for instructing students in grades one and two in the Elementary Language International Program (ELIP) in Toronto public schools in Ontario, Canada. Based on an analysis developed from Fairclough and Parker's criteria, this paper determined stereotypes…

  17. Realities of Romanian Art. Fulbright-Hays Summer Seminars Abroad, 1997. (Romania and Bulgaria).

    ERIC Educational Resources Information Center

    Parrott, Meredith

    This document consists of a two-page outline and seventeen photographs of Romanian art objects. This unit focuses on advancing the high school student from the art of Western Europe to the art of Eastern Europe. The curriculum projects are geared for the 11th and 12th grade student. Students begin with a study of Rodin and progress toward that of…

  18. How Private Is the Relation with God? Religiosity and Family Religious Socialization in Romanian Emerging Adults

    ERIC Educational Resources Information Center

    Negru, Oana; Haragâs, Cosmina; Mustea, Anca

    2014-01-01

    This qualitative study explores the dynamics of religious cognitions, behaviors, and emotions in emerging adult discourse in a sample of Romanian youth of heterogeneous socioeconomic, denominational (Orthodox Christian, Roman Catholic, Neo-protestant), and educational background. Also, from a parent-child dyad perspective, we investigate the role…

  19. Longitudinal Studies Using a "Natural Experiment" Design: The Case of Adoptees from Romanian Institutions

    ERIC Educational Resources Information Center

    Rutter, Michael; Kumsta, Robert; Schlotz, Wolff; Sonuga-Barke, Edmund

    2012-01-01

    Objective: To summarize the advantages and limitations of general population, high-risk and "natural experiment" longitudinal studies for studying psychological change. The English and Romanian Adoptees study is used as an example of a "natural experiment," and detailed findings are provided. Method: What is new is a focus on the young people who…

  20. Behavior Problems in Postinstitutionalized Romanian Adoptees: Explanatory Parameters in the Adoptive Home

    ERIC Educational Resources Information Center

    Le Mare, Lucy; Audet, Karyn

    2014-01-01

    We examined behavior problems in 80 adolescents (39 male; mean age = 15.74 years) adopted in early childhood by Canadians from globally depriving Romanian institutions. Overall, rates of clinically significant behavior problems were comparable to rates found in younger postinstitutionalized adopted children. The association between duration of…

  1. Romanian Preschool Teachers' Understanding of Emotional and Behavioral Difficulties: Implications for Designing Teacher Trainings

    ERIC Educational Resources Information Center

    Stefan, Catrinel A.; Rebega, Oana L.; Cosma, Alina

    2015-01-01

    Researchers have emphasized the role of the teacher-child relationship on children's adjustment. Children lacking such positive relationships are placed at increased risk for emotional and behavioral difficulties (EBD). We propose a qualitative approach to exploring Romanian teachers' knowledge and strategies related to preschoolers who…

  2. Comparative Analysis of the Mathematics Problems Given at International Tests and at the Romanian National Tests

    ERIC Educational Resources Information Center

    Marchis, Iuliana

    2009-01-01

    The results of the Romanian pupils on international tests PISA and TIMSS in Mathematics are below the average. These poor results have many explications. In this article we compare the Mathematics problems given on these international tests with those given on national tests in Romania.

  3. Health Information in Romanian (Română): MedlinePlus

    MedlinePlus

    ... Search Search MedlinePlus GO GO About MedlinePlus Site Map FAQs Contact Us Health Topics Drugs & Supplements Videos & Tools You Are Here: Home → Multiple Languages → Romanian (Română) URL of this page: https://www.nlm. ...

  4. A Longitudinal Study of Service Use in Families of Children Adopted from Romanian Orphanages

    ERIC Educational Resources Information Center

    Le Mare, Lucy; Audet, Karyn; Kurytnik, Karen

    2007-01-01

    Post-adoption service use and unmet service needs were examined longitudinally in three matched groups of children: children adopted from Romanian orphanages following a minimum of eight months' institutional experience (RO: n = 36); children from Romania who were destined for orphanages but were adopted early in infancy (EA: n = 25); and Canadian…

  5. A Three Way Analysis of the Academic Capital of a Romanian University

    ERIC Educational Resources Information Center

    Prejmerean, Mihaela Cornelia; Vasilache, Simona

    2008-01-01

    The paper applies three-way analysis (Kroonenberg, 1982, 2008) to the components of academic capital of a Romanian university, over a five-year period, showing the biases and the relations between the various components. The influences from inside the academia are being discussed, together with analyzing their positive or not so positive effect on…

  6. A Comparative Study of Learning Strategies Used by Romanian and Hungarian Preuniversity Students in Science Learning

    ERIC Educational Resources Information Center

    Lingvay, Mónika; Timofte, Roxana S.; Ciascai, Liliana; Predescu, Constantin

    2015-01-01

    Development of pupils' deep learning approach is an important goal of education nowadays, considering that a deep learning approach is mediating conceptual understanding and transfer. Different performance at PISA tests of Romanian and Hungarian pupils cause us to commence a study for the analysis of learning approaches employed by these pupils.…

  7. Resiliency in the Aftermath of Deprivation: A Second Look at the Development of Romanian Orphanage Children.

    ERIC Educational Resources Information Center

    Morison, Sara J.; Ellwood, Ann-Louise

    2000-01-01

    Examined cognitive development in children adopted after at least eight months in a Romanian orphanage, and evaluated the influence of a stable adoptive family and home environment on their development. Found that subjects scored lower than comparison group of nonadopted, never institutionalized children on all cognitive measures, and on most…

  8. Behavioural Indicators of Perceived Managerial and Leadership Effectiveness within Romanian and British Public Sector Hospitals

    ERIC Educational Resources Information Center

    Hamlin, Robert G.; Patel, Taran

    2012-01-01

    Purpose: This paper aims to report the results of a replication study of perceived managerial and leadership effectiveness within a Romanian public sector hospital, and to discuss the extent to which they are similar to and different from findings from equivalent studies carried out in two British NHS Trust hospitals. Design/methodology/approach:…

  9. Romanian Pupils at the Spanish Primary Schools: Continuities and Discontinuities between Former and Current Educational Experiences

    ERIC Educational Resources Information Center

    Ion, Georgeta

    2011-01-01

    During the last few years, East-Europeans, predominantly Romanians, have become the second largest cultural minority in Catalonia (Spain). Spanish educational institutions now have students from more than twenty different cultures. This paper focuses on the educational background and the factors which characterize the educational experience of…

  10. Civil Society and Control of Corruption: Assessing Governance of Romanian Public Universities

    ERIC Educational Resources Information Center

    Mungiu-Pippidi, Alina; Dusu, Andra Elena

    2011-01-01

    Romania is perceived as the most corrupt EU member state according to Transparency International Corruption Perception Index. In 2008-2009, a grassroots coalition of civil society organizations and education stakeholders created the Coalition for Clean Universities which organized the first assessment of integrity of the Romanian higher education…

  11. The Romanian-English Contrastive Analysis Project; Further Developments in Contrastive Studies, Vol. 5.

    ERIC Educational Resources Information Center

    Chitoran, Dumitru, Ed.

    The fifth volume in this series contains ten articles dealing with various aspects of Romanian-English contrastive analysis. They are: "Theoretical Interpretation and Methodological Consequences of 'REGULARIZATION'," by Tatiana Slama-Cazacu; "On Error Analysis," by Charles M. Carlton; "The Contrastive Hypothesis in Second Language Acquisition," by…

  12. Relative fission product yield determination in the USGS TRIGA Mark I reactor

    NASA Astrophysics Data System (ADS)

    Koehl, Michael A.

    Fission product yield data sets are one of the most important and fundamental compilations of basic information in the nuclear industry. This data has a wide range of applications which include nuclear fuel burnup and nonproliferation safeguards. Relative fission yields constitute a major fraction of the reported yield data and reduce the number of required absolute measurements. Radiochemical separations of fission products reduce interferences, facilitate the measurement of low level radionuclides, and are instrumental in the analysis of low-yielding symmetrical fission products. It is especially useful in the measurement of the valley nuclides and those on the extreme wings of the mass yield curve, including lanthanides, where absolute yields have high errors. This overall project was conducted in three stages: characterization of the neutron flux in irradiation positions within the U.S. Geological Survey TRIGA Mark I Reactor (GSTR), determining the mass attenuation coefficients of precipitates used in radiochemical separations, and measuring the relative fission products in the GSTR. Using the Westcott convention, the Westcott flux, modified spectral index, neutron temperature, and gold-based cadmium ratios were determined for various sampling positions in the USGS TRIGA Mark I reactor. The differential neutron energy spectrum measurement was obtained using the computer iterative code SAND-II-SNL. The mass attenuation coefficients for molecular precipitates were determined through experiment and compared to results using the EGS5 Monte Carlo computer code. Difficulties associated with sufficient production of fission product isotopes in research reactors limits the ability to complete a direct, experimental assessment of mass attenuation coefficients for these isotopes. Experimental attenuation coefficients of radioisotopes produced through neutron activation agree well with the EGS5 calculated results. This suggests mass attenuation coefficients of molecular

  13. Accuracy studies with carbon clusters at the Penning trap mass spectrometer TRIGA-TRAP

    NASA Astrophysics Data System (ADS)

    Ketelaer, J.; Beyer, T.; Blaum, K.; Block, M.; Eberhardt, K.; Eibach, M.; Herfurth, F.; Smorra, C.; Nagy, Sz.

    2010-05-01

    Extensive cross-reference measurements of well-known frequency ratios using various sizes of carbon cluster ions 12Cn + (10≤n≤23) were performed to determine the effects limiting the accuracy of mass measurements at the Penning-trap facility TRIGA-TRAP. Two major contributions to the uncertainty of a mass measurement have been identified. Fluctuations of the magnetic field cause an uncertainty in the frequency ratio due to the required calibration by a reference ion of uf(νref)/νref = 6(2) × 10-11/min × Δt. A mass-dependent systematic shift of the frequency ratio of epsilonm(r)/r = -2.2(2) × 10-9 × (m-mref)/u has been found as well. Finally, the nuclide 197Au was used as a cross-check since its mass is already known with an uncertainty of 0.6 keV.

  14. An iterative approach for TRIGA fuel burn-up determination using nondestructive gamma-ray spectrometry.

    PubMed

    Wang, T K; Peir, J J

    2000-01-01

    The purpose of this work is to establish a method for evaluating the burn-up values of the rod-type TRIGA spent fuel by using gamma-ray spectrometry of the short-lived fission products 97Zr/97Nb, 132I, and 140La. Fuel irradiation history is not needed in this method. Short-lived fission-product activities were established by reirradiating the spent fuels in a nuclear reactor. Based on the measured activities, 235U burn-up values can be deduced by iterative calculations. The complication caused by 239Pu production and fission is also discussed in detail. The burn-up values obtained by this method are in good agreement with those deduced from the conventional method based on long-lived fission products 137Cs, 134Cs/137Cs ratio and 106Ru/137Cs ratio. PMID:10670930

  15. Neutron spectra at two beam ports of a TRIGA Mark III reactor loaded with HEU fuel.

    PubMed

    Vega-Carrillo, H R; Hernández-Dávila, V M; Aguilar, F; Paredes, L; Rivera, T

    2014-01-01

    The neutron spectra have been measured in two beam ports, one radial and another tangential, of the TRIGA Mark III nuclear reactor from the National Institute of Nuclear Research in Mexico. Measurements were carried out with the reactor core loaded with high enriched uranium fuel. Two reactor powers, 5 and 10 W, were used during neutron spectra measurements using a Bonner sphere spectrometer with a (6)LiI(Eu) scintillator and 2, 3, 5, 8, 10 and 12 in.-diameter high-density polyethylene spheres. The neutron spectra were unfolded using the NSDUAZ unfolding code. For each spectrum total flux, mean energy and ambient dose equivalent were determined. Measured spectra show fission, epithermal and thermal neutrons, being harder in the radial beam port. PMID:23746708

  16. The characteristic assessment of spent ion exchange resin from PUSPATI TRIGA REACTOR (RTP) for immobilization process

    SciTech Connect

    Wahida, Nurul; Yasir, Muhamad Samudi; Majid, Amran Ab; Irwan, M. N.; Wahab, Mohd Abd; Marzukee, Nik; Paulus, Wilfred; Phillip, Esther; Thanaletchumy

    2014-09-03

    In this paper, spent ion exchange resin generated from PUSPATI TRIGA reactor (RTP) in Malaysian Nuclear Agency were characterized based on the water content, radionuclide content and radionuclide leachability. The result revealed that the water content in the spent resin is 48%. Gamma spectrometry analysis indicated the presence of {sup 134}Cs, {sup 137}Cs, {sup 152}Eu, {sup 54}Mn, {sup 58}Co, {sup 60}Co and {sup 65}Zn. The leachability test shows a small concentrations (<1 Bq/l) of {sup 152}Eu and {sup 134}Cs were leached out from the spent resin while {sup 60}Co activity concentrations slightly exceeded the limit generally used for industrial wastewater i.e. 1 Bq/l. Characterization of spent ion exchange resin sampled from RTP show that this characterization is important as a basis to immobilize this radioactive waste using geopolymer technology.

  17. Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element

    NASA Astrophysics Data System (ADS)

    Mohammed, Abdul Aziz; Pauzi, Anas Muhamad; Rahman, Shaik Mohmmed Haikhal Abdul; Zin, Muhamad Rawi Muhammad; Jamro, Rafhayudi; Idris, Faridah Mohamad

    2016-01-01

    In confronting global energy requirement and the search for better technologies, there is a real case for widening the range of potential variations in the design of nuclear power plants. Smaller and simpler reactors are attractive, provided they can meet safety and security standards and non-proliferation issues. On fuel cycle aspect, thorium fuel cycles produce much less plutonium and other radioactive transuranic elements than uranium fuel cycles. Although not fissile itself, Th-232 will absorb slow neutrons to produce uranium-233 (233U), which is fissile. By introducing Thorium, the numbers of highly enriched uranium fuel element can be reduced while maintaining the core neutronic performance. This paper describes the core kinetic of a small research reactor core like TRIGA fueled with a Th filled fuel element matrix using a general purpose Monte Carlo N-Particle (MCNP) code.

  18. Operation and reactivity measurements of an accelerator driven subcritical TRIGA reactor

    NASA Astrophysics Data System (ADS)

    O'Kelly, David Sean

    Experiments were performed at the Nuclear Engineering Teaching Laboratory (NETL) in 2005 and 2006 in which a 20 MeV linear electron accelerator operating as a photoneutron source was coupled to the TRIGA (Training, Research, Isotope production, General Atomics) Mark II research reactor at the University of Texas at Austin (UT) to simulate the operation and characteristics of a full-scale accelerator driven subcritical system (ADSS). The experimental program provided a relatively low-cost substitute for the higher power and complexity of internationally proposed systems utilizing proton accelerators and spallation neutron sources for an advanced ADSS that may be used for the burning of high-level radioactive waste. Various instrumentation methods that permitted ADSS neutron flux monitoring in high gamma radiation fields were successfully explored and the data was used to evaluate the Stochastic Pulsed Feynman method for reactivity monitoring.

  19. Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia.

    PubMed

    Yavar, A R; Khalafi, H; Kasesaz, Y; Sarmani, S; Yahaya, R; Wood, A K; Khoo, K S

    2012-10-01

    A 3-D model for 1 MW TRIGA Mark II research reactor was simulated. Neutron flux parameters were calculated using MCNP-4C code and were compared with experimental results obtained by k(0)-INAA and absolute method. The average values of φ(th),φ(epi), and φ(fast) by MCNP code were (2.19±0.03)×10(12) cm(-2)s(-1), (1.26±0.02)×10(11) cm(-2)s(-1) and (3.33±0.02)×10(10) cm(-2)s(-1), respectively. These average values were consistent with the experimental results obtained by k(0)-INAA. The findings show a good agreement between MCNP code results and experimental results. PMID:22885391

  20. Irradiation facility at the TRIGA Mainz for treatment of liver metastases.

    PubMed

    Hampel, G; Wortmann, B; Blaickner, M; Knorr, J; Kratz, J V; Lizón Aguilar, A; Minouchehr, S; Nagels, S; Otto, G; Schmidberger, H; Schütz, C; Vogtländer, L

    2009-07-01

    The TRIGA Mark II reactor at the University of Mainz provides ideal conditions for duplicating BNCT treatment as performed in Pavia, Italy, in 2001 and 2003 [Pinelli, T., Zonta, A., Altieri, S., Barni, S., Braghieri, A., Pedroni, P., Bruschi, P., Chiari, P., Ferrari, C., Fossati, F., Nano, R., Ngnitejeu Tata, S., Prati, U., Ricevuti, G., Roveda, L., Zonta, C., 2002. TAOrMINA: from the first idea to the application to the human liver. In: Sauerwein et al. (Eds.), Research and Development in Neutron Capture Therapy. Proceedings of the 10th International Congress on Neutron Capture Therapy, Monduzzi editore, Bologna, pp. 1065-1072]. In order to determine the optimal parameters for the planned therapy and therefore for the design of the thermal column, calculations were conducted using the MCNP-code and the transport code ATTILA. The results of the parameter study as well as a possible configuration for the irradiation of the liver are presented. PMID:19394836

  1. The characteristic assessment of spent ion exchange resin from PUSPATI TRIGA REACTOR (RTP) for immobilization process

    NASA Astrophysics Data System (ADS)

    Wahida, Nurul; Yasir, Muhamad Samudi; Majid, Amran Ab; Wahab, Mohd Abd; Marzukee, Nik; Paulus, Wilfred; Phillip, Esther; Thanaletchumy, Irwan, M. N.

    2014-09-01

    In this paper, spent ion exchange resin generated from PUSPATI TRIGA reactor (RTP) in Malaysian Nuclear Agency were characterized based on the water content, radionuclide content and radionuclide leachability. The result revealed that the water content in the spent resin is 48%. Gamma spectrometry analysis indicated the presence of 134Cs, 137Cs, 152Eu, 54Mn, 58Co, 60Co and 65Zn. The leachability test shows a small concentrations (<1 Bq/l) of 152Eu and 134Cs were leached out from the spent resin while 60Co activity concentrations slightly exceeded the limit generally used for industrial wastewater i.e. 1 Bq/l. Characterization of spent ion exchange resin sampled from RTP show that this characterization is important as a basis to immobilize this radioactive waste using geopolymer technology.

  2. Thermal hydraulic analysis for the Oregon State TRIGA reactor using RELAP5-3D

    SciTech Connect

    Marcum, W.R.; Woods, B.G.; Hartman, M.

    2008-07-15

    Thermal hydraulic analyses have being conducted at Oregon State University (OSU) in support of the conversion of the OSU TRIGA reactor (OSTR) core from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel as part of the Reduced Enrichment for Research and Test Reactors program. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both the HEU and LEU cores; calculate peak values of fuel temperature, cladding temperature, surface heat flux as well as departure from nuclear boiling ratio (DNBR) for steady state and pulse operation; and perform accident analyses for the accident scenarios identified in the OSTR safety analysis report. RELAP5-3D Version 2.4.2 was implemented to develop a model for the thermal hydraulic study. The OSTR core conversion is planned to take place in late 2008. (author)

  3. Development process of the new control console of ININ's TRIGA mark III reactor

    SciTech Connect

    Rivero-Gutierrez, T.

    2006-07-01

    A description of the development of the new ININ's TRIGA Mark III reactor control console is presented in this meeting. Most of the operation and safety monitoring of the reactor is carried out by means of a personal computer (PC), some interface cards, and an auxiliary computer that drives the control rod mechanisms. In this console, the safety actions are taken by the Protection System (SEC), which acquires the data directly from the safety related systems, specified in the reactor's console design technical specifications. The console, based on the concept of virtual instrumentation, is composed of a group of systems that make easier to the operator the activation of the sequential steps required to operate the reactor. (authors)

  4. Core Calculation of 1 MWatt PUSPATI TRIGA Reactor (RTP) using Monte Carlo MVP Code System

    SciTech Connect

    Karim, Julia Abdul

    2008-05-20

    The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speed by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained.

  5. Final qualification testing results for TRIGA low-enriched uranium fuel

    SciTech Connect

    West, G.B.; Simnad, M.T.; Copeland, G.L.

    1987-01-01

    Following the adoption of policies by the US government and other fuel supplier nations to limit, with few exceptions, export of fuels to those enriched to < 20% in /sup 235/U, GA Technologies undertook, starting in 1976, a rigorous program to develop uranium zirconium-hydride fuels with high uranium concentrations up to 3.7 g U/cm/sup 3/, while limiting the enrichment to < 20% in /sup 235/U. By increasing the uranium concentration from 8.5 to 45 wt% and by including erbium as a burnable poison, the long reactivity lifetime of the high-enriched uranium cores has been preserved. The achieved purpose of these low-enriched uranium (LEU) fuels was also to preserve all the unique safety features of the TRIGA fuel system - prompt negative temperature coefficient of reactivity, high fission product retentivity, chemical stability when quenched from high temperatures in water, and dimensional stability over a broad range of operating temperatures.

  6. Criticality safety assessment of a TRIGA reactor spent-fuel pool under accident conditions

    SciTech Connect

    Glumac, B; Ravnik, M.; Logar, M.

    1997-02-01

    Additional criticality safety analysis of a pool-type storage for TRIGA spent fuel at the Jozef Stefan Institute in Ljubljana, Slovenia, is presented. Previous results have shown that subcriticality is not guaranteed for some postulated accidents (earthquake with subsequent fuel rack disintegration resulting in contact fuel pitch) under the assumption that the fuel rack is loaded with fresh 12 wt% standard fuel. To mitigate this deficiency, a study was done on replacing a certain number of fuel elements in the rack with cadmium-loaded absorber rods. The Monte Carlo computer code MCNP4A with an ENDF/B-V library and detailed three-dimensional geometrical model of the spent-fuel rack was used for this purpose. First, a minimum critical number of fuel elements was determined for contact pitch, and two possible geometries of rack disintegration were considered. Next, it was shown that subcriticality can be ensured when pitch is decreased from a rack design pitch of 8 cm to contact, if a certain number of fuel elements (8 to 20 out of 70) are replaced by absorber rods, which are uniformly mixed into the lattice. To account for the possibility that random mixing of fuel elements and absorber rods can occur during rack disintegration and result in a supercritical configuration, a probabilistic study was made to sample the probability density functions for random absorber rod lattice loadings. Results of the calculations show that reasonably low probabilities for supercriticality can be achieved (down to 10{sup {minus}6} per severe earthquake, which would result in rack disintegration and subsequent maximum possible pitch decrease) even in the case where fresh 12 wt% standard TRIGA fuel would be stored in the spent-fuel pool.

  7. McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: Four years of operations

    SciTech Connect

    Heidel, C.C.; Richards, W.J.

    1994-07-01

    McClellan Air Force Base, at Sacramento, California, is headquarters for the Sacramento Air Force Logistics Center (SM-ALC). McClellan Air Force Base provides extensive inspection and maintenance capabilities for the F-111, F-1 5, and other military aircraft. Criticality of the MNRC TRIGA reactor was obtained on January 20, 1990 with 63 standard TRIGA fuel elements, three fuel-followed control rods and one air-followed control rod. Presently there are 93 fuel elements in the reactor core. The reactor can be operated at 1 MW steady state power, producing pulses up to three dollars worth of reactivity addition, and can be square waved up to 1 MW. The reactor core contains a circular grid plate and a graphite reflector assembly surrounding the core. Four tangential beam ports installed in the reflector assembly provide a thermal neutron flux to four radiography bays. The reactor tank is twenty-four (24) feet deep, seven and one-half (7.5) feet in diameter, and has a protrusion in the upper portion of the reactor tank. This protrusion is scheduled for use as a neutron thermal collimator in the future. Besides the neutron radiography capabilities, the reactor contains a pneumatic rabbit system, a central thimble, an in-core irradiation facility, and three additional cutouts that provide locations for additional irradiation facilities. The central thimble can be removed along with the B-ring locations of the upper portion of the grid plate to provide an additional and larger in-core irradiation facility. A new upper grid plate has been manufactured to expand one triangular cutout so that larger experiments can be inserted directly into the reactor core. Some operational problems experienced during the first four years of operations are the timeout of the CSC and DAC watchdogs, deterioration of the heat exchanger gaskets, and loss of thermocouples in the instrumented fuel elements. (author)

  8. Neutronic and thermal hydraulic analysis of the Geological Survey TRIGA Reactor

    NASA Astrophysics Data System (ADS)

    Shugart, Nicolas

    The United States Geological Survey TRIGA Reactor (GSTR) is a 1 MW reactor located in Lakewood, Colorado. In support of the GSTR's relicensing efforts, this project developed and validated a Monte Carlo N-Particle Version 5 (MCNP5) model of the GSTR reactor. The model provided estimates of the excess reactivity, power distribution and the fuel temperature, water temperature, void, and power reactivity coefficients for the current and limiting core. The MCNP5 model predicts a limiting core excess reactivity of 6.48 with a peak rod power of 22.2 kW. The fuel and void reactivity coefficients for the limiting core are strongly negative, and the core water reactivity coefficient is slightly positive, consistent with other TRIGA analyses. The average fuel temperature reactivity coefficient of the full power limiting core is -0.0135 /K while the average core void coefficient is -0.069 /K from 0-20 % void. The core water temperature reactivity coefficient is +0.012 /K. Following the neutronics analysis, the project developed RELAP5 and PARET-ANL models of the GSTR hot-rod fuel channel under steady state and transient conditions. The GSTR limiting core, determined as part of this analysis, provides a worst case operating scenario for the reactor. During steady state operations, the hot rod of the limiting core has a peak fuel temperature of 829 K and a minimum departure from nucleate boiling ratio of 2.16. After a $3.00 pulse reactivity insertion the fuel reaches a peak temperature is 1070 K. Examining the model results several seconds after a pulse reveals flow instabilities that result from weaknesses in the current two-channel model.

  9. Ecological state of the Romanian Black Sea littoral lacustrine ecosystems

    NASA Astrophysics Data System (ADS)

    Gomoiu, M.-T.

    2009-04-01

    The author uses the results of his own researches as well as data from specialty literature to assess the ecological state of some typical lacustrine ecosystems considered, about 50 years ago, of major importance by their functions, services and researches, for the human populations in the settlements nearby. Based on this assessment the author recommends a few criteria which can be taken into account when programs of integrated management of these coastal ecosystems are initiated. The paper focuses on the study cases regarding the following major ecosystems: 1. Razelm-Sinoie Lagoon Complex - tightly linked to the Danube River and Delta systems, 2. Taşaul Lake - interfered in the last two decades by a branch of the DanubeRiver - Black Sea Canal and 3. Techirghiol Lake - for a long time under the sea level, a hyperhaline lake with therapeutic, sapropelic mud, disturbed by huge quantities of freshwaters infiltrated from the irrigation system. At present, the state of the lacustrine ecosystems at the Romanian Black Sea Coast can be characterized, mainly, by the following aspects: · Increase in the quantities of nutrients and chemical toxicants; · Rise in the level and frequency of eutrophication and pollution phenomena; · Drastic reduction of specific diversity; · Simplification of communities' structure - biocoenosis homogeneity; · Decrease in numerical abundance and biomass of benthic populations and consequently, low biofilter power by the decrease of the filter-feeder populations; · Worsening of the qualitative and the quantitative state of the biological benthic resources; · Thriving opportunistic forms (e.g. the worms causing sediment bioturbation); · Invasion by some exotic species, with harmful, unexpected consequences; · All populations undergo quantitative fluctuations; · Decrease in the fish population and in the use values of lacustrine assets, with strong impact on the welfare of the human society. Almost all pressure forms associated with the

  10. Romanian wild boars and Mangalitza pigs have a European ancestry and harbour genetic signatures compatible with past population bottlenecks

    PubMed Central

    Manunza, A.; Amills, M.; Noce, A.; Cabrera, B.; Zidi, A.; Eghbalsaied, S.; de Albornoz, E. Carrillo; Portell, M.; Mercadé, A.; Sànchez, A.; Balteanu, V.

    2016-01-01

    We aimed to analyse the genetic diversity of Romanian wild boars and to compare it with that from other wild boar and pig populations from Europe and Asia. Partial sequencing of the mitochondrial encoded cytochrome b (MT-CYB) gene from 36 Romanian wild boars and 36 domestic pigs (Mangalitza, Bazna and Vietnamese breeds) showed that the diversity of Romanian wild boars and Mangalitza pigs is fairly reduced, and that most of the members of these two populations share a common MT-CYB haplotype. Besides, in strong contrast with the Bazna animals, Romanian wild boars and Mangalitza swine did not carry Asian variants at the MT-CYB locus. The autosomal genotyping of 18 Romanian wild boars with the Illumina Porcine SNP60 BeadChip revealed that their genetic background is fundamentally European, even though signs of a potential Near Eastern ancestry (~25%) were detectable at K = 4 (the most significant number of clusters), but not at higher K-values. Admixture analysis also showed that two wild boars are of a hybrid origin, which could be explained by the mating of feral animals with domestic pigs. Finally, a number of Romanian wild boars displayed long runs of homozygosity, an observation that is consistent with the occurrence of past population bottlenecks and the raise of inbreeding possibly due to overhunting or to the outbreak of infectious diseases. PMID:27418428