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Sample records for austrian triga-mark-ii reactor

  1. Utilization of Slovenian TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Snoj, L.; Smodis, B.

    2010-01-01

    TRIGA Mark II research reactor at the Jozef Stefan Institute [JSI] is extensively used for various applications, such as: irradiation of various samples, training and education, verification and validation of nuclear data and computer codes, testing and development of experimental equipment used for core physics tests at a nuclear power plant. The paper briefly describes the aforementioned activities and shows that even such small reactors are still indispensable in nuclear science and technology. (author)

  2. Decontamination of TRIGA Mark II reactor, Indonesia

    International Nuclear Information System (INIS)

    Suseno, H.; Daryoko, M.; Goeritno, A.

    2002-01-01

    The TRIGA Mark II Reactor in the Centre for Research and Development Nuclear Technique Bandung has been partially decommissioned as part of an upgrading project. The upgrading project was carried out from 1995 to 2000 and is being commissioned in 2001. The decommissioning portion of the project included disassembly of some components of the reactor core, producing contaminated material. This contaminated material (grid plate, reflector, thermal column, heat exchanger and pipe) will be sent to the Decontamination Facility at the Radioactive Waste Management Development Centre. (author)

  3. Decommissioning of TRIGA Mark II type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Dooseong; Jeong, Gyeonghwan; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    The first research reactor in Korea, KRR 1, is a TRIGA Mark II type with open pool and fixed core. Its power was 100 kWth at its construction and it was upgraded to 250 kWth. Its construction was started in 1957. The first criticality was reached in 1962 and it had been operated for 36,000 hours. The second reactor, KRR 2, is a TRIGA Mark III type with open pool and movable core. These reactors were shut down in 1995, and the decision was made to decommission both reactors. The aim of the decommissioning activities is to decommission the KRR 2 reactor and decontaminate the residual building structures and site, and to release them as unrestricted areas. The KRR 1 reactor was decided to be preserve as a historical monument. A project was launched for the decommissioning of these reactors in 1997, and approved by the regulatory body in 2000. A total budget for the project was 20.0 million US dollars. It was anticipated that this project would be completed and the site turned over to KEPCO by 2010. However, it was discovered that the pool water of the KRR 1 reactor was leaked into the environment in 2009. As a result, preservation of the KRR 1 reactor as a monument had to be reviewed, and it was decided to fully decommission the KRR 1 reactor. Dismantling of the KRR 1 reactor takes place from 2011 to 2014 with a budget of 3.25 million US dollars. The scope of the work includes licensing of the decommissioning plan change, removal of pool internals including the reactor core, removal of the thermal and thermalizing columns, removal of beam port tubes and the aluminum liner in the reactor tank, removal of the radioactive concrete (the entire concrete structure will not be demolished), sorting the radioactive waste (concrete and soil) and conditioning the radioactive waste for final disposal, and final statuses of the survey and free release of the site and building, and turning over the site to KEPCO. In this paper, the current status of the TRIGA Mark-II type reactor

  4. Evaluation of TRIGA Mark II reactor in Turkey

    International Nuclear Information System (INIS)

    Bilge, Ali Nezihi

    1990-01-01

    There are two research reactors in Turkey and one of them is the university Triga Mark II reactor which was in service since 1979 both for education and industrial application purposes. The main aim of this paper is to evaluate the spectrum of the services carried by Turkish Triga Mark II reactor. In this work, statistical distribution of the graduate works and applications, by using Triga Mark II reactor is examined and evaluated. In addition to this, technical and scientific uses of this above mentioned reactor are also investigated. It was already showed that the uses and benefits of this reactor can not be limited. If the sufficient work and service is given, NDT and industrial applications can also be carried economically. (orig.)

  5. Probabilistic Safety Assessment Of It TRIGA Mark-II Reactor

    International Nuclear Information System (INIS)

    Ergun, E; Kadiroglu, O.S.

    1999-01-01

    The probabilistic safety assessment for Istanbul Technical University (ITU) TRIGA Mark-II reactor is performed. Qualitative analysis, which includes fault and event trees and quantitative analysis which includes the collection of data for basic events, determination of minimal cut sets, calculation of quantitative values of top events, sensitivity analysis and importance measures, uncertainty analysis and radiation release from fuel elements are considered

  6. Performances on nuclear activation analysis by TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Capannesi, G.; Rosada, A.

    1986-01-01

    Progresses in methodological research and connected applications in the field of activation analysis are introduced. Some peculiar characteristics on the TRIGA MARK II reactor have enabled the possibility of obtaining interesting results. The particular, the rotating radiation device Lazy Susan, with a capability of 40 positionings, permits homogeneity in neutron flux and energy spectrum stability within 15%. High level of precision and accuracy are obtained in analytic. Applications of major interest have been: - reference material certification; - forensic applications; - electrolytic cell productivity evaluation. The TRIGA MARK II reactor is equipped with a thermal column throughout a D 2 O diaphragm with a thickness of 70 cm. The available neutron flux has no fast and epithermal components. Via this facility a method has been tested for the instrumental determination of Al in Si metal of solar and electronic degree. (author)

  7. Corrosion problem in the CRENK Triga Mark II research reactor

    International Nuclear Information System (INIS)

    Kalenga, M.

    1990-01-01

    In August 1987, a routine underwater optical inspection of the aluminum tank housing the core of the CRENK Triga Mark II reactor, carried out to update safety condition of the reactor, revealed pitting corrosion attacks on the 8 mm thick aluminum tank bottom. The paper discuss the work carried out by the reactor staff to dismantle the reactor in order to allow a more precise investigation of the corrosion problem, to repair the aluminum tank bottom, and to enhance the reactor overall safety condition

  8. The optimal control of ITU TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    Can, Burhanettin

    2008-01-01

    In this study, optimal control of ITU TRIGA Mark-II Reactor is discussed. A new controller has been designed for ITU TRIGA Mark-II Reactor. The controller consists of main and auxiliary controllers. The form is based on Pontragyn's Maximum Principle and the latter is based on PID approach. For the desired power program, a cubic function is chosen. Integral Performance Index includes the mean square of error function and the effect of selected period on the power variation. YAVCAN2 Neutronic - Thermal -Hydraulic code is used to solve the equations, namely 11 equations, dealing with neutronic - thermal - hydraulic behavior of the reactor. For the controller design, a new code, KONTCAN, is written. In the application of the code, it is seen that the controller controls the reactor power to follow the desired power program. The overshoot value alters between 100 W and 500 W depending on the selected period. There is no undershoot. The controller rapidly increases reactivity, then decreases, after that increases it until the effect of temperature feedback is compensated. Error function varies between 0-1 kW. (author)

  9. Ageing Management in the CENM Triga Mark II Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    El Younoussi, C.; Nacir, B.; El Bakkari, B.; Boulaich, Y. [Centre for Nuclear Studies of Maâmora (CENM), National Centre of Energy Sciences and Nuclear Techniques (CNESTEN), Rabat (Morocco)

    2014-08-15

    Physical ageing is one of the most important factors that may reduce the safety margins calculated in the design of safety system components of a research reactor. In this context, special efforts are necessary for ensuring the safety of research reactors through appropriate ageing management actions. The paper deals with the overall aspects of the ageing management system of the Moroccan TRIGA Mark II research reactor. The management system covers among others, management of structures, critical components inspections, the control command system and nuclear instrumentation verification. The paper presents also how maintenance and periodic testing are organized and managed in the reactor module. Practical examples of ageing management actions of some systems and components during recent years are presented. (author)

  10. Preliminary neutronic design of TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    Sarikaya, B.; Tombakoglu, M.; Cecen, Y.; Kadiroglu, O. K.

    2001-01-01

    It is very important to analyse the behaviour of the research reactors, since, they play a key role in developing the power reactor technology and radiation applications such as isotope generation for medical treatments. In this study, the neutronic behaviour of the TRIGA MARK II reactor, owned and operated by Istanbul Technical University is analysed by using the SCALE code system. In the analysis, in order to overcome the disadvantages of special TRIGA codes, such as TRIGAP, the SCALE code system is chosen to perform the calculations. TRIGAP and similar codes have limited geometrical (one-dimensional geometry) and cross sectional options (two-group calculations), however, SCALE has the capability of wider range of geometrical modelling capability (three-dimensional modelling is possible) and multi-group calculations are possible

  11. Perturbation analysis of the TRIGA Mark II reactor Vienna

    Energy Technology Data Exchange (ETDEWEB)

    Khan, R. [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Islamabad (Pakistan); Villa, M.; Stummer, T.; Boeck, H. [Vienna Univ. of Technology (Austria). Atominstitut; Saeedbadshah [International Islamic Univ., Islamabad (Pakistan)

    2013-04-15

    The safety design of a nuclear reactor needs to maintain the steady state operation at desired power level. The safe and reliable reactor operation demands the complete knowledge of the core multiplication and its changes during the reactor operation. Therefore it is frequently of interest to compute the changes in core multiplication caused by small disturbances in the field of reactor physics. These disturbances can be created either by geometry or composition changes of the core. Fortunately if these changes (or perturbations) are very small, one does not have to repeat the reactivity calculations. This article focuses the study of small perturbations created in the Central Irradiation Channel (CIC) of the TRIGA mark II core to investigate their reactivity influences on the core reactivity. For this purpose, 3 different kinds of perturbations are created by inserting 3 different samples in the CIC. The cylindrical void (air), heavy water (D2O) and Cadmium (Cd) samples are inserted into the CIC separately to determine their neutronics behavior along the length of the core. The Monte Carlo N-Particle radiation transport code (MCNP) is applied to simulate these perturbations in the CIC. The MCNP theoretical predictions are verified by the experiments performed on the current reactor core. The behavior of void in the whole core and its dependence on position and water fraction is also presented in this article. (orig.)

  12. Larger research programs at the beam holes of the Austrian TRIGA Mark II reactor. Design and construction of a Fourier chopper-selector at the Austrian TRIGA reactor

    International Nuclear Information System (INIS)

    Fleck, C.M.

    1970-01-01

    A neutron chopping system utilizing Fourier analysis has great advantages to alternative systems. For this purpose the chopper consists of a disc, opaque to neutrons, rotating on an axis perpendicular to its centre. Around its outside edge a series of uniformly spaced teeth and spaces are formed with neutron transparent gaps extending towards the centre. By using a stationary section having the same pattern of teeth and gaps it is possible to utilize a beam area considerably larger than the area of one tooth. During the last years at the TRIGA Reactor in Vienna a neutron chopping-and selecting-system is developed and in construction, which will not only chop the beam in that way necessary for Fourier analysis but also select the energy. The selection is done by seven discs of the form described above mounted on an axis. The selector is designed for neutron wave lengths between 3 and 30 A. The resolution is constant over the whole range of energy and depends on the beam divergence. Thus the modulation frequency is 10 4 sec -1 and the half-width of the neutron pulse about 50 μsec

  13. Different microprocessor controlled devices for ITU TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Can, B.; Omuz, S.; Uzun, S.; Apan, H.

    1990-01-01

    In this paper the design of a period meter and multichannel thermometer, which are controlled by a microprocessor, in order to be used at ITU TRIGA Mark-II Reactor is presented. The system works as a simple microcomputer, which includes a CPU, a EPROM, a RAM, a CTC, a PIO, a PIA a keyboard and displays, using the assembly language. The period meter can work either with pulse signal or with analog signal depending on demand of the user. The period is calculated by software and its range is -99,9 sec, to +2.1 sec. When the period drops +3 sec, the system gives alarm illuminating a LED. The multichannel thermometer has eight temperature channels. Temperature channels can manually or automatically be selected. The channel selection time can be adjusted. The thermometer gives alarm illuminating a LED, when the temperature rises to 600 C. Temperature data is stored in the RAM and is shown on a display. This system provides us to use four spare thermocouples in the reactor. (orig.)

  14. Twenty years of operation of Ljubljana's TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Dimic, V.

    1986-01-01

    Twenty years have now passed since the start of the TRIGA Mark II reactor in Ljubljana. The reactor was critical on May 31, 1966. The total energy produced until the end of May 1986 was 14.048 MWh or 585 MWd. For the first 14 years (until 1981) the yearly energy produced was about 600 MWh, since 1981 the yearly energy produced was 1000 MWh when a routine radioactive isotopes production started for medical use as well as other industrial applications, such as doping and irradiation with fast neutrons of silicon monocrystals, production of level indicators (irradiated cobalt wire), production of radioactive iridium for gamma-radiography, leak detection in pipes by sodium, etc. Besides these, applied research around the reactor is being conducted in the following main fields, where- many unique methods have been developed or have found their way into the local industry or hospitals: neutron radiography, neutron induced auto-radiography using solid state nuclear track detectors, nondestructive methods for assessment of nuclear burn-up, neutron dosimetry, calculation of core burn-up for the optimal in-core fuel management strategy. The solvent extraction method was developed for the everyday production of 99m Tc, which is the most widely used radionuclide in diagnostic nuclear medicine. The methods were developed for the production of the following isotopes: 18 F, 85m Kr, 24 Na, 82 Br, 64 Zn, 125 I. Neutron activation analysis represents one of the major usages for the TRIGA reactor. Basic research is being conducted in the following main fields: solid state physics (elastic and inelastic scattering of the neutrons), neutron dosimetry, neutron radiography, reactor physics and neutron activation analysis. The reactor is used very extensively as a main instrument in the Reactor Training Centre in Ljubljana where manpower training for our nuclear power plant and other organisations has been performed. Although the reactor was designed very carefully in order to be used for

  15. Characterization of the TRIGA Mark II reactor full-power steady state

    Energy Technology Data Exchange (ETDEWEB)

    Cammi, Antonio, E-mail: antonio.cammi@polimi.it [Politecnico di Milano – Department of Energy, CeSNEF (Enrico Fermi Center for Nuclear Studies), via La Masa 34, 20156 Milano (Italy); Zanetti, Matteo [Politecnico di Milano – Department of Energy, CeSNEF (Enrico Fermi Center for Nuclear Studies), via La Masa 34, 20156 Milano (Italy); Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica [University of Milano-Bicocca, Physics Department “G. Occhialini” and INFN Section, Piazza dell’Ateneo Nuovo, 20126 Milan (Italy); Magrotti, Giovanni; Prata, Michele; Salvini, Andrea [University of Pavia, Applied Nuclear Energy Laboratory (L.E.N.A.), Via Gaspare Aselli 41, 27100 Pavia (Italy)

    2016-04-15

    Highlights: • Full-power steady state characterization of the TRIGA Mark II reactor. • Monte Carlo and Multiphysics simulation of the TRIGA Mark II reactor. • Sub-cooled boiling effects in the TRIGA Mark II reactor. • Thermal feedback effects in the TRIGA Mark II reactor. • Experimental data based validation. - Abstract: In this paper, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor at the University of Pavia is achieved by coupling the Monte Carlo (MC) simulation for neutronics with the “Multiphysics” model for thermal-hydraulics. Neutronic analyses have been carried out with a MCNP5 based MC model of the entire reactor system, already validated in fresh fuel and zero-power configurations (in which thermal effects are negligible) and using all available experimental data as a benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core must be established. To evaluate this, a thermal-hydraulic model has been developed, using the power distribution results from the MC simulation as input. The thermal-hydraulic model is focused on the core active region and takes into account sub-cooled boiling effects present at full reactor power. The obtained temperature distribution is then entered into the MC model and a benchmark analysis is carried out to validate the model in fresh fuel and full-power configurations. An acceptable correspondence between experimental data and simulation results concerning full-power reactor criticality proves the reliability of the adopted methodology of analysis, both from the perspective of neutronics and thermal-hydraulics.

  16. Neutron beam utilization at the TRIGA Mark II reactor Vienna

    International Nuclear Information System (INIS)

    Villa, M.; Boeck, H.; Ismail, S.; Koerner, S.; Baron, M.; Hainbuchner, M.; Badurek, G.; Buchelt, R.J.

    1999-01-01

    A review is given about the research activities around the 250 kw TRIGA reactor Vienna, which are adequate to other neutron sources of comparable or bigger size. The topics selected for presentation range from neutron radiography, materials irradiation, neutron small-angle scattering, neutron activation analysis, neutron polarization to neutron interferometry. It is the aim of this presentation to stimulate programs for more efficient use around TRIGA research reactors with neutron flux densities of 1013 cm-2a-1 at the center of the reactor core. We briefly describe the experimental facilities installed at the 250 kw TRIGA reactor of the Austrian Universities in Vienna and present a great part of the current research activities performed with them. We believe that most of the techniques and experiments presented here are adequate for implementation to other reactors of similar or even higher power. Those technologies which require extremely specialized know-how not generally available at every research Inst.e will not be treated here or are just mentioned without any further details.(author)

  17. Visual examination program of the TRIGA Mark II reactor Vienna with the nuclear underwater telescope

    International Nuclear Information System (INIS)

    Boeck, H.; Hammer, J.; Varga, K.

    1985-12-01

    The visual inspection programm carried out during a three month shut-period at the TRIGA Mark II reactor Vienna is described. Optical inspection of all welds inside the reactor tank was carried out with an underwater telescope developed by the Central Research Institute of Physics, Budapest, Hungary. It is shown that even after 23 years of reactor operation all tank internals were found to be in good condition and minor defects can be easily repaired by remote handling tools. (Author)

  18. Data base formation for important components of reactor TRIGA MARK II

    International Nuclear Information System (INIS)

    Jordan, R.; Mavko, B.; Kozuh, M.

    1992-01-01

    The paper represents specific data base formation for reactor TRIGA MARK II in Podgorica. Reactor operation data from year 1985 to 1990 were collected. Two groups of collected data were formed. The first group includes components data and the second group covers data of reactor scrams. Time related and demand related models were used for data evaluation. Parameters were estimated by classical method. Similar data bases are useful everywhere where components unavailabilities may have severe drawback. (author) [sl

  19. Over Twenty Years Of Experience In ITU TRIGA MARK-II Reactor

    International Nuclear Information System (INIS)

    Yavuz, Hasbi

    2008-01-01

    I.T.U. TRIGA MARK-II Training and Research Reactor, rated at 250 kW steady-state and 1200 MW pulsing power is the only research and training reactor owned and operated by a university in Turkey. Reactor has been operating since March 11, 1979; therefore the reactor has been operating successfully for more than twenty years. Over the twenty years of operation: - The tangential beam tube was equipped with a neutron radiography facility, which consists of a divergent collimator and exposure room; - A computerized data acquisition system was designed and installed such that all parameters of the reactor, which are observed from the console, could be monitored both in normal and pulse operations; - An electrical power calibration system was built for the thermal power calibration of the reactor; - Publications related with I.T.U. TRIGA MARK-II Training and Research Reactor are listed in Appendix; - Two majors undesired shutdown occurred; - The I.T.U. TRIGA MARK-II Training and Research Reactor is still in operation at the moment. (authors)

  20. The evaluation of research reactor TRIGA MARK II safety

    International Nuclear Information System (INIS)

    Jordan, R.; Kozuh, M.; Mavko, B.

    1994-01-01

    In the paper the Probabilistic Safety Analysis (PSA) of a research reactor is described. Five different initiating events were selected and analyzed with the use of event trees. Seven reactor systems were modeled with fault trees. Three groups of radiation releases were introduced - Success, Reactor-Hall, Environment - and their frequencies were estimated. The importance factors of initiating events, human errors and basic events were calculated regarding the consequence groups. (author)

  1. Flux measurement in ZBR at the TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Dauke, M.

    2005-01-01

    The determination of the neutron flux in the TRIGA-2-Vienna reactor was the objective of this research. The theory of the method (4π-β detectors) is presented as well as the determination of the maximum flux, gold-cadmium differential measurement, cobalt-wire measurement, finally a comparison of all results was made and interpreted. (nevyjel)

  2. Monte Carlo analysis of Musashi TRIGA mark II reactor core

    International Nuclear Information System (INIS)

    Matsumoto, Tetsuo

    1999-01-01

    The analysis of the TRIGA-II core at the Musashi Institute of Technology Research Reactor (Musashi reactor, 100 kW) was performed by the three-dimensional continuous-energy Monte Carlo code (MCNP4A). Effective multiplication factors (k eff ) for the several fuel-loading patterns including the initial core criticality experiment, the fuel element and control rod reactivity worth as well as the neutron flux measurements were used in the validation process of the physical model and neutron cross section data from the ENDF/B-V evaluation. The calculated k eff overestimated the experimental data by about 1.0%Δk/k for both the initial core and the several fuel-loading arrangements. The calculated reactivity worths of control rod and fuel element agree well the measured ones within the uncertainties. The comparison of neutron flux distribution was consistent with the experimental ones which were measured by activation methods at the sample irradiation tubes. All in all, the agreement between the MCNP predictions and the experimentally determined values is good, which indicated that the Monte Carlo model is enough to simulate the Musashi TRIGA-II reactor core. (author)

  3. Neutronics analysis of TRIGA Mark II research reactor

    Directory of Open Access Journals (Sweden)

    Haseebur Rehman

    2018-02-01

    Full Text Available This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4 and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE codes. Cores 133 and 134 were analyzed in 2-D (r, θ and 3-D (r, θ, z, using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied using various libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0, Joint Evaluated Fission and Fusion File (JEFF-3.1, Japanese Evaluated Nuclear Data Library (JENDL-3.2, and Joint Evaluated File (JEF-2.2 nuclear data. The simulation results showed that the multiplication factor calculated for all these data libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134 was also calculated with different homogenization approaches. A comparison was made with experimental and reported Monte Carlo results, and it was found that, using proper homogenization of absorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantly improved.

  4. Activation of TRIGA Mark II research reactor concrete shield

    International Nuclear Information System (INIS)

    Zagar, Tomaz; Ravnik, Matjaz; Bozic, Matjaz

    2002-01-01

    To determine neutron activation inside the TRIGA research reactor concrete body a special sample-holder for irradiation inside horizontal channel was developed and tested. In the sample-holder various samples can be irradiated at different concrete shielding depths. In this paper the description of the sample-holder, experiment conditions and results of long-lived activation measurements are given. Long-lived neutron-induced gamma-ray-emitting radioactive nuclides in the samples were measured with HPGe detector. The most active long-lived radioactive nuclides in ordinary concrete samples were found to be 60 Co and 152 Eu and in barytes concrete samples 60 Co, 152 Eu and 133 Ba. Measured activity density of all nuclides was found to decrease almost linearly with depth in logarithmic scale. (author)

  5. Collimator and shielding design for boron neutron capture therapy (BNCT) facility at TRIGA MARK II reactor

    International Nuclear Information System (INIS)

    Mohd Rafi Mohd Solleh; Abdul Aziz Tajuddin; Abdul Aziz Mohamed; Eid Mahmoud Eid Abdel Munem; Mohamad Hairie Rabir; Julia Abdul Karim; Yoshiaki, Kiyanagi

    2011-01-01

    The geometry of reactor core, thermal column, collimator and shielding system for BNCT application of TRIGA MARK II Reactor were simulated with MCNP5 code. Neutron particle lethargy and dose were calculated with MCNPX code. Neutron flux in a sample located at the end of collimator after normalized to measured value (Eid Mahmoud Eid Abdel Munem, 2007) at 1 MW power was 1.06 x 10 8 n/ cm 2 / s. According to IAEA (2001) flux of 1.00 x 10 9 n/ cm 2 / s requires three hours of treatment. Few modifications were needed to get higher flux. (Author)

  6. Modernization design of neutron radiography of ITU TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Tugrul, B.; Bilge, A.N.

    1988-01-01

    ITU TRIGA MARK-II Research and Training Reactor has a power of 250 KW and has three beam tubes. One of them is tangential beam tube used for neutron radiography. In this study, the neutron radiography set in the tangential beam tube is described with its problems for ITU TRIGA Reactor. After that modernization of the system is designed and the applicability of the direct and indirect methods is evaluated. Improving the ratio of length to diameter for the beam tube, elimination the fogging on the film and constructive design for practice and secure application of the technique is developed. (author)

  7. Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia

    International Nuclear Information System (INIS)

    Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica; Alloni, Daniele; Magrotti, Giovanni; Manera, Sergio; Prata, Michele; Salvini, Andrea; Cammi, Antonio; Zanetti, Matteo; Sartori, Alberto

    2016-01-01

    Highlights: • A fuel evolution model for a TRIGA Mark II reactor has been developed. • Reproduction of nearly 50 years of reactor operation. • The model was used to predict the best reactor reconfiguration. • Reactor life was extended without adding fresh fuel elements. - Abstract: A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the University of Pavia. The results were used to predict the effects of a complete core reconfiguration and the accuracy of this prediction was tested experimentally. We used the Monte Carlo code MCNP5 to reproduce system neutronics in different operating conditions and to analyze neutron fluxes in the reactor core. The software that took care of time evolution, completely designed in-house, used the neutron fluxes obtained by MCNP5 to evaluate fuel consumption. This software was developed specifically to keep into account some features that differentiate low power experimental reactors from those used for power production, such as the daily ON/OFF cycle and the long fuel lifetime. These effects can not be neglected to properly account for neutron poison accumulation. We evaluated the effect of 48 years of reactor operation and predicted a possible new configuration for the reactor core: the objective was to remove some of the fuel elements from the core and to obtain a substantial increase in the Core Excess reactivity value. The evaluation of fuel burnup and the reconfiguration results are presented in this paper.

  8. Biological Tests for Boron Neutron Capture Therapy Research at the TRIGA Mark II Reactor in Pavia

    Energy Technology Data Exchange (ETDEWEB)

    Protti, N.; Ballarini, F.; Bortolussi, S.; De Bari, A.; Stella, S.; Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); Nuclear Physics National Institute (INFN), Pavia (Italy); Bruschi, P. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); Bakeine, J.G.; Cansolino, L.; Clerici, A.M. [Laboratory of Experimental Surgery, Department of Surgery, University of Pavia, Pavia (Italy)

    2011-07-01

    The thermal column of the TRIGA Mark II reactor of the Pavia University is used as an irradiation facility to perform biological tests and irradiations of living systems for Boron Neutron Capture Therapy (BNCT) research. The suitability of the facility has been ensured by studying the neutron flux and the photon background in the irradiation chamber inside the thermal column. This characterization has been realized both by flux and dose measurements as well as by Monte Carlo simulations. The routine irradiations concern in vitro cells cultures and different tumor animal models to test the efficacy of the BNCT treatment. Some results about these experiments will be described. (author)

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

    Science.gov (United States)

    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. Copyright © 2014 Elsevier Ltd. All rights reserved.

  10. An analytical approach to the positive reactivity void coefficient of TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Edgue, Erdinc; Yarman, Tolga

    1988-01-01

    Previous calculations of reactivity void coefficient of I.T.U. TRIGA Mark-II Reactor was done by the second author et al. The theoretical predictions were afterwards, checked in this reactor experimentally. In this work an analytical approach is developed to evaluate rather quickly the reactivity void coefficient of I.T.U. TRIGA Mark-II, versus the size of the void inserted into the reactor. It is thus assumed that the reactor is a cylindrical, bare nuclear system. Next a belt of water of 2πrΔrH is introduced axially at a distance r from the center line of the system. r here, is the thickness of the belt, and H is the height of the reactor. The void is described by decreasing the water density in the belt region. A two group diffusion theory is adopted to determine the criticality of our configuration. The space dependency of the group fluxes are, thereby, assumed to be J 0 (2.405 r / R) cos (π Z / H), the same as that associated with the original bare reactor uniformly loaded prior to the change. A perturbation type of approach, thence, furnishes the effect of introducing a void in the belt region. The reactivity void coefficient can, rather surprisingly, be indeed positive. To our knowledge, this fact had not been established, by the supplier. The agreement of our predictions with the experimental results is good. (author)

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

    International Nuclear Information System (INIS)

    Eko Priyono; Kurnia Wibowo; Anang Susanto

    2016-01-01

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

  12. Criticality calculation in TRIGA MARK II PUSPATI Reactor using Monte Carlo code

    International Nuclear Information System (INIS)

    Rafhayudi Jamro; Redzuwan Yahaya; Abdul Aziz Mohamed; Eid Abdel-Munem; Megat Harun Al-Rashid; Julia Abdul Karim; Ikki Kurniawan; Hafizal Yazid; Azraf Azman; Shukri Mohd

    2008-01-01

    A Monte Carlo simulation of the Malaysian nuclear reactor has been performed using MCNP Version 5 code. The purpose of the work is the determination of the multiplication factor (k e ff) for the TRIGA Mark II research reactor in Malaysia based on Monte Carlo method. This work has been performed to calculate the value of k e ff for two cases, which are the control rod either fully withdrawn or fully inserted to construct a complete model of the TRIGA Mark II PUSPATI Reactor (RTP). The RTP core was modeled as close as possible to the real core and the results of k e ff from MCNP5 were obtained when the control fuel rods were fully inserted, the k e ff value indicates the RTP reactor was in the subcritical condition with a value of 0.98370±0.00054. When the control fuel rods were fully withdrawn the value of k e ff value indicates the RTP reactor is in the supercritical condition, that is 1.10773±0.00083. (Author)

  13. Data base formation for important components of reactor TRIGA MARK II

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, R; Mavko, B; Kozuh, M [Inst. Jozef Stefan, Ljubljana (Slovenia)

    1992-07-01

    The paper represents specific data base formation for reactor TRIGA MARK II in Podgorica. Reactor operation data from year 1985 to 1990 were collected. Two groups of collected data were formed. The first group includes components data and the second group covers data of reactor scrams. Time related and demand related models were used for data evaluation. Parameters were estimated by classical method. Similar data bases are useful everywhere where components unavailabilities may have severe drawback. (author) [Slovenian] V referatu smo prikazali raziskavo, v okviru katere smo za raziskovalni reaktor TRIGA MARK II v Podgorici izoblikovali specificno bazo podatkov. Zbrali smo podatke obratovanja reaktorja od leta 1985 do 1990. Rezultate raziskave dogodkov smo razdelili v dve glavni skupini. V prvo spadajo obratovalni podatki o komponentah, v drugo skupino pa spadajo zagoni oz. zaustavitve reaktorja. Podatke smo ovrednotili z modelom v casovnem prostoru in z modelom na zahtevo. Parametre modelov smo dolocili s klasicno metodo. Opisane baze podatkov so uporabne povsod, kjer so lahko posledice nezanesljivega delovanja sistemov velike. [author].

  14. Using TRIGA Mark II research reactor for irradiation with thermal neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Kolšek, Aljaž, E-mail: aljaz.kolsek@gmail.com; Radulović, Vladimir, E-mail: vladimir.radulovic@ijs.si; Trkov, Andrej, E-mail: andrej.trkov@ijs.si; Snoj, Luka, E-mail: luka.snoj@ijs.si

    2015-03-15

    Highlights: • Monte Carlo N-Particle Transport Code was used to design and perform calculations. • Characterization of the TRIGA Mark II ex-core irradiation facilities was performed. • The irradiation device was designed in the TRIGA irradiation channel. • The use of the device improves the fraction of thermal neutron flux by 390%. - Abstract: Recently a series of test irradiations was performed at the JSI TRIGA Mark II reactor for the Fission Track-Thermoionization Mass Spectrometry (FT-TIMS) method, which requires a well thermalized neutron spectrum for sample irradiation. For this purpose the Monte Carlo N-Particle Transport Code (MCNP5) was used to computationally support the design of an irradiation device inside the TRIGA model and to support the actual measurements by calculating the neutron fluxes inside the major ex-core irradiation facilities. The irradiation device, filled with heavy water, was designed and optimized inside the Thermal Column and the additional moderation was placed inside the Elevated Piercing Port. The use of the device improves the ratio of thermal neutron flux to the sum of epithermal and fast neutron flux inside the Thermal Column Port by 390% and achieves the desired thermal neutron fluence of 10{sup 15} neutrons/cm{sup 2} in irradiation time of 20 h.

  15. Computer code for the thermal-hydraulic analysis of ITU TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Ustun, G.; Durmayaz, A.

    2002-01-01

    Istanbul Technical University (ITU) TRIGA Mark-II reactor core consists of ninety vertical cylindrical elements located in five rings. Sixty-nine of them are fuel elements. The reactor is operated and cooled with natural convection by pool water, which is also cooled and purified in external coolant circuits by forced convection. This characteristic leads to consider both the natural and forced convection heat transfer in a 'porous-medium analysis'. The safety analysis of the reactor requires a thermal-hydraulic model of the reactor to determine the thermal-hydraulic parameters in each mode of operation. In this study, a computer code cooled TRIGA-PM (TRIGA - Porous Medium) for the thermal-hydraulic analysis of ITU is considered. TRIGA Mark-II reactor code has been developed to obtain velocity, pressure and temperature distributions in the reactor pool as a function of core design parameters and pool configuration. The code is a transient, thermal-hydraulic code and requires geometric and physical modelling parameters. In the model, although the reactor is considered as only porous medium, the other part of the reactor pool is considered partly as continuum and partly as porous medium. COMMIX-1C code is used for the benchmark purpose of TRIGA-PM code. For the normal operating conditions of the reactor, estimations of TRIGA-PM are in good agreement with those of COMMIX-1C. After some more improvements, this code will be employed for the estimation of LOCA scenario, which can not be analyses by COMMIX-1C and the other multi-purpose codes, considering a break at one of the beam tubes of the reactor

  16. Nine years of operation of ITU-TRR TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Yavuz, H.; Bayuelken, A.R.; Yavuz, M.A.

    1988-01-01

    ITU-TRR TRIGA Mark-II reactor in Istanbul with a steady state power of 250 kW and a pulsing capability up to 1200 MW has been operating since March 11,1979 with an energy release of 107.5 MWh and a total of 72 pulses. During this nearly nine years, the reactor was in operation without any major undesired shut down. One of the major problems was faced when the instrumented fuel element in position 9 of the F ring went totally out of order. Secondly, the cooling tower of the secondary cooling system could not be operated properly during the hot summer days, and also we had a tar leakage problem with the radial beam port connection to the tank. During the regular maintenance work in this summer, the measurements of changes in nuclear and physical parameters of the reactor fuel and dummy elements have also proceeded. (author)

  17. A digital data acquisition and display system for ITU TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Can, B.; Omuz, S.

    2008-01-01

    Full text: In this study, a digital data acquisition and display system realized for ITU TRIGA Mark-II Reactor is described. This system is realized in order to help the reactor operator and to increase reactor console capacity. The system consists of two main units, which are host computers and RTI-815F, analog devices, data acquisition card. RTI-815F is multi-function analog/digital input/output board that plugs into one of the available long expansion slots in the IBM-PC, PC/XT, PC/AT, or equivalent personal computers. It has 16 analog input channels for single-ended input signals or 8 analog input channels for differential input signals. But its channel capacity can be increased to 32 input channels for single-ended input signals or 16 input channels for differential input signals. RTI-815F board contains 2 analog output channels, 8 digital input channels and 8 digital output channels. In the ITD TRIGA Mark-II Reactor, 6 fuel temperature channels, 3 water temperature channels, 3 control rod position channels and 4 power channels are chosen as analog input signals for RTI-815F. Its digital outputs are assigned to cooling tower fan, primary and secondary pump reactor scram, control rod rundown. During operation, data are automatically archived to disk and displayed on screen. The channel selection time and sampling time can be adjusted. The simulated movement and position of control rods in the reactor core can be noted and displayed. The changes of power, fuel temperature and water temperature can be displayed on the screen as a graphic. In this system both period and reactivity are calculated and displayed on the screen. (authors)

  18. Present Services at the TRIGA Mark II Reactor of the JSI

    International Nuclear Information System (INIS)

    Smodiš, B.; Snoj, L.

    2013-01-01

    The TRIGA Mark II research reactor of the Jožef Stefan Institute has been continuously operating since the year 1966. The currently offered services include: (1) Neutron activation analysis in both instrumental and radiochemical modes; (2) neutron irradiation of various kinds of materials intended to be used for research and applicative purposes; (3) training and education of university students as well as on-job training of staff working in public and private institutions, (4) verification of computer codes and nuclear data, comprising primarily criticality calculations and neutron flux distribution studies and (5) testing and development of a digital reactivity meter. The paper briefly describes the aforementioned activities and shows that even such small reactors are still indispensable in nuclear science and technology. (author)

  19. Calculation of neutron fluxes in biological shield of the TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Bozic, M.; Zagar, T.; Ravnik, M.

    2001-01-01

    The complete calculation of neutron fluxes in biological shield and verification with experimental results is presented. Calculated results are obtained with TORT code (TORT-Three Dimensional Oak Ridge Discrete Ordinates Neutron/Photon Transport Code). Experimental results used for comparison are available from irradiation experiment with selected type of concrete and other materials in irradiation channel 4 in TRIGA Mark II reactor. These experimental results were used as a benchmark. Homogeneous type of problem (without inserted irradiation channel) and problem with asymmetry (inserted beam port 4, filled with different materials) were of interest for neutron flux calculation. Deviation from material data set up as original parameters is also considered (first of all presence of water in concrete and density of concrete) for type of concrete in biological shield and for selected type of concrete in irradiation channel. BUGLE-96 (47 neutron energy groups) library is used. Excellent agreement between calculated and experimental results for reaction rate is received.(author)

  20. Non-destructive material investigation with thermal neutrons at the TRIGA Mark II reactor in Vienna

    International Nuclear Information System (INIS)

    Bastuerk, M.; Boeck, H.; Zamani, B.; Zawisky, M.; Rauch, H.

    2004-01-01

    Neutron tomography providing 3D information about interior of an object is a very efficient tool to visualize inner defects of the materials, non-destructively. In this study, some applications of neutron tomography in different fields such as geology, aerospace, civil engineering and archaeology were presented. Distribution of minerals in pumice and rock samples, visualization of inner defects within a new developed titan aluminum turbine blade, and distribution of silica gel as an important impregnating agent in construction and restoration of buildings were investigated. The measurements of tomography projections taken in the 0 to 180 o angle were performed with a thermal neutron flux of 10 5 at the TRIGA Mark II research reactor in Vienna, and the common filtered back projection method was used for the 3D image reconstruction. (author)

  1. Neutron radiography applications in I.T.U. TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Tugrul, A. B.

    2002-01-01

    Neutron radiography is an important radiographic technique which is supplied different and advanced information according to the X or gamma ray radiography. However, it has a trouble for supplying the convenient neutron sources. Tangential beam tube of Istanbul Technical University (ITU) TRIGA Mark-II Training and Research Reactor has been arranged for using neutron radiography. The neutron radiography set defined as detailed for the application of the technique. Two different techniques for neutron radiography are defined as namely, transfer method and direct method. For the transfer method dysprosium and indium screens are used in the study. But, dysprosium generally was preferred in many studies in the point of view nuclear safety. Gadolinium was used for direct method. Two techniques are compared and explained the preferring of the transfer technique. Firstly, reference composition is prepared for seeing the differences between neutron and X-ray or gamma radiography. In addition of it, some radiograph samples are given neutron and X-ray radiography which shows the different image characters. Lastly, some examples are given from archaeometric studies. One of them the brass plates of Great Mosque door in Cizre. After the neutron radiography application, organic dye traces are noticed. Other study is on a sword that belong to Urartu period at the first millennium B.C. It is seen that some wooden part on it. Some different artefacts are examined with neutron radiography from the Ikiztepe excavation site, then some animal post parts are recognized on them. One of them is sword and sheath which are corroded together. After the neutron radiography application, it can be noticed that there are a cloth between the sword and its sheath. By using neutron radiography, many interesting and detailed results are observed in ITU TRIGA Mark-II Training and Research Reactor. Some of them shouldn't be recognised by using any other technique

  2. Archaeometric studies by using neutron radiography in ITU TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Tugrul, A. Beril

    2008-01-01

    Archaeometric many studies have been done by using neutron radiography in ITU TRIGA Mark-II Training and Research Reactor for over 15 years. Tangential beam tube has been arranged for using neutron radiography. Generally, transfer technique has been preferred with using dysprosium screen, but indium screen also is used. Some studies are described which are all on the Anatolian artefacts. The first study from 13th century AD deals with Seljukian period from south-east Anatolia. It investigated a plate from Great Mosque door in Cizre. With means of the neutron radiography painting traces are investigated on the plates. Organic dye traces are noticed on some of plates, which have generally animal figures. Other studies from Urartu period at the first millennium B.C, investigates artefacts found at the vicinity of Van on east Anatolia. An important one is a sword that was found in a grave. It has some corrosion defects. The neutron radiography was applied and shown that wooden parts are there. Other studies referred to samples from the Ikiztepe Excavation site on north Anatolia. Many artefacts were examined by neutron radiography. Some of them evidenced animal parts are recognised as covering parts. An interesting result was obtained to a sword and its sheath that were corroded together. After the neutron radiography applications, it was noticed that there are a cloth between the sword and its sheath. Hence, it was the cause of corrosion of the artefact. By using neutron radiography, many interesting and detailed results were observed by means of the neutron beam from the ITU TRIGA Mark-II Training and Research Reactor. Some of them could not be evidenced by means of any other technique

  3. Damage analysis of TRIGA MARK II Bandung reactor tank material structure

    International Nuclear Information System (INIS)

    Soedardjo; Sumijanto

    2000-01-01

    Damage of Triga Mark II Bandung reactor tank material structure has been analyzed. The analysis carried out was based on ultrasonic inspection result in 1996 and the monthly reports of reactor operation by random data during 1988 up to 1995. Ultrasonic test data had shown that thinning processes on south and west region of reactor out side wall at upper part of water level had happened. Reactor operation data had shown the demineralized water should be added monthly to the reactor and bulk shielding water tank. Both reactor and bulk shielding tank are shielded by concrete of Portland type I cement consisting of CaO content about 58-68 %. The analysis result shows that the reaction between CaO and seepage water from bulk shielding wall had taken place and consequently the reactor out sidewall surroundings became alkaline. Based on Pourbaix diagram, the aluminum reactor tank made of aluminum alloy 6061 T6 would be corroded easily at pH equal an greater than 8.6. The passive layer AI 2 O 3 aluminum metal surface would be broken due to water reaction taken place continuously at high pH and produces hydrogen gas. The light hydrogen gas would expand the concrete cement and its expanding power would open the passive layer of aluminum metal upper tank. The water sea pages from adding water into reactor tank could indicate the upper water level tank corrosion is worse than the lower water level tank. (author)

  4. Operational Experience with the TRIGA Mark II Reactor of the University of Pavia

    Energy Technology Data Exchange (ETDEWEB)

    Tigliole, A. Borio Di; Alloni, D.; Cagnazzo, M.; Coniglio, M.; Lana, F.; Losi, A.; Magrotti, G.; Manera, S.; Marchetti, F.; Pappalardo, P.; Prata, M.; Provasi, M.C.; Salvini, A.; Scian, G.; Vinciguerra, G. [University of Pavia, Laboratory of Applied Nuclear Energy (L.E.N.A), Via Aselli 41, 27100 Pavia (Italy)

    2011-07-01

    The Laboratory of Applied Nuclear Energy (LENA) is an Interdepartmental Research Centre of the University of Pavia which operates a 250 kW TRIGA Mark II Research Nuclear Reactor, a Cyclotron for the production of radioisotopes and other irradiation facilities. The reactor is in operation since 1965 and many home-made upgrading were realized in the past years in order to assure a continuous operation of the reactor for the future. The annual reactor operational time at nominal power is in the range of 300 - 400 hours depending upon the time schedule of some experiments and research activities. The reactor is mainly used for NAA activities, BNCT research, samples irradiation and training. In specific, few tens of hours of reactor operation per year are dedicated to training courses for University students and for professionals. Besides, the LENA Centre hosts every year more than one thousand high school students in visit. Lately, LENA was certified ISO 9001:2008 for the ''operation and maintenance of the reactor'' and for the ''design and delivery of the irradiation service''. Nowadays the reactor shows a good technical state and, at the moment, there are no political or economical reason to consider the reactor shut-down. (author)

  5. Computational analysis of neutronic parameters of CENM TRIGA Mark II research reactor

    International Nuclear Information System (INIS)

    El Younoussi, C.; El Bakkari, B.; Boulaich, Y.; Riyach, D.; Otmani, S.; Marrhich, I.; Badri, H.; Htet, A.; Nacir, B.; El Bardouni, T.; Boukhal, H.; Zoubair, M.; Ossama, M.; Chakir, E.

    2010-01-01

    The CENM TRIGA MARK II reactor is part of the National Center for Energy, Sciences and Nuclear Techniques (CNESTEN). It's a standard design 2MW, natural-convection-cooled reactor with a graphite reflector containing 4 beam tubes and a thermal column. The reactor has several applications in different fields as industry, agriculture, medicine, training and education. In the present work a computational study has been carried out in the framework of neutronic parameters studies of the reactor. A detailed MCNP model that include all elements of the core and surrounding structures has been developed to calculate different parameters of the core (The effective multiplication factor, reactivity experiments comprising control rods worth, excess reactivity and shutdown margin). Further calculations have been carried out to calculate the neutron flux profiles at different locations of the reactor core. The cross sections used are processed from the library provided with MCNP5 and based on the ENDF/B-VII with continuous dependence in energy and special treatment of thermal neutrons in lightweight materials. (author)

  6. Visualization of neutron flux and power distributions in TRIGA Mark II reactor as an educational tool

    International Nuclear Information System (INIS)

    Snoj, Luka; Ravnik, Matjaz; Lengar, Igor

    2008-01-01

    Modern Monte Carlo computer codes (e.g. MCNP) for neutron transport allow calculation of detailed neutron flux and power distribution in complex geometries with resolution of ∼1 mm. Moreover they enable the calculation of individual particle tracks, scattering and absorption events. With the use of advanced software for 3D visualization (e.g. Amira, Voxler, etc.) one can create and present neutron flux and power distribution in a 'user friendly' way convenient for educational purposes. One can view axial, radial or any other spatial distribution of the neutron flux and power distribution in a nuclear reactor from various perspectives and in various modalities of presentation. By visualizing the distribution of scattering and absorption events and individual particle tracks one can visualize neutron transport parameters (mean free path, diffusion length, macroscopic cross section, up-scattering, thermalization, etc.) from elementary point of view. Most of the people remember better, if they visualize the processes. Therefore the representation of the reactor and neutron transport parameters is a convenient modern educational tool for the (nuclear power plant) operators, nuclear engineers, students and specialists involved in reactor operation and design. The visualization of neutron flux and power distributions in Jozef Stefan Institute TRIGA Mark II research reactor is treated in the paper. The distributions are calculated with MCNP computer code and presented using Amira and Voxler software. The results in the form of figures are presented in the paper together with comments qualitatively explaining the figures. (authors)

  7. Testing the applicability of the k 0-NAA method at the MINT's TRIGA MARK II reactor

    International Nuclear Information System (INIS)

    Siong, Wee Boon; Dung, Ho Manh; Wood, Ab. Khalik; Salim, Nazaratul Ashifa Abd.; Elias, Md. Suhaimi

    2006-01-01

    The Analytical Chemistry Laboratory at MINT is using the NAA technique since 1980s and is the only laboratory in Malaysia equipped with a research reactor, namely the TRIGA MARK II. Throughout the years the development of NAA technique has been very encouraging and was made applicable to a wide range of samples. At present, the k 0 method has become the preferred standardization method of NAA (k 0 -NAA) due to its multi-elemental analysis capability without using standards. Additionally, the k 0 method describes NAA in physically and mathematically understandable definitions and is very suitable for computer evaluation. Eventually, the k 0 -NAA method has been adopted by MINT in 2003, in collaboration with the Nuclear Research Institute (NRI), Vietnam. The reactor neutron parameters (α and f) for the pneumatic transfer system and for the rotary rack at various locations, as well as the detector efficiencies were determined. After calibration of the reactor and the detectors, the implemented k 0 method was validated by analyzing some certified reference materials (including IAEA Soil 7, NIST 1633a, NIST 1632c, NIST 1646a and IAEA 140/TM). The analysis results of the CRMs showed an average u score well below the threshold value of 2 with a precision of better than ±10% for most of the elemental concentrations obtained, validating herewith the introduction of the k 0 -NAA method at the MINT

  8. Testing the applicability of the k0-NAA method at the MINT's TRIGA MARK II reactor

    Science.gov (United States)

    Siong, Wee Boon; Dung, Ho Manh; Wood, Ab. Khalik; Salim, Nazaratul Ashifa Abd.; Elias, Md. Suhaimi

    2006-08-01

    The Analytical Chemistry Laboratory at MINT is using the NAA technique since 1980s and is the only laboratory in Malaysia equipped with a research reactor, namely the TRIGA MARK II. Throughout the years the development of NAA technique has been very encouraging and was made applicable to a wide range of samples. At present, the k0 method has become the preferred standardization method of NAA ( k0-NAA) due to its multi-elemental analysis capability without using standards. Additionally, the k0 method describes NAA in physically and mathematically understandable definitions and is very suitable for computer evaluation. Eventually, the k0-NAA method has been adopted by MINT in 2003, in collaboration with the Nuclear Research Institute (NRI), Vietnam. The reactor neutron parameters ( α and f) for the pneumatic transfer system and for the rotary rack at various locations, as well as the detector efficiencies were determined. After calibration of the reactor and the detectors, the implemented k0 method was validated by analyzing some certified reference materials (including IAEA Soil 7, NIST 1633a, NIST 1632c, NIST 1646a and IAEA 140/TM). The analysis results of the CRMs showed an average u score well below the threshold value of 2 with a precision of better than ±10% for most of the elemental concentrations obtained, validating herewith the introduction of the k0-NAA method at the MINT.

  9. Thermal Hydraulics Analysis for the 3MW TRIGA MARK-II Research Reactor Under Transient Condition

    International Nuclear Information System (INIS)

    Huda, M.Q.; Bhuiyan, S.I.; Mondal, M.A.W.

    1996-12-01

    Some important thermal hydraulic parameters of the 3 MW TRIGA MARK-II research reactor operating under transient condition were investigated using two computer codes PULTRI and TEMPUL. Major transient parameters, such as, peak power and prompt energy released after pulse, maximum fuel and coolant temperature, surface heat flux, time and radial distribution of temperature within fuel element after pulse, fuel, fuel-cladding gap width variation, etc. were computer and compared with the experimental and operational values as reported in the safety Analysis Report (SAR). It was observed that pulsing of the reactor inserting an excess reactivity of $2.00 shoots the reactor power level to 854.353 MW compared to an experimental value of 852 MW; the maximum fuel temperature corresponding to this peak power was found to be 846.76 o C which is much less than the limiting maximum value of fuel temperature of 1150 0 C as reported in SAR. During a pulse if the film boiling occurs for a peak adiabatic fuel temperature of 1000 o C, the calculated outer cladding wall temperature was observed to be 702.39 0 C compared to a value of 760 o C reported in SAR under the same condition. The investigated other results were also found to be in good agreement with the values reported in the SAR. 16 refs., 22 figs. (author)

  10. Neutronic Analysis of the 3 MW TRIGA MARK II Research Reactor, Part I: Monte Carlo Simulation

    International Nuclear Information System (INIS)

    Huda, M.Q.; Chakrobortty, T.K.; Rahman, M.; Sarker, M.M.; Mahmood, M.S.

    2003-05-01

    This study deals with the neutronic analysis of the current core configuration of a 3 MW TRIGA MARK II research reactor at Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh and validation of the results by benchmarking with the experimental, operational and available Final Safety Analysis Report (FSAR) values. The three-dimensional continuous-energy Monte Carlo code MCNP4C was used to develop a versatile and accurate full-core model of the TRIGA core. The model represents in detail all components of the core with literally no physical approximation. All fresh fuel and control elements as well as the vicinity of the core were precisely described. Continuous energy cross-section data from ENDF/B-VI and S(α, β) scattering functions from the ENDF/B-V library were used. The validation of the model against benchmark experimental results is presented. The MCNP predictions and the experimentally determined values are found to be in very good agreement, which indicates that the Monte Carlo model is correctly simulating the TRIGA reactor. (author)

  11. Utilization of a typical 250 kW TRIGA Mark II reactor at a University

    International Nuclear Information System (INIS)

    Villa, M.; Boeck, H.; Musilek, A.

    2007-01-01

    The 250 kW TRIGA Mark-II reactor operates since March 1962 at the Atominstitut Vienna/Austria. Its main tasks are nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection and dosimetry, and low temperature physics and fusion research. Academic research is carried out by students in the above mentioned fields coordinated and supervised by about 70 staff members with the aim of a masters- or PhD degree in one of the above mentioned areas. During the past 15 years about 580 students graduated through the Atominstitut. In addition, the Atominstitut co-operates closely with the nearby located IAEA in research projects, coordinated research programs (CRP) and supplying expert services. Regular training courses are carried out for the IAEA for Safeguard Trainees, fellowship places are offered for scientists from developing countries and staff members carry out expert missions to research centres in Africa, Asia and South America. Special Nuclear Material (SNM) is stored for calibration purposes at the Atominstitut belonging to the IAEA. (author)

  12. Measurements of neutron flux distributions in the core of the Ljubljana TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    Rant, J.; Ravnik, M.; Mele, I.; Dimic, V.

    2008-01-01

    Recently the Ljubljana TRIGA Mark II Reactor has been refurbished and upgraded to pulsed operation. To verify the core design calculations using TRIGAP and PULSTR1 codes and to obtain necessary data for future irradiation and neutron beam experiments, an extensive experimental program of neutron flux mapping and neutron field characterization was carried out. Using the existing neutron measuring thimbles complete axial and radial distributions in two radial directions were determined for two different core configurations. For one core configuration the measurements were also carried out in the pulsed mode. For flux distributions thin Cu (relative measurements) and diluted Au wires (absolute values) were used. For each radial position the cadmium ratio was determined in two axial levels. The core configuration was rather uniform, well defined (fresh fuel of a single type, including fuelled followers) and compact (no irradiation channels or gaps), offering unique opportunity to test the computer codes for TRIGA reactor calculations. The neutron flux measuring procedures and techniques are described and the experimental results are presented. The agreement between the predicted and measured power peaking factors are within the error limits of the measurements (<±5%) and calculations (±10%). Power peaking occurs in the B ring, and in the A ring (centre) there is a significant flux depression. (authors)

  13. Comparison of standardised decommissioning costing tools on pilot Vienna TRIGA MARK-II research reactor

    International Nuclear Information System (INIS)

    Hornacek, M.; Kristofova, K.; Slugen, V.; Zachar, M.; Stummer, T.

    2017-01-01

    The main purpose of the paper is to compare decommissioning costing code CERREX (Cost Estimation for Research Reactors in Excel) with advanced calculation methodology applied in eOMEGA-RR code. CERREX code was developed in line with the IAEA recommendations for decommissioning costing of research facilities and fully implements the ISDC (International Structure for Decommissioning Costing of Nuclear Installations) structure and costing methodology. In comparison with CERREX, usually applied in preliminary costing, the code eOMEGA-RR incorporates the realistic activity and material flow during decommissioning process (e.g. decontamination, dismantling and waste management). This advanced approach enables to carry out the decommissioning planning and costing more effectively. Moreover, the user-friendly interface helps to perform wide range of sensitivity analyses. In order to meet the above mentioned objectives, the model calculation costing case for TRIGA MARK-II research reactor in Vienna was developed in both calculation codes. The whole process covered four step-by-step procedures to be implemented. At first, inventory database taking into account physical as well as radiological parameters (e.g.: contamination, dose rates, nuclide vectors, limits and conditions) was developed. At second, advanced decommissioning costing case using CERREX and eOMEGA-RR code was created. At third, sensitivity analyses to estimate the impact of changing input parameters on calculated results were performed. Finally, costing results obtained from both cost calculation codes are compared and discussed. (authors)

  14. Reactor physics tests of TRIGA Mark-II Reactor in Ljubljana

    International Nuclear Information System (INIS)

    Ravnik, M.; Mele, I.; Trkov, A.; Rant, J.; Glumac, B.; Dimic, V.

    2008-01-01

    TRIGA Mark-II Reactor in Ljubljana was recently reconstructed. The reconstruction consisted mainly of replacing the grid plates, the control rod mechanisms and the control unit. The standard type control rods were replaced by the fuelled follower type, the central grid location (A ring) was adapted for fuel element insertion, the triangular cutouts were introduced in the upper plate design. However, the main novelty in reactor physics and operational features of the reactor was the installation of a pulse rod. Having no previous operational experience in pulsing, a detailed and systematic sequence of tests was defined in order to check the predicted design parameters of the reactor with measurements. The following experiments are treated in this paper: initial criticality, excess reactivity measurements, control rod worth measurement, fuel temperature distribution, fuel temperature reactivity coefficient, pulse parameters measurement (peak power, prompt energy, peak temperature). Flux distributions in steady state and pulse mode were measured as well, however, they are treated only briefly due to the volume of the results. The experiments were performed with completely fresh fuel of 12 w% enriched Standard Stainless Steel type. The core configuration was uniform (one fuel element type, including fuelled followers) and compact (no irradiation channels or gaps), as such being particularly convenient for testing the computer codes for TRIGA reactor calculations. Comparison of analytical predictions, obtained with WIMS, SLXTUS, TRIGAP and PULSTRI codes to measured values showed agreement within the error of the measurement and calculation. The paper has the following contents: 1. Introduction; 2. Steady State Experiments; 2.1. Core loading and critical experiment; 2.2. Flux range determination for tests at zero power; 2.3. Digital reactivity meter checkout; 2.4. Control rod worth measurements; 2.5. Excess reactivity measurement; 2.6. Thermal power calibration; 2

  15. Calculation analysis of TRIGA MARK II reactor core composed of two types of fuel elements

    International Nuclear Information System (INIS)

    Ravnik, M.

    1988-11-01

    The most important properties of mixed cores are treated for TRIGA MARK II reactor, composed of standard (20% enriched, 8.5w% U content) and FLIP (70% enriched, 8.5w% U content) fuel elements. Large difference in enrichment and presence of burnable poison in FLIP fuel have strong influence on the main core characteristics, such as: fuel temperature coefficient, power defect, Xe and Sm worth, power and flux distributions, etc. They are significantly different for both types of fuel. Optimal loading of mixed cores therefore strongly depends on the loading pattern of both types of fuel elements. Results of systematic calculational analysis of mixed cores are presented. Calculations on the level of fuel element are performed with WIMSD-4 computer code with extended cross-section library. Core calculations are performed with TRIGAP two-group 1-D diffusion code. Results are compared to measurements and physical explanation is provided. Special concern is devoted to realistic mixed cores, for which optimal in-core fuel management is derived. Refs, figs and tabs

  16. Operation experience with the 3 MW TRIGA Mark-II research reactor of Bangladesh

    International Nuclear Information System (INIS)

    Islam, M.S.; Haque, M.M.; Salam, M.A.; Rahman, M.M.; Khandokar, M.R.I.; Sardar, M.A.; Saha, P.K.; Haque, A.; Malek Sonar, M.A.; Uddin, M.M.; Hossain, S.M.S.; Zulquarnain, M.A.

    2004-01-01

    The 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) has been operating since September 14, 1986. The reactor is used for radioisotope production ( 131 I, 99m Tc, 46 Sc), various R and D activities and manpower training. The reactor has been operated successfully since it's commissioning with the exception of a few reportable incidents. Of these, the decay tank leakage incident of 1997 is considered to be the most significant one. As a result of this incident, reactor operation at full power under forced-convection mode remained suspended for about 4 years. During that time, the reactor was operated at a power level of 250 kW so as to carry out experiments that require lower neutron flux. This was made possible by establishing a temporary by pass connection across the decay tank using local technology. The other incident was the contamination of the Dry Central Thimble (DCT) that took place in March 2002 when a pyrex vial containing 50 g of TeO 2 powder got melted inside the DCT. The vial was melted due to high heat generation on its surface while the reactor was operated for 8 hours at 3 MW for trial production of Iodine-131 ( 131 I). A Wet Central Thimble (WCT) was used to replace the damaged DCT in June 2002 such that the reactor operation could be resumed. The WCT was again replaced by a new DCT in June 2003 such that radioisotope production could be continued. A total of 873 irradiation requests (IRs) have been catered for different reactor uses. Out of these, 114 IRs were for radioisotope (RI) production and 759 IRs for different experiments. The total amount of RI produced stands at about 2100 GBq. The total amount of burn-up-fuel is about 6158 MWh. Efforts are on to undertake an ADP project so as to convert the analog console and I and C system of the reactor into digital one. The paper summarizes the reactor operation experiences focusing on troubleshooting, rectification, modification, RI production, various R and D

  17. Operation experience and maintenance at the TRIGA Mark II L.E.N.A. reactor

    International Nuclear Information System (INIS)

    Gngoli, F.; Berzero, A.; Lana, F.; Rosti, G.; Meloni, S.

    2008-01-01

    The TRIGA Mark II reactor of the University of Pavia was operated in the last two years on a routine basis, mostly for neutron activation analysis purposes. Moreover the reactor was completely shutdown in the first six months of this year to allow the dismantling of the NADIR experimental setup. The paper presents: - Reactor operation from July 1990 to June 1992; - Reactor users in the time period January 1990 - December 1991; - Specific activities of some radionuclides in the filling materials; - Specific activity of some radionuclides in thermal column materials. Operations related to dismantling of NADIR experimental facility are described. Finally the new thermal column configuration is presented. Starting from the end inside the reactor tank, a graphite layer (35 cm thick) was positioned, followed by a bismuth layer (10 cm thick) to reduce gamma-ray intensity. The old graphite rods were then positioned leaving in the central part, on the equatorial plane of the thermal column, a cavity whose vertical section has 40 cm width and 20 cm height. The bottom of the cavity, towards to the reactor tank, has been lined with additional layers of graphite (10 cm), bismuth (10 cm) and again graphite (1 cm). The new configuration allowed new experiments to be performed. The cavity in the central part has been created to allow the irradiation of large biological samples such as experimental animal and human livers. This is a peculiar step in a neutron capture boron therapy project to be carried out at the University of Pavia. In order to avoid an implemented 41 Ar production in the void space between shutters and the thermal column outer end, the external surface of the thermal column has been coated with boral sheets. The neutron flux profile, both thermal and epithermal, and cadmium ratio for gold are shown. The flux distribution appears to be adequate to proceed with the neutron capture boron therapy experiment. The LENA Health Physics Service has checked all phases of

  18. The possibility of gamma ray sterilization by using ITU TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Bilge, A.N.; Tugrul, B.; Yavuz, H.

    1988-01-01

    Gamma rays are one of the effective method for sterilization which is preferred for a long time. Generally Co-60 radioisotope sources betatrons or accelerators are used for the sterilization. In this work, it was aimed to find the possibilities of the sterilization by gamma rays obtained in ITU TRIGA Mark-II radial tube. Radiation dosages are measured in the radial tube and several medical products are irradiated. Irradiation is arranged according to the desired dosages. Irradiated sterilized goods (mainly medical products) tested and checked at the Governmental Medical Health Center and results compared with literature. It can be seen that this kind of irradiation is a good tool for sterilization. Unfortunately, because of the stability of the radial tube and impracticality of the system it is rather difficult to compete with industrial system using Co-60 and accelerators. Nevertheless, this type of irradiation is also applicable for the purpose of the sterilization by using ITU TRIGA Mark II. (author)

  19. Evaluation for the status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Sook; Lee, Byung Doo

    2007-11-15

    Safeguards implementation of nuclear material was carried out at facility level in an effect to support the peaceful nuclear activities in KAERI. Safeguards implementation is to fulfill the obligations associated with international agreements such as IAEA comprehensive safeguards agreement and additional protocol. IAEA inspection is the most important and basic factor of the safeguards implementation for the purpose of verifying whether all source or special fissionable material is diverted to nuclear weapons or other nuclear explosive devices. The status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor during 2001-2006 is evaluated in this report.

  20. Irradiation positions for fission-track dating in the University of Pavia TRIGA Mark II nuclear reactor

    International Nuclear Information System (INIS)

    Oddone, Massimo; Meloni, Sandro; Balestrieri, Maria Laura; Bigazzi, Giulio

    2002-01-01

    An irradiation position arranged is described in the present paper for fission-track dating in the Triga Mark II reactor of the University of Pavia. Fluence values determined using the NIST glass standard SRM 962a for fission-track dating and the traditional metal foils are compared. Relatively good neutron thermalization (φ th /φ f = 0.956) and lack of significant fluence spatial gradients are good factors for fission-track dating. Finally, international age standards (or putative age standards) irradiated in this new position yielded results consistent with independent reference ages. (author)

  1. Evaluation for the status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor

    International Nuclear Information System (INIS)

    Kim, Hyun Sook; Lee, Byung Doo

    2007-11-01

    Safeguards implementation of nuclear material was carried out at facility level in an effect to support the peaceful nuclear activities in KAERI. Safeguards implementation is to fulfill the obligations associated with international agreements such as IAEA comprehensive safeguards agreement and additional protocol. IAEA inspection is the most important and basic factor of the safeguards implementation for the purpose of verifying whether all source or special fissionable material is diverted to nuclear weapons or other nuclear explosive devices. The status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor during 2001-2006 is evaluated in this report

  2. Neutronics analysis of the TRIGA Mark II reactor core and its experimental facilities

    International Nuclear Information System (INIS)

    Khan, R.

    2010-01-01

    The neutronics analysis of the current core of the TRIGA Mark II research reactor is performed at the Atominstitute (ATI) of Vienna University of Technology. The current core is a completely mixed core having three different types of fuels i.e. aluminium clad 20 % enriched, stainless steel clad 20 % enriched and SS clad 70 % enriched (FLIP) Fuel Elements (FE(s)). The completely mixed nature and complicated irradiation history of the core makes the reactor physics calculations challenging. This PhD neutronics research is performed by employing the combination of two best and well practiced reactor simulation tools i.e. MCNP (general Monte Carlo N-particle transport code) for static analysis and ORIGEN2 (Oak Ridge Isotop Generation and depletion code) for dynamic analysis of the reactor core. The PhD work is started to develop a MCNP model of the first core configuration (March 1962) employing fresh fuel composition. The neutrons reaction data libraries ENDF/B-VI is applied taking the missing isotope of Samarium from JEFF3.1. The MCNP model of the very first core has been confirmed by three different local experiments performed on the first core configuration. These experiments include the first criticality, reactivity distribution and the neutron flux density distribution experiment. The first criticality experiment verifies the MCNP model that core achieves its criticality on addition of the 57th FE with a reactivity difference of about 9.3 cents. The measured reactivity worths of four FE(s) and a graphite element are taken from the log book and compared with MCNP simulated results. The percent difference between calculations and measurements ranges from 4 to 22 %. The neutron flux density mapping experiment confirms the model completely exhibiting good agreement between simulated and the experimental results. Since its first criticality, some additional 104-type and 110-type (FLIP) FE(s) have been added to keep the reactor into operation. This turns the current

  3. Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code

    International Nuclear Information System (INIS)

    Boulaich, Y.; Nacir, B.; El Bardouni, T.; Boukhal, H.; Chakir, E.; El Bakkari, B.; El Younoussi, C.

    2015-01-01

    Highlights: • PARET model for the Moroccan TRIGA MARK II reactor has been developed. • Transient behavior under reactivity insertion has been studied based on PARET code. • Power factors required by PARET code have been calculated by using MCNP5 code. • The dependence on time of the main thermal-hydraulic parameters was calculated. • Results are largely far to compromise the thermal design limits. - Abstract: A three dimensional model for the Moroccan 2 MW TRIGA MARK II reactor has been developed for thermal-hydraulic and safety analysis by using the PARET/ANL and MCNP5 codes. This reactor is located at the nuclear studies center of Mâamora (CENM), Morocco. The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM). The axial distributions of power factors required by the PARET code have been calculated in each fuel element rod by using MCNP5 code. Based on this thermal-hydraulic model, a safety analysis under the reactivity insertion phenomenon has been carried out and the dependence on time of the main thermal-hydraulic parameters was calculated. Results were compared to the thermal design limits imposed to maintain the integrity of the clad

  4. Neutron optics experiments at the TRIGA Mark II reactor of the Atominstitut Wien

    International Nuclear Information System (INIS)

    Jericha, E.; Badurek, G.; Baron, M.; Hasegawa, Y.; Jaekel, M.; Klepp, J.; Rofner, A.; Sponar, S.; Trinker, M.; Villa, M.; Rauch, H.

    2004-01-01

    We present the layout and characteristics of the 3 neutron optics instruments located at the beam ports of the Vienna TRIGA reactor (hosted by the Atominstitut of the Austrian Universities, Vienna University of Technology) and the most recent experiments performed thereon. (author)

  5. Neutron flux measurement in the thermal column of the Malaysian TRIGA mark II reactor with MCNP verification

    International Nuclear Information System (INIS)

    Abdel Munem, E.; Shukri, A.; Tajuddin, A.A.

    2006-01-01

    A study of the thermal column of the Malaysian TRIGA Mark II reactor, forming part of a feasibility study for BNCT was proposed in 2001. In the current study, pure metals were used to measure the neutron flux at selected points in the thermal column and the neutron flux determined using SAND-II. Monte Carlo simulation of the thermal column was also carried out. The reactor core was homogenized and calculations of the neutron flux through the graphite stringers performed using MCNP5. The results show good agreement between the measured flux and the MCNP calculated flux. An obvious extension from this is that the MCNP neutron flux output can be utilized as an input spectrum for SAND-II for the flux iteration. (author)

  6. The new area monitoring system and the fuel database of the TRIGA Mark II reactor in Vienna

    International Nuclear Information System (INIS)

    Villa, M.; Boeck, H.; Hofbauer, M.; Schwarz, V.

    2004-01-01

    The 250 kW TRIGA Mark-II reactor operates since March 1962 at the Atominstitut, Vienna, Austria. Its main tasks are nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection and dosimetry, and low temperature physics and fusion research. Academic research is carried out by students in the above mentioned fields coordinated and supervised by about 70 staff members with the aim of a masters- or PhD degree in one of the above mentioned areas. After 25 years of successful operation, it was necessary to exchange the old area monitoring system with a new digital one. The purpose of the new system is the permanent control of the reactor hall, the primary and secondary cooling system and the monitoring of the ventilation system. The paper describes the development and implementation of the new area monitoring system. The second topic in this paper describes the development of the new fuel database. Since March 7th, 1962, the TRIGA Mark II reactor Vienna operates with an average of 263 MWh per year, which corresponds to a uranium burn-up of 13.7 g per year. Presently we have 81 TRIGA fuel elements in the core, 55 of them are old aluminium clad elements from the initial criticality while the rest are stainless steel clad elements which had been added later to compensate the uranium consumption. Because 67 % of the elements are older than 40 years, it was necessary to put the history of every element in a database, to get an easy access to all the relevant data for every element in our facility. (author)

  7. Core map generation for the ITU TRIGA Mark II research reactor using Genetic Algorithm coupled with Monte Carlo method

    Energy Technology Data Exchange (ETDEWEB)

    Türkmen, Mehmet, E-mail: tm@hacettepe.edu.tr [Nuclear Engineering Department, Hacettepe University, Beytepe Campus, Ankara (Turkey); Çolak, Üner [Energy Institute, Istanbul Technical University, Ayazağa Campus, Maslak, Istanbul (Turkey); Ergün, Şule [Nuclear Engineering Department, Hacettepe University, Beytepe Campus, Ankara (Turkey)

    2015-12-15

    Highlights: • Optimum core maps were generated for the ITU TRIGA Mark II Research Reactor. • Calculations were performed using a Monte Carlo based reactor physics code, MCNP. • Single-Objective and Multi-Objective Genetic Algorithms were used for the optimization. • k{sub eff} and ppf{sub max} were considered as the optimization objectives. • The generated core maps were compared with the fresh core map. - Abstract: The main purpose of this study is to present the results of Core Map (CM) generation calculations for the İstanbul Technical University TRIGA Mark II Research Reactor by using Genetic Algorithms (GA) coupled with a Monte Carlo (MC) based-particle transport code. Optimization problems under consideration are: (i) maximization of the core excess reactivity (ρ{sub ex}) using Single-Objective GA when the burned fuel elements with no fresh fuel elements are used, (ii) maximization of the ρ{sub ex} and minimization of maximum power peaking factor (ppf{sub max}) using Multi-Objective GA when the burned fuels with fresh fuels are used. The results were obtained when all the control rods are fully withdrawn. ρ{sub ex} and ppf{sub max} values of the produced best CMs were provided. Core-averaged neutron spectrum, and variation of neutron fluxes with respect to radial distance were presented for the best CMs. The results show that it is possible to find an optimum CM with an excess reactivity of 1.17 when the burned fuels are used. In the case of a mix of burned fuels and fresh fuels, the best pattern has an excess reactivity of 1.19 with a maximum peaking factor of 1.4843. In addition, when compared with the fresh CM, the thermal fluxes of the generated CMs decrease by about 2% while change in the fast fluxes is about 1%.Classification: J. Core physics.

  8. Verification of Monte Carlo calculations of the neutron flux in the carousel channels of the TRIGA Mark II reactor, Ljubljana

    International Nuclear Information System (INIS)

    Jacimovic, R.; Maucec, M.; Trkov, A.

    2002-01-01

    In this work experimental verification of Monte Carlo neutron flux calculations in the carousel facility (CF) of the 250 kW TRIGA Mark II reactor at the Jozef Stefan Institute is presented. Simulations were carried out using the Monte Carlo radiation-transport code, MCNP4B. The objective of the work was to model and verify experimentally the azimuthal variation of neutron flux in the CF for core No. 176, set up in April 2002. '1'9'8Au activities of Al-Au(0.1%) disks irradiated in 11 channels of the CF covering 180'0 around the perimeter of the core were measured. The comparison between MCNP calculation and measurement shows relatively good agreement and demonstrates the overall accuracy with which the detailed spectral characteristics can be predicted by calculations.(author)

  9. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    International Nuclear Information System (INIS)

    Uddin, M.N.; Sarker, M.M.; Khan, M.J.H.; Islam, S.M.A.

    2010-01-01

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k eff and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  10. Study of a new automatic reactor power control for the TRIGA Mark II reactor at University of Pavia

    Energy Technology Data Exchange (ETDEWEB)

    Borio Di Tigliole, A.; Magrotti, G. [Laboratorio Energia Nucleare Applicata (L.E.N.A.), University of Pavia, Via Aselli 41, 27100 (Italy); Cammi, A.; Memoli, V. [Politecnico di Milano, Department of Energy, Nuclear Engineering Division (CeSNEF), Via Ponzio 34/3, 20133 Milano (Italy); Gadan, M. A. [Instrumentation and Control Department, National Atomic Energy Comission of Argentina, University of Pavia (Italy)

    2009-07-01

    The installation of a new Instrumentation and Control (IC) system for the TRIGA Mark-II reactor at University of Pavia has recently been completed in order to assure a safe and continuous reactor operation for the future. The intervention involved nearly the whole IC system and required a channel-by-channel component substitution. One of the most sensitive part of the intervention concerned the Automatic Reactor Power Controller (ARPC) which permits to keep the reactor at an operator-selected power level acting on the control rod devoted to the fine regulation of system reactivity. This controller installed can be set up using different control logics: currently the system is working in relay mode. The main goal of the work presented in this paper is to set up a Proportional-Integral-Derivative (PID) configuration of the new controller installed on the TRIGA reactor of Pavia so as to optimize the response to system perturbations. The analysis have shown that a continuous PID offers generally better results than the relay mode which causes power oscillations with an amplitude of 3% of the nominal power

  11. Systematical investigations of the emission of carbon 14 from a TRIGA-Mark-II reactor - methods and results

    International Nuclear Information System (INIS)

    Pfeiffer, K.J.

    1981-01-01

    Almost no information is available about the extent of the carbon-14 releases from a research reactor. For this reason this report is dealing with the emission of C-14 from the Vienna TRIGA-Mark-II reactor. In addition the resulting radiation exposure is estimated. Due to the low activity concentrations of C-14 in research reactor effluents special requirements are necessary for sampling and measuring. A technique providing both sufficient lower limit of detection and little effort of sample preparation was developed. Carbon dioxide was trapped by bubbling air taken from the stack through washing bottles containing an aqueous solution of sodium hydroxide. After sampling a precipitate of CaCO 3 was formed and about 8 g of calcium carbonate were counted as a gel suspension by liquid scintillation counting. The formation of the gel was provided by mixing water with a scintillation cocktail originally developed for uptake of high quantities of aqueous solutions. The resulting lower limit of detection was about 50 Bq/kg carbon being equivalent to 9mBq/m 3 air. Concluding the measurements, which were carried out by weekly counting and a period of some 14 months, a normalized release rate of about 280 Bq (7, 1μCi) was found. This release rate is somewhat higher than the reported values for power reactors, because the main activity is produced by activation of air in experimental equipments. (author)

  12. Safety evaluation for instrumentation and control system upgrading project of Malaysian TRIGA MARK II PUSPATI Research reactor

    International Nuclear Information System (INIS)

    Ridha Roslan; Nik Mohd Faiz Khairuddin

    2013-01-01

    Full-text: Malaysian TRIGA MARK II research reactor has been in safe operation since its first criticality in 1982. The reactor is licensed to be operated by Malaysian Nuclear Agency to perform training and research development related activities. Due to its extensive operation since last three decades, the option of modifications for safety and safety-related item and component become a necessary to replace the outdated equipment to a stat-of-art, reliable technologies. This paper will present the current regulatory activities performed by Atomic Energy Licensing Board (AELB) to ensure the upgrading of analogue to digital instrumentation and control system is implemented in safe manner. The review activity includes documentation review, manufacturer quality audit and on-site inspection for commissioning. The review performed by AELB is based on The International Atomic Energy Agency (IAEA) Safety Requirements NS-R-4, entitled Safety of Research Reactors. During this endeavour, AELB seeks technical cooperation from Korea Institute of Nuclear Safety (KINS), the nuclear experts organization of the country of origin of the instrumentation and control technology. The regulatory activity is still on-going and is expected to be completed by issuance of Authorization for Restart on December 2013. (author)

  13. Characterization of typical irradiation channels of CNESTEN'S TRIGA Mark II reactor (Rabat, Morocco) using NAA K0-method

    International Nuclear Information System (INIS)

    Embarch, K.; Bounouira, H.; Bounakhla, M.; Amsil, H.; Jacimovic, R.

    2010-01-01

    The aim of this work is the use of neutron activation analysis using k0-standardization method to characterize some typical irradiation channels of the Moroccan TRIGA Mark II research reactor. The two parameters of neutron flux in the selected irradiation channels used for elemental concentration calculation, f (thermal-to-epithermal ratio) and α (deviation from the 1/E distribution), have been determined as well in the pneumatic tube (PT) as in the carousel facility (CR1) using the zirconium bare triple method. Results obtained for f and α in two irradiation channels show that f parameter determined in this way is different in the carousel facility (CR1) and the PT channel. This can be explained by the fact that the CR1 channel is situated in a graphite reflector and is relatively far from the reactor core, while the PT is in the core. Parameter α in the CR1 has a positive value, as expected, indicating that the neutron spectrum is relatively well thermalized. Parameter α in the PT has a negative value, which is very small and cannot significantly influence the final results obtained by k0-method. The method in our laboratory is validated by analyzing the elemental concentrations of the IAEA Standard Reference Material (Soil-7). All calculations were performed using Kay Win Software. (author)

  14. Operation and maintenance of the 250 kW TRIGA Mark II reactor at the J. Stefan Institute

    International Nuclear Information System (INIS)

    Dimic, V.

    1982-01-01

    Over the last two years the TRIGA Mark II reactor in Ljubljana has been operated at an energy release of about 2250 MWh or about 4200 hours per year. In this period, about 2000 samples were irradiated. Since the last TRIGA Owners' Conference there has been an increase in all operational data because of a very extensive programme of irradiation of molybdenum for the everyday production of technetium-99 m by a solvent extraction method. Because of its age and absolencence replacement of the console electronics was considered some time ago. Therefore, partly new instrumentation was installed this year. A new console is under construction. Furthermore, a new core configuration was established after 7 fresh FLIP fuel elements were delivered by GA. At this time it was noticed that 2 dummy elements are stuck in the upper grid plate. They will be exchanged during the regular maintenance work in August this year. During the last two years the reactor has been operated without any longer shut-down due to technical difficulties. (author)

  15. Safety analysis and optimization of the core fuel reloading for the Moroccan TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Nacir, B.; Boulaich, Y.; Chakir, E.; El Bardouni, T.; El Bakkari, B.; El Younoussi, C.

    2014-01-01

    Highlights: • Additional fresh fuel elements must be added to the reactor core. • TRIGA reactor could safely operate around 2 MW power with 12% fuel elements. • Thermal–hydraulic parameters were calculated and the safety margins are respected. • The 12% fuel elements will have no influence on the safety of the reactor. - Abstract: The Moroccan TRIGA MARK II reactor core is loaded with 8.5% in weight of uranium standard fuel elements. Additional fresh fuel elements must periodically be added to the core in order to remedy the observed low power and to return to the initial reactivity excess at the End Of Cycle. 12%-uranium fuel elements are available to relatively improve the short fuel lifetime associated with standard TRIGA elements. These elements have the same dimensions as standards elements, but with different uranium weight. The objective in this study is to demonstrate that the Moroccan TRIGA reactor could safely operate, around 2 MW power, with new configurations containing these 12% fuel elements. For this purpose, different safety related thermal–hydraulic parameters have been calculated in order to ensure that the safety margins are largely respected. Therefore, the PARET model for this TRIGA reactor that was previously developed and combined with the MCNP transport code in order to calculate the 3-D temperature distribution in the core and all the most important parameters like the axial distribution of DNBR (Departure from Nucleate Boiling Ratio) across the hottest channel. The most important conclusion is that the 12% fuel elements utilization will have no influence on the safety of the reactor while working around 2 MW power especially for configurations based on insertions in C and D-rings

  16. Trends in the operation of the LENA 250 kW TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Meloni, S.; Cambieri, A.; Cingoli, F.; Genova, N.

    1972-01-01

    A general trend is observed in the past two years of an ageing of all the equipment in the Laboratory, namely electronic equipment, auxiliary apparatus, and irradiation devices such as the rotary specimen rack, which means a higher cost of the reactor operation and management. As far as the utilization of the reactor is concerned in the past two years, an increase is experienced in the number of experiments to be carried out with the reactor. Data about the reactor operation, maintenance and utilization during the past two years are presented in the report

  17. Operation experience with the TRIGA Mark II reactor Vienna in the years 1972 through 1974

    International Nuclear Information System (INIS)

    Boeck, H.

    1974-01-01

    Since the last TRIGA Users Conference in Pavia 1972 the TRIGA reactor Vienna was in operation without any larger undesired shut-down. The integral thermal power production by Sept. 1, 1974 was 3420 MWh. The principal work carried out during the last two years on the reactor system was the installation of a new heat exchanger and primary pump both designed for 1 MW steady state operation. Permission was also obtained from the local authority to withdraw up to 90 m 3 /h secondary cooling water from the well. Some troubles were observed with the pulse rod. After nearly 12 years of operation the connection between the piston rod and control rod broke off just below the water surface. Therefore the piston was shot out without withdrawing the pulse rod itself. After locating the trouble the damage was repaired within one day. The SST fuel elements type 110 were received by the end of 1972 for the purpose of power upgrading. All other fuel elements except one are still located in the reactor core and shifted periodically in order to obtain an optimal burnup. A new alarm system was ordered from Hartmann and Braun and is under installation at the moment. In order to facilitate cooperation with the reactor operation personnel and the experimenters in the reactor hall an accurate power indicator has been installed in the reactor hall which allows all experimenters to read the reactor power as accurately as in the control room itself. (U.S.)

  18. Current research work carried out at the 250 kW TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Dimic, V.; Kristof, E.; Rant, J.

    1972-01-01

    The main physics experiments accomplished during the last two years of the reactor operation include the cold neutron, fast neutron and n-gamma spectrometry, neutron radiography and in the radiochemical laboratory quite extensive program on neutron activation analysis is carried on the seed irradiation facilities in connection with the research contract with the IAEA were constructed. In additional, the connection of the reactor to the on-line computer CDC 1700 is finished. The task of this work is the monitoring and control of the reactor power level and other operating conditions. This paper deals briefly only with the cold neutron, fast neutron and n-gamma spectrometry. The other fields of activity at our reactor will be described more in detail in the separate papers presented in this section

  19. Research programs carried out at the TRIGA Mark II reactor Vienna

    International Nuclear Information System (INIS)

    Bock, H.

    1978-01-01

    During the period July 1976 to July 1978 approximately 170 papers have been published by staff members of the Atominstitute in scientific journals covering the main research fields which are: radiation physics; nuclear physics; reactor technology; neutron solid state physics; radiochemistry; health physics. In the department of reactor technology research work was is done on in-core instrumentation, failed fuel element detection systems and neutron radiography

  20. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    International Nuclear Information System (INIS)

    Ryan, B.C.

    1997-05-01

    This report is a final culmination of activities funded through the Department of Energy's (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher's workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead

  1. TRIGA Mark II nuclear reactor facility. Final report, 1 July 1980--30 June 1995

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, B.C.

    1997-05-01

    This report is a final culmination of activities funded through the Department of Energy`s (DOE) University Reactor Sharing Program, Grant DE-FG02-80ER10273, during the period 1 July 1980 through 30 June 1995. Progress reports have been periodically issued to the DOE, namely the Reactor Facility Annual Reports C00-2082/2219-7 through C00-2082/10723-21, which are contained as an appendix to this report. Due to the extent of time covered by this grant, summary tables are presented. Table 1 lists the fiscal year financial obligations of the grant. As listed in the original grant proposals, the DOE grant financed 70% of project costs, namely the total amount spent of these projects minus materials costs and technical support. Thus the bulk of funds was spent directly on reactor operations. With the exception of a few years, spending was in excess of the grant amount. As shown in Tables 2 and 3, the Reactor Sharing grant funded a immense number of research projects in nuclear engineering, geology, animal science, chemistry, anthropology, veterinary medicine, and many other fields. A list of these users is provided. Out of the average 3000 visitors per year, some groups participated in classes involving the reactor such as Boy Scout Merit Badge classes, teacher`s workshops, and summer internships. A large number of these projects met the requirements for the Reactor Sharing grant, but were funded by the University instead.

  2. Adaptive control method for core power control in TRIGA Mark II reactor

    Science.gov (United States)

    Sabri Minhat, Mohd; Selamat, Hazlina; Subha, Nurul Adilla Mohd

    2018-01-01

    The 1MWth Reactor TRIGA PUSPATI (RTP) Mark II type has undergone more than 35 years of operation. The existing core power control uses feedback control algorithm (FCA). It is challenging to keep the core power stable at the desired value within acceptable error bands to meet the safety demand of RTP due to the sensitivity of nuclear research reactor operation. Currently, the system is not satisfied with power tracking performance and can be improved. Therefore, a new design core power control is very important to improve the current performance in tracking and regulate reactor power by control the movement of control rods. In this paper, the adaptive controller and focus on Model Reference Adaptive Control (MRAC) and Self-Tuning Control (STC) were applied to the control of the core power. The model for core power control was based on mathematical models of the reactor core, adaptive controller model, and control rods selection programming. The mathematical models of the reactor core were based on point kinetics model, thermal hydraulic models, and reactivity models. The adaptive control model was presented using Lyapunov method to ensure stable close loop system and STC Generalised Minimum Variance (GMV) Controller was not necessary to know the exact plant transfer function in designing the core power control. The performance between proposed adaptive control and FCA will be compared via computer simulation and analysed the simulation results manifest the effectiveness and the good performance of the proposed control method for core power control.

  3. Operating experience and maintenance at the TRIGA Mark II LENA reactor

    International Nuclear Information System (INIS)

    Cingoli, F.; Meloni, S.; Alloni, L.

    1986-01-01

    A summary of reactor operation and maintenance in the time period 1982-1986 is presented and discussed. Some problems occurred from instrumentated aluminum cladded elements. Both of them presented damage in the cable tubes and one element showed a protuberance in the cladding. They were replaced with stainless - steel cladded ones. Both elements were sealed up in stainless - steel tubes and put away in wells, 3 meters deep, in the reactor room floor. Some minor problems, correlated to the quite aid instrumentation of the console, are reported. The reactor activity in the last four years was conditioned by the developing of the n - n-bar oscillation NADIR experiment. The thermal column was dismantled and rebuilt in consideration of the Nadir experiment necessities and this job is described in detail. The building containing, the target and the void pipe, presented in 1982 Conference, are now completely operating and the experiment is running. (author)

  4. Operating experience and maintenance at the TRIGA Mark II LENA reactor

    International Nuclear Information System (INIS)

    Cingoli, F.; Altieri, S.; Lana, F.; Rosti, G.; Alloni, L.; Meloni, S.

    1988-01-01

    The last two years at the Trigs Mark II LENA plant were characterized by the running of the n-n-bar oscillation NADIR experiment. Consequently reactor operation was positively affected and the running hours rose again above 1000 hours per year. The LENA team was also deeply involved in the procedures for the renewal of the reactor operation license. The new requirements set by the Nuclear Energy Licensing Authority (ENEA for Italy) most of which concerning radiation protection and environmental impact, have been already fulfilled. In some cases the installation of new apparatus is underway

  5. Modeling a TRIGA Mark II reactor using the Attila three-dimensional deterministic transport code

    International Nuclear Information System (INIS)

    Keller, S.T.; Palmer, T.S.; Wareing, T.A.

    2005-01-01

    A benchmark model of a TRIGA reactor constructed using materials and dimensions similar to existing TRIGA reactors was analyzed using MCNP and the recently developed deterministic transport code Attila TM . The benchmark reactor requires no MCNP modeling approximations, yet is sufficiently complex to validate the new modeling techniques. Geometric properties of the benchmark reactor are specified for use by Attila TM with CAD software. Materials are treated individually in MCNP. Materials used in Attila TM that are clad are homogenized. Attila TM uses multigroup energy discretization. Two cross section libraries were constructed for comparison. A 16 group library collapsed from the SCALE 4.4.a 238 group library provided better results than a seven group library calculated with WIMS-ANL. Values of the k-effective eigenvalue and scalar flux as a function of location and energy were calculated by the two codes. The calculated values for k-effective and spatially averaged neutron flux were found to be in good agreement. Flux distribution by space and energy also agreed well. Attila TM results could be improved with increased spatial and angular resolution and revised energy group structure. (authors)

  6. In-service inspection and maintenance schedule for a typical TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    Boeck, H.

    1996-05-01

    This report lists all the systems and components of the TRIGA reactor Vienna which are inspected and maintained in regular intervals. These intervals are categorized in monthly, quarterly, semi-annual and annual inspections. Further the type of inspection and the responsibility for the inspection is shown. For each component specific inspection sheets have been developed, some examples are given in the annex. (author)

  7. A high performance neutron powder diffractometer at 3 MW Triga Mark-II research reactor in Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Kamal, I., E-mail: imtiaz-kamal26@yahoo.com; Yunus, S. M., E-mail: yunussm11@yahoo.com; Datta, T. K., E-mail: tk-datta4@yahoo.com; Zakaria, A. K. M.; Das, A. K.; Aktar, S.; Hossain, S. [Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, Dhaka (Bangladesh); Berliner, R., E-mail: RB@instrumentationAssociates.com [Instrumentation Associates, Durham, North Carolina (United States); Yelon, W. B., E-mail: yelonwb@hotmail.com [Oak Ridge National Laboratory, Oak Ridge, Tennessee (United States)

    2016-07-12

    A high performance neutron diffractometer called Savar Neutron Diffractometer (SAND) was built and installed at radial beam port-2 of TRIGA Mark II research reactor at AERE, Savar, Dhaka, Bangladesh. Structural studies of materials are being done by this technique to characterize materials crystallograpohically and magnetically. The micro-structural information obtainable by neutron scattering method is very essential for determining its technological applications. This technique is unique for understanding the magnetic behavior in magnetic materials. Ceramic, steel, electronic and electric industries can be benefited from this facility for improving their products and fabrication process. This instrument consists of a Popovicimonochromator with a large linear position sensitive detector array. The monochromator consists of nine blades of perfect single crystal of silicon with 6 mm thickness each. The monochromator design was optimized to provide maximum flux on 3 mm diameter cylindrical sample with a relatively flat angular dependence of resolution. Five different wave lengths can be selected by orienting the crystal at various angles. A sapphire filter was used before the primary collimator to minimize the first neutron. The detector assembly is composed of 15 linear position sensitive proportional counters placed at either 1.1 m or 1.6 m from the sample position and enclosed in a air pad supported high density polythene shield. Position sensing is obtained by charge division using 1-wide NIM position encoding modules (PEM). The PEMs communicate with the host computer via USB. The detector when placed at 1.1 m, subtends 30° (2θ) at each step and covers 120° in 4 steps. When the detector is placed at 1.6 m it subtends 20° at each step and covers 120° in 6 steps. The instrument supports both low and high temperature sample environment. The instrument supports both low and high temperature sample environment. The diffractometer is a state-of-the art technology

  8. Fast neutron spectrum in the exposure room of the TRIGA Mark II reactor in Ljubljana

    International Nuclear Information System (INIS)

    Kristof, E.S.

    2003-01-01

    In this paper a description of the high energy neutrons at a usual position in the dry cell of our reactor is given. Neutrons emerging from the graphite reflector enter the exposure room through the horizontal shaft. At the irradiation position samples of detection materials were irradiated. After irradiation γ-ray spectra were measured and from the saturation activities the spectrum was calculated. (author)

  9. Analysis of crack-formation in the shielding concrete of a TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Linsbauer, H.; Maydl, P.

    1978-01-01

    Within a short time after the start-up of the reactor several cracks appeared at the concrete surface and the number and width of the cracks had grown till now. Experimental and theoretical analysis were made in order to investigate the origin of the cracks and to prevent further crack increase. Crack movement was measured by inductive gages and simultaneously the temperature of the cooling water in the reactor tank at the top and at the bottom as well as the air and the concrete temperature were recorded. The calculations of the thermal stresses were made in two independent ways: 1. Analytically, simulating the shielding concrete as an infinite hollow cylinder of constant thickness and 2. Using the Finite Element method, for a better description of the geometry. It was concluded that the cracks of the shielding concrete are exclusively caused by the thermal stresses. The thermal insulation at the lower part of the shielding is not effective. The structural system of the shielding concrete as a monolithic block without joints produces automatically tensile stresses

  10. Reaction Rate Benchmark Experiments with Miniature Fission Chambers at the Slovenian TRIGA Mark II Reactor

    Science.gov (United States)

    Štancar, Žiga; Kaiba, Tanja; Snoj, Luka; Barbot, Loïc; Destouches, Christophe; Fourmentel, Damien; Villard, Jean-François AD(; )

    2018-01-01

    A series of fission rate profile measurements with miniature fission chambers, developed by the Commisariat á l'énergie atomique et auxénergies alternatives, were performed at the Jožef Stefan Institute's TRIGA research reactor. Two types of fission chambers with different fissionable coating (235U and 238U) were used to perform axial fission rate profile measurements at various radial positions and several control rod configurations. The experimental campaign was supported by an extensive set of computations, based on a validated Monte Carlo computational model of the TRIGA reactor. The computing effort included neutron transport calculations to support the planning and design of the experiments as well as calculations to aid the evaluation of experimental and computational uncertainties and major biases. The evaluation of uncertainties was performed by employing various types of sensitivity analyses such as experimental parameter perturbation and core reaction rate gradient calculations. It has been found that the experimental uncertainty of the measurements is sufficiently low, i.e. the total relative fission rate uncertainty being approximately 5 %, in order for the experiments to serve as benchmark experiments for validation of fission rate profiles. The effect of the neutron flux redistribution due to the control rod movement was studied by performing measurements and calculations of fission rates and fission chamber responses in different axial and radial positions at different control rod configurations. It was confirmed that the control rod movement affects the position of the maximum in the axial fission rate distribution, as well as the height of the local maxima. The optimal detector position, in which the redistributions would have minimum effect on its signal, was determined.

  11. Operating experiences and utilization programmes of the BAEC 3 MW TRIGA Mark-II research reactor of Bangladesh

    International Nuclear Information System (INIS)

    Haque, M.M.; Soner, M.A.M.; Saha, P.K.; Salam, M.A.; Zulquarnain, M.A.

    2008-01-01

    The 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) has been operating since September 14, 1986. The reactor is used for radioisotope production ( 131 I, 99m Tc, 46 Sc), various R and D activities, manpower training and education. The reactor has been operated successfully since its commissioning with the exception of a few reportable incidents. Of these, the decay tank leakage incident of 1997 is considered to be the most significant one. As a result of this incident, reactor operation at full power remained suspended for about 4 years. However, the reactor operation was continued during this period at a power level of 250 kW to cater the needs of various R and D groups, which required lower neutron flux for their experiments. This was made possible by establishing a temporary by pass connection across the decay tank using local technology. The reactor was made operational again at full power after successful replacement of the damaged decay tank in August 2001. At that time, several modifications of the reactor cooling system along with its associated structures were also implemented and then necessary testing and commissioning of the newly installed component/equipment were carried out. The other incident was the contamination of the Dry Central Thimble (DCT) that took place in March 2002 when a pyrex vial containing 50g of TeO 2 powder got melted inside the DCT. The vial was melted due to high heat generation on its surface while the reactor was operated for 8 hours at 3 MW for trial production of Iodine-131 ( 131 I). A Wet Central Thimble (WCT) was used to replace the damaged DCT in June 2002 such that the reactor operation could be resumed. The WCT was again replaced by a new DCT in June 2003 such that radioisotope production could be continued. The facility has so far been used to train up a total of 27 personnel including several foreign nationals to the level of Senior Reactor Operator (SRO) and Reactor Operator (RO). The

  12. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes

    International Nuclear Information System (INIS)

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

    2011-01-01

    Research highlights: → The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. → The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). → The most important conclusion is that all obtained values of DNBR, fuel center and surface temperature, cladding surface temperature and coolant temperature across the hottest channel are largely far to compromise safety of the reactor. - Abstract: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. In order to validate our PARET/ANL and COOLOD-N2 models, the fuel center temperature as function of core power was calculated and compared with the corresponding experimental values. The comparison indicates that the calculated values are in satisfactory agreement with the measurement. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). Therefore, we have calculated the departure from nucleate boiling ratio (DNBR), fuel center and surface temperature, cladding surface temperature and coolant temperature profiles across the hottest channel. The most important conclusion is that all obtained values are largely far to compromise safety of the reactor.

  13. Measurement of the neutron activation constants Q0 and k0 for the 27Al(n, γ)28Al reaction at the JSI TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Vladimir Radulovic; Andrej Trkov; Radojko Jacimovic; Robert Jeraj

    2013-01-01

    Measurements of the neutron activation constants Q 0 and k 0 for the 27 Al(n, γ) 28 Al reaction have been performed in two irradiation channels with different spectral characteristics at the JSI TRIGA Mark II reactor. In the determination of Q 0 the fission spectrum contribution to the reaction rates has been corrected for. The final experimental value of the Q 0 factor was found to differ significantly from the adopted value in the k 0 -database. The experimental value of the k 0 factor is in agreement with the recommended value in the k 0 -database. The thermal cross-section and resonance integral for the reaction were found to be in good agreement with the values calculated from the cross-sections from the ENDF/B-VII.1 library. (author)

  14. Experience in operation and maintenance of the TRIGA Mark II reactor at the University of Pavia in the time period July 1974 - June 1976

    International Nuclear Information System (INIS)

    Cambieri, A.; Cingoli, F.; Genova, N.; Meloni, S.; Perlini, G.

    1976-01-01

    The operation of the 250 kW steady state/250 MW pulsed TRIGA Mark II Reactor of the University of Pavia over the past two years is presented and discussed. Reactor maintenance activity is presented as well. Data for reactor utilization and a summary of the health physics procedures are also given. Since the third European Conference of TRIGA Reactor Users in 1974, reactor operation took place smoothly without major troubles. Because of the core excess decrease due to reactor operation and consequent burn-up, ten new stainless steel clad fuel elements were bought from General Atomic. Reactor operation license expired at the end of 1975 and it is now under way the bureaucratic work to get its renewal. The aging of the electronic equipment raises minor problems and the predicted switching to a new solid state equipment started by changing the old electromechanical rod position indicators with new digital ones. The installation of the Euracos II facility (Enriched Uranium Converter Source), described at the last TRIGA Users Conference, began at the end of 1975 and it is still under way. The first operation of the facility will take place at reduced power so that the removal of the graphite blocks from thermal column was not accomplished. The installation of the facility is described and the procedures of its operation in connection with reactor operation are presented as well. (author)

  15. The study of time-dependent neutronics parameters of the 2MW TRIGA Mark II Moroccan research reactor using BUCAL1 computer code

    International Nuclear Information System (INIS)

    Bakkari, B. El; Nacir, B.; El Younoussi, C.; Boulaich, Y.; Riyach, I.; Otmani, S.; Marcih, I.; Elbadri, H.; El Bardouni, T; Merroun, O.; Boukhal, H.; Zoubair, M.; Htet, A.; Chakir, M.

    2010-01-01

    The 2-MW TRIGA MARK II research reactor at Centre National de l'Energie, des Sciences et des Techniques Nucleaires (CNESTEN) achieved initial criticality on May 2, 2007 with 71 fuel elements. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower and training and production of radioisotopes for their use in agriculture, industry and medicine. This work aims to study the time-dependent neutronics parameters of the TRIGA reactor for elaborating and planning of an in-core fuel management strategy to maximize the utilization of the TRIGA fluxes, using a new elaborated burnup computer code called 'BUCAL1'. The code can be used to aid in analysis, prediction, and optimization of fuel burnup performance in a nuclear reactor. It was developed to incorporate the neutron absorption tally/reaction information generated directly by MCNP5 code in the calculation of fissioned or neutron-transmuted isotopes for multi-fueled regions. The use of Monte Carlo method and punctual cross section data characterizing the MCNP code allows an accurate simulation of neutron life cycle in the reactor, and the integration of data on the entire energy spectrum, thus a more accurate estimation of results than deterministic code can do. Also, for the purpose of this study, a full-model of the TRIGA reactor was developed using the MCNP5 code. The validation of the MCNP model of the TRIGA reactor was made by benchmarking the reactivity experiments. (author)

  16. Power level control of the TRIGA Mark-II research reactor using the multifeedback layer neural network and the particle swarm optimization

    International Nuclear Information System (INIS)

    Coban, Ramazan

    2014-01-01

    Highlights: • A multifeedback-layer neural network controller is presented for a research reactor. • Off-line learning of the MFLNN is accomplished by the PSO algorithm. • The results revealed that the MFLNN–PSO controller has a remarkable performance. - Abstract: In this paper, an artificial neural network controller is presented using the Multifeedback-Layer Neural Network (MFLNN), which is a recently proposed recurrent neural network, for neutronic power level control of a nuclear research reactor. Off-line learning of the MFLNN is accomplished by the Particle Swarm Optimization (PSO) algorithm. The MFLNN-PSO controller design is based on a nonlinear model of the TRIGA Mark-II research reactor. The learning and the test processes are implemented by means of a computer program at different power levels. The simulation results obtained reveal that the MFLNN-PSO controller has a remarkable performance on the neutronic power level control of the reactor for tracking the step reference power trajectories

  17. Criticality and safety parameter studies for upgrading 3 MW TRIGA MARK II research reactor and validation of generated cross section library and computational method

    International Nuclear Information System (INIS)

    Bhuiyan, S.I.; Mondal, M.A.W.; Sarker, M.M.; Rahman, M.; Shahdatullah, M.S.; Huda, M.Q.; Chakrroborty, T.K.; Khan, M.J.H.

    2000-01-01

    This study deals with the neutronic and thermal hydraulic analysis of the 3MW TRIGA MARK II research reactor to upgrade it to a higher flux. The upgrading will need a major reshuffling and reconfiguration of the current core. To reshuffle the current core configuration, the chain of NJOY94.10 - WIMSD-5A - CITATION - PARET - MCNP4B2 codes has been used for the overall analysis. The computational methods, tools and techniques, customisation of cross section libraries, various models for cells and super cells, and a lot of associated utilities have been standardised and established/validated for the overall core analysis. Analyses using the 4-group and 7-group libraries of macroscopic cross sections generated from the 69-group WIMSD-5 library showed that a 7-group structure is more suitable for TRIGA calculations considering its LEU fuel composition. The MCNP calculations established that the CITATION calculations and the generated cross section library are reasonably good for neutronic analysis of TRIGA reactors. Results obtained from PARET demonstrated that the flux upgrade will not cause the temperature limit on the fuel to be exceeded. Also, the maximum power density remains, by a substantial margin below the level at which the departure from nucleate boiling could occur. A possible core with two additional irradiation channels around the CT is projected where almost identical thermal fluxes as in the CT are obtained. The reconfigured core also shows 7.25% thermal flux increase in the Lazy Susan. (author)

  18. Comparison of neutron fluxes obtained by 2-D and 3-D geometry with different shielding libraries in biological shield of the TRIGA MARK II reactor

    International Nuclear Information System (INIS)

    Bozic, M.; Zagar, T.; Ravnik, M.

    2003-01-01

    Neutron fluxes in different spatial locations in biological shield are obtained with TORT code (TORT-Three Dimensional Oak Ridge Discrete Ordinates Neutron/Photon Transport Code). Libraries used with TORT code were BUGLE-96 library (coupled library with 47 neutron groups and 20 gamma groups) and VITAMIN-B6 library (coupled library with 199 neutron groups and 42 gamma groups). BUGLE-96 library is derived from VITAMIN-B6 library. 2-D and 3-D models for homogeneous type of problem (without inserted beam port 4) and problem with asymmetry (non-homogeneous problem; inserted beam port 4, filled with different materials) were of interest for neutron flux calculation. The main purpose is to verify the possibility for using 2-D approximation model instead of large 3-D model in some calculations. Another purpose of this paper was to compare neutron spectral constants obtained from neutron fluxes (3-D model) determined with smaller BUGLE-96 library with new constants obtained from fluxes calculated with bigger VITAMIN-B6 library. These neutron spectral constants are used in isotopic calculation with SCALE code package (ORIGEN-S). In past only neutron spectral constants determined by neutron fluxes from BUGLE-96 library were used. Experimental results used for isotopic composition comparison are available from irradiation experiment with selected type of concrete and other materials in beam port 4 (irradiation channel 4) in TRIGA Mark II reactor. These experimental results were used as a benchmark in this paper. (author)

  19. Improved measurements of thermal power and control rods using multiple detectors at the TRIGA Mark II reactor in Ljubljana

    International Nuclear Information System (INIS)

    Zerovnik Gasper; Snoj Luka; Trkov Andrej; Barbot Loic; Fourmentel Damien; Villard Jean-Francois

    2013-06-01

    The aim of the current bilateral project between CEA Cadarache and JSI is to improve the accuracy of the online thermal power monitoring at the JSI TRIGA reactor. Simultaneously, a new wide range multichannel acquisition system for fission chambers, recently developed by CEA, is tested. In the paper, calculational and experimental power calibration methods are described. The focus is on use of multiple detectors in combination with pre-calculated and pre-measured control rod- position-dependent correction factors to improve the reactor power reading. The system will be implemented and tested at the JSI TRIGA reactor in 2014. (authors)

  20. Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

    International Nuclear Information System (INIS)

    Salam, M. A.

    2013-01-01

    The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

  1. Refurbishment, Modernization and Ageing Management Program of The 3MW TRIGA Mark-II Research Reactor of Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Salam, M. A. [Atomic Energy Research Establishment, Dhaka (Bangladesh)

    2013-07-01

    The 3 MW TRIGA MK-II research reactor of Bangladesh Atomic Energy Commission (BAEC) achieved its first criticality on 14 September 1986. The reactor has been used for manpower training, radioisotope production and various R and D activities in the field of neutron activation analysis, neutron radiography and neutron scattering. Reactor Operation and Maintenance Unit (ROMU) is responsible for operation and maintenance of the research reactor. During the past twenty seven years ROMU carried out several refurbishments, replacement, modification and modernization activities in the reactor facility. The major tasks carried out under refurbishment program were replacement of the corrosion damaged N-16 decay tank by a new one, replacement of the fouled shell and tube type heat exchanger by a plate type one, modification of the shielding arrangements around the N-16 decay tank and ECCS system and solving the radial beam port-1 leakage problem. All of these refurbishment activities were performed under an annual development project (ADP) funded by Bangladesh government. BAEC research reactor (RR) was operated by analogue console system from its commissioning to July, 2011. Old analog based console has been replaced by digital console on June, 2012. Modernization program for the reactor control console due to obsolescence and unavailability of spare parts of I and C system was vital to restore the safe operation of the reactor. Considering these facts, installation of a digital control console and I and C system based on the state-of-the-art digital technology became necessary. Reactor digital console system installation tasks were performed under another ADP funded project by Bangladesh government. Now the reactor is operating with the digital control system. Besides this, the Neutron Radiography (NR) facility has been modernized by the addition of a digital neutron radiography set-up at the tangential beam port. The Neutron Scattering (NS) facility also has been upgraded

  2. Corrosion Induced Leakage Problem of the Radial Beam Port 1 of BAEC Triga Mark-II Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kalam, A.; Salam, M. A.; Sarder, M. A.; Rahman, M. M.; Rahman, M.; Rahman, A.; Chowdhury, A. Z.; Uddin, M. S.; Haque, M. M.; Zulquarnain, M.A., E-mail: kalambaec@yahoo.com [Reactor Operation and Maintenance Unit, Atomic Energy Research Establishment (AERE), Dhaka (Bangladesh)

    2014-08-15

    The BAEC reactor has so far been operated as per the technical specifications and procedures laid down in the SAR of the research reactor. The BP leakage problem of the BAEC research reactor was an issue that could lead to a situation close to a LOCA. Therefore, the matter was handled carefully, taking all measures so that such an incident could be prevented. Assistance of agencies outside BAEC was taken for solving the problem. It is understood that the silicone rubber lining of the encirclement clamp may become damaged by neutron irradiation. Therefore, while designing the clamp, provisions were kept such that it can be dismantled and reinstalled again following lining replacement. As a moderately aged facility, the ageing management BAEC TRIGA research reactor deserves significant attention. BAEC, together with its strategic partners, are doing what is needed in this regard.

  3. Operation and maintenance of the 250 kW TRIGA Mark II reactor at the J. Stefan Institute

    International Nuclear Information System (INIS)

    Dimic, V.; Mrcun, I.

    1978-01-01

    During the last two years the reactor was in operation without any longer shut-down. Only a small bending of the regulating control rod was noticed. This failure was repaired. One of the major problem, but not connected to the operation of the reactor, is the delivery of the new FLIP fuel elements. Since the beginning of operation, the reactor has been at full power about 24-00 hours per year, or 220 hours per month, which means that the utilization of the reactor in Ljubljana is relatively very high. One of the reasons for this high utilization is the quite extensive production of radioactive isotopes, especially short lived, for various consumers and the irradiation of samples for our nuclear chemistry division. Problems with rotary specimen rack occurred and a new rotary specimen rack was installed. During the last years some of the original instrumentation of the reactor was substituted because of ageing of the electronics or to improve the operational capabilities of the reactor

  4. Operation and maintenance of the 250 kW TRIGA Mark II reactor at the J. Stefan Institute

    International Nuclear Information System (INIS)

    Dimic, V.

    1980-01-01

    Since the last TRIGA Conference, the reactor has completed approximately 4800 operating hours without major problems. The problem with the lack of fresh fuel elements is going to be solved after the signing of a new agreement for the supply of fuel between the IAEA, the Yugoslav and US Governments. In order to increase the reactivity the fuel elements from the outer zone we shuffled to the inner zone, and old fuel elements from the fuel container were added to the F ring. Due to the large demand for irradiation, a new pneumatic facility for loading and unloading the samples in the rotary specimen rack or central thimble has been constructed and installed. A configuration based on two microcomputers in a master slave hierarchical organisation for automatic data logging and direct has been finished and the system was installed after extensive testing. The reactor operation is now more reliable and simpler for the operators. Some of the original instrumentation of the reactor has been gradually substituted because of ageing: a start-up channel with digital display, a power integrator, a digital electronic rod position indicator, a digital power range switch without resistors and a new 2-pen recorder have been installed. The following instrumentation was ordered by the IAEA from the Hartmann and Brawn company: a start-up channel, a log channel, a safety channel, an automatic power control and water temperature, conductivity, level and activity measuring units. During the last year, with the help of our nuclear chemistry department, the production of high concentration and high purity technetium-99 m for medical use was developed by a solvent extraction method

  5. Comparative Study of some Parameters reported in the Safety Analysis Report of TRIGA MARK II Research reactor with Calculations

    International Nuclear Information System (INIS)

    Chakrobortty, T.K.; Huda, M.Q.; Bhuiyan, S.I.; Mondal, M.A.W.

    1997-06-01

    An attempt has been made to investigate some of the parametric results reported in the safety Analysis Report (SAR) with the theoretical analysis carried out by different computer codes and data bases. Different neutronics, thermal hydraulics and safety parameters such as core criticality and burnup lifetime, power peaking factor, prompt negative temperature coefficient, neutron flux, pulse characteristics, steady state and transient behaviors of the TRIGA reactor were analyzed. The investigated results were found to be in fairly good agreement with the values reported in the SAR. 12 refs., 14 figs., 1 table (Author)

  6. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3

    International Nuclear Information System (INIS)

    Altaf, M.H.; Badrun, N.H.; Chowdhury, M.T.

    2015-01-01

    Highlights: • SRAC-PIJ code and SRAC-CITATION have been utilized to model the core. • Most of the simulated results show no significant differences with references. • Thermal peak flux varies a bit due to up condition of TRIGA. • ENDF/B-VII.0 and JENDL-3.3 libraries perform well for neutronics analysis of TRIGA. - Abstract: Important kinetic parameters such as effective multiplication factor, k eff , excess reactivity, neutron flux and power distribution, and power peaking factors of TRIGA Mark II research reactor in Bangladesh have been calculated using the comprehensive neutronics calculation code system SRAC 2006 with the evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3. In the code system, PIJ code was employed to obtain cross section of the core cells, followed by the integral calculation of neutronic parameters of the reactor conducted by CITATION code. All the analyses were performed using the 7-group macroscopic cross section library. Results were compared to the experimental data, the safety analysis report (SAR) of the reactor provided by General Atomic as well as to the simulated values by numerically benchmarked MCNP4C, WIMS-CITATION and SRAC-CITATION codes. The maximum power densities at the hot spot were found to be 169.7 W/cc and 170.1 W/cc for data libraries ENDF/B-VII.0 and JENDL-3.3, respectively. Similarly, the total peaking factors based on ENDF/B-VII.0 and JENDL-3.3 were calculated as 5.68 and 5.70, respectively, which were compared to the original SAR value of 5.63, as well as to MCNP4C, WIMS-CITATION and SRAC-CITATION results. It was found in most cases that the calculated results demonstrate a good agreement with our experiments and published works. Therefore, this analysis benchmarks the code system and will be helpful to enhance further neutronics and thermal hydraulics study of the reactor

  7. Validation of absolute axial neutron flux distribution calculations with MCNP with 197Au(n,γ)198Au reaction rate distribution measurements at the JSI TRIGA Mark II reactor.

    Science.gov (United States)

    Radulović, Vladimir; Štancar, Žiga; Snoj, Luka; Trkov, Andrej

    2014-02-01

    The calculation of axial neutron flux distributions with the MCNP code at the JSI TRIGA Mark II reactor has been validated with experimental measurements of the (197)Au(n,γ)(198)Au reaction rate. The calculated absolute reaction rate values, scaled according to the reactor power and corrected for the flux redistribution effect, are in good agreement with the experimental results. The effect of different cross-section libraries on the calculations has been investigated and shown to be minor. Copyright © 2013 Elsevier Ltd. All rights reserved.

  8. Burn-up TRIGA Mark II benchmark experiment

    International Nuclear Information System (INIS)

    Persic, A.; Ravnik, M.; Zagar, T.

    1998-01-01

    Different reactor codes are used for calculations of reactor parameters. The accuracy of the programs is tested through comparison of the calculated values with the experimental results. Well-defined and accurately measured benchmarks are required. The experimental results of reactivity measurements, fuel element reactivity worth distribution and fuel-up measurements are presented in this paper. The experiments were performed with partly burnt reactor core. The experimental conditions were well defined, so that the results can be used as a burn-up benchmark test case for a TRIGA Mark II reactor calculations.(author)

  9. Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

    International Nuclear Information System (INIS)

    Khan, Jahirul Haque

    2013-01-01

    The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark-II

  10. MCNP simulation of the TRIGA Mark II benchmark experiment

    International Nuclear Information System (INIS)

    Jeraj, R.; Glumac, B.; Maucec, M.

    1996-01-01

    The complete 3D MCNP model of the TRIGA Mark II reactor is presented. It enables precise calculations of some quantities of interest in a steady-state mode of operation. Calculational results are compared to the experimental results gathered during reactor reconstruction in 1992. Since the operating conditions were well defined at that time, the experimental results can be used as a benchmark. It may be noted that this benchmark is one of very few high enrichment benchmarks available. In our simulations experimental conditions were thoroughly simulated: fuel elements and control rods were precisely modeled as well as entire core configuration and the vicinity of the core. ENDF/B-VI and ENDF/B-V libraries were used. Partial results of benchmark calculations are presented. Excellent agreement of core criticality, excess reactivity and control rod worths can be observed. (author)

  11. The Design of a Prompt Gamma Neutron Activation Analysis Beam for BNCT Purpose at the TRIGA Mark II Reactor in Pavia

    Energy Technology Data Exchange (ETDEWEB)

    Stella, S.; Bazani, A.; Ballarini, F.; Bortolussi, S.; Protti, N.; Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia (Italy); Istituto Nazionale di Fisica Nucleare (INFN), Section of Pavia (Italy); Bruschi, P. [Department of Nuclear and Theoretical Physics, University of Pavia (Italy)

    2011-07-01

    In preclinical and clinical Boron Neutron Capture Therapy studies the knowledge of the amount of {sup 10}B in blood and tissues is very important. The boron concentration measurements method used in Pavia (Italy) is based on the charged particles spectrometry of thin tissue cuts irradiated in the Thermal Column of the TRIGA reactor of the University. In order to perform measurements in biological liquids such as blood and urine, or in other tissue that cannot be cut in slices, a Prompt Gamma Neutron Activation Analysis (PGNAA) facility is being designed, which measures {sup 10}B concentration detecting the prompt gamma from boron nuclear capture reaction. At the TRIGA reactor in Pavia, there are four horizontal channels, potentially available for PGNAA. The choice of the suitable channel, and the design of its configuration, were achieved using the Monte Carlo neutron transport code MCNP4c2. To perform the simulations, an input code already validated, describing the reactor structure and the neutron source, was used. The calculations were implemented applying non-analog techniques for the neutron transport, that are necessary to obtain a sufficient statistic in every positions along the channel and especially at its end. The selection of the channel for PGNAA installation was carried out by comparing the simulated fluxes obtained in the different channels at the present configuration. The channel shielded by the core reflector was chosen, because the graphite lowers the fast component of the neutrons, with no need to insert additional material in the facility. The thermal flux at its end is 1.7 x 10{sup 8} n/cm{sup 2} s with thermal-to-total neutron flux ratio around 0.8. Subsequently a bismuth block for gamma radiation shielding and blocks of single crystal sapphire as filter for fast neutron component were inserted in the channel. Other components of the facility that are under study are a collimator and the beam catcher. (author)

  12. Fuel Management Strategies for a Possible Future LEU Core of a TRIGA Mark II Vienna

    Energy Technology Data Exchange (ETDEWEB)

    Khan, R.; Villa, M.; Steinhauser, G.; Boeck, H. [Vienna University of Technology-Atominstitut (Austria)

    2011-07-01

    The Vienna University of Technology/Atominstitut (VUT/ATI) operates a TRIGA Mark II research reactor. It is operated with a completely mixed core of three different types of fuel. Due to the US fuel return program, the ATI have to return its High Enriched Uranium (HEU) fuel latest by 2019. As an alternate, the Low Enrich Uranium (LEU) fuel is under consideration. The detailed results of the core conversion study are presented at the RRFM 2011 conference. This paper describes the burn up calculations of the new fuel to predict the future burn up behavior and core life time. It also develops an effective and optimized fuel management strategy for a possible future operation of the TRIGA Mark II with a LEU core. This work is performed by the combination of MCNP5 and diffusion based neutronics code TRIGLAV. (author)

  13. Temperature feedback of TRIGA MARK-II fuel

    Science.gov (United States)

    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.

  14. TRIGA Mark II Ljubljana - spent fuel transportation

    International Nuclear Information System (INIS)

    Ravnik, M.; Dimic, V.

    2008-01-01

    The most important activity in 1999 was shipment of the spent fuel elements back to the United States for final disposal. This activity started already in 1998 with some governmental support. In July 1999 all spent fuel elements (219 pieces) from the TRIGA research reactor in Ljubljana were shipped back to the United Stated by the ship from the port Koper in Slovenia. At the same time shipment of the spent fuel from the research reactor in Pitesti, Romania, and the research reactor in Rome, Italy, was conducted. During the loading the radiation exposure to the workers was rather low. The loading and shipment of the spent nuclear fuel went very smoothly and according the accepted time table. During the last two years the TRIGA research reactor in Ljubljana has been in operation about 1100 hours per year and without any undesired shut-down. (authors)

  15. Time Evolution of Selected Actinides in TRIGA MARK-II Fuel

    International Nuclear Information System (INIS)

    Usang, M.D.; Naim Shauqi Hamzah; Mohamad Hairie Rabir

    2011-01-01

    Study is made on the evolution of several actinides capable of undergoing fission or breeding available on the Malaysian Nuclear Agency (MNA) TRIGA MARK-II fuel. Population distribution of burned fuel in the MNA reactor is determined with a model developed using WIMS. This model simulates fuel conditions in the hottest position in the reactor, thus the location where most of the burn up occurs. Theoretical basis of these nuclide time evolution are explored and compared with the population obtained from our models. Good agreements are found for the theoretical time evolution and the population of Uranium-235, Uranium-236, Uranium-238 and Plutonium-239. (author)

  16. Decontamination and decommissioning project status of the TRIGA Mark II and III in Korea

    International Nuclear Information System (INIS)

    Paik, S.T.; Park, S.K.; Chung, K.W.; Chung, U.S.; Jung, K.J.

    1999-01-01

    TRIGA Mark-II, the first research reactor in Korea, has operated since 1962, and the second one, TRIGA Mark-III since 1972. Both of them had their operation phased out in 1995 due to their lives and operation of the new research reactor, HANARO (High-flux Advanced Neutron Application Reactor) at the Korea Atomic Energy Institute (KAERI) in Taejon. Decontamination and decommissioning (D and D) project of TRIGA Mark-II and Mark-III was started in January 1997 and will be completed in December 2002. The first year of the project, work was performed in preparation of the decommissioning plan, start of the environmental impact assessment and setup licensing procedure and documentation for the project with cooperation of Korea Institute of Nuclear Safety (KINS). Hyundai Engineering Company (HEC) is the main contractor to do design and licensing documentation for the D and D of both reactors. British Nuclear Fuels plc (BNFL) is the technical assisting partner of HEC. The decommissioning plan document was submitted to the Ministry of Since and Technology (MOST) for the decommissioning license in December 1998, and it expecting to be issued a license in mid 1999. The goal of this project is to release the reactor site and buildings as an unrestricted area. This paper summarizes current status and future plan for the D and D project. (author)

  17. A Case Study: Implementation of a Management System for the TRIGA Mark II Research Reactor at the Laboratory of Applied Nuclear Energy (LENA) of the University of Pavia, Italy. Annex I

    International Nuclear Information System (INIS)

    2013-01-01

    This annex provides an example for the implementation of a management system for operating organizations of research reactors, based on a case study in which the implementation of such a system has been completed. The case study relates the experience of the Applied Nuclear Energy Laboratory (hereafter referred to as LENA) of the University of Pavia, Italy. This example is used because of the recent completion of the implementation of an integrated management system, and also because of the specific characteristics of the organization (such as the limited number of staff, limited financial resources, etc.), which are often typical for organizations that operate smaller research reactors. Section I-1 gives a brief presentation of the organization, including the scope of work, the main activities performed, the organizational structure, the identification of interested parties and the applicable requirements and standards. Section I-2 describes the LENA Management System, the reasons for its implementation, the stages of its development and the processes involved. Some practical examples related to the development of the LENA Management System are discussed in Section I-3, indicating the choices made by the organization. In particular, Section I-3.12 shows the correlation between the LENA Management System processes and the processes considered in the main body of this publication.

  18. Boron Neutron Capture Therapy activity of diffused tumors at TRIGA Mark II in Pavia

    Energy Technology Data Exchange (ETDEWEB)

    Bortolussi, S.; Stella, S.; De Bari, A.; Altieri, S. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy)]|[National Institute of Nuclear Physics (INFN), Pavia (Italy); Bruschi, P.; Bakeine, J.G. [Department of Nuclear and Theoretical Physics, University of Pavia, Pavia (Italy); Clerici, A.; Ferrari, C.; Zonta, C.; Zonta, A. [Department of Surgery, University of Pavia, Pavia (Italy); Nano, R. [Department of Animal Biology, University of Pavia, Pavia (Italy)

    2008-10-29

    The Boron neutron Capture Therapy research in Pavia has a long tradition: it begun more than 20 years ago at the TRIGA Mark II reactor of the University. A technique for the treatment of the hepatic metastases was developed, consisting in explanting the liver treated with {sup 10}B, irradiating it in the thermal column of the reactor, and re-implanting the organ in the patient. In the last years, the possibility of applying BNCT to the lung tumours using epithermal collimated neutron beams and without explanting the organ, is being explored. The principal obtained results of the BNCT research will be presented, with particular emphasis on the following aspects: a) the project of a new thermal column configuration to make the thermal neutron flux more uniform inside the explanted liver, b) the Monte Carlo study by means of the MCNP code of the thermal neutron flux distribution inside a patient's thorax irradiated with epithermal neutrons, and c) the measurement of the boron concentration in tissues by (n,{alpha}) spectroscopy and neutron autoradiography. (authors)

  19. Boron Neutron Capture Therapy activity of diffused tumors at TRIGA Mark II in Pavia

    International Nuclear Information System (INIS)

    Bortolussi, S.; Stella, S.; De Bari, A.; Altieri, S.; Bruschi, P.; Bakeine, J.G.; Clerici, A.; Ferrari, C.; Zonta, C.; Zonta, A.; Nano, R.

    2008-01-01

    The Boron neutron Capture Therapy research in Pavia has a long tradition: it begun more than 20 years ago at the TRIGA Mark II reactor of the University. A technique for the treatment of the hepatic metastases was developed, consisting in explanting the liver treated with 10 B, irradiating it in the thermal column of the reactor, and re-implanting the organ in the patient. In the last years, the possibility of applying BNCT to the lung tumours using epithermal collimated neutron beams and without explanting the organ, is being explored. The principal obtained results of the BNCT research will be presented, with particular emphasis on the following aspects: a) the project of a new thermal column configuration to make the thermal neutron flux more uniform inside the explanted liver, b) the Monte Carlo study by means of the MCNP code of the thermal neutron flux distribution inside a patient's thorax irradiated with epithermal neutrons, and c) the measurement of the boron concentration in tissues by (n,α) spectroscopy and neutron autoradiography. (authors)

  20. Seed irradiation facilities at TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Najzer, M.

    1972-01-01

    Fast neutrons and gamma-rays with their high and low LET respectively are excellent complementary tools for investigation of the effect of different types of mutations. TRIGA Irradiation Facility and Thermal Column Irradiation Facility were designed and installed for the first time in the TRIGA tank and thermal column respectively. The basic idea of design was the use of depleted uranium as gamma-ray and thermal neutron shield and simultaneously as thermal to fast neutron converter. Low LET radiation, due to direct and thermal neutron capture gamma-rays, is strongly attenuated while fast neutron flux is increased. GIF is made of a cadmium tube inserted in a graphite block. It is located in the central thermal column channel. The basic idea is to convert thermal neutrons to gamma-rays by capture in the cadmium

  1. Simulation of TRIGA Mark II Benchmark Experiment using WIMSD4 and CITATION codes

    International Nuclear Information System (INIS)

    Dalle, Hugo Moura; Pereira, Claubia

    2000-01-01

    This paper presents a simulation of the TRIGA Mark II Benchmark Experiment, Part I: Steady-State Operation and is part of the calculation methodology validation developed to the neutronic calculation of the CDTN's TRIGA IPR - R1 reactor. A version of the WIMSD4, obtained in the Centro de Tecnologia Nuclear, in Cuba, was used in the cells calculation. In the core calculations was adopted the diffusion code CITATION. Was adopted a 3D representation of the core and the calculations were carried out at two energy groups. Many of the experiments were simulated, including, K eff , control rods reactivity worth, fuel elements reactivity worth distribution and the fuel temperature reactivity coefficient. The comparison of the obtained results, with the experimental results, shows differences in the range of the accuracy of the measurements, to the control rods worth and fuel temperature reactivity coefficient, or on an acceptable range, following the literature, to the K eff and fuel elements reactivity worth distribution and the fuel temperature reactivity coefficient. The comparison of the obtained results, with the experimental. results, shows differences in the range of the accuracy of the measurements, to the control rods worth and fuel temperature reactivity coefficient, or in an acceptable range, following the literature, to the K eff and fuel elements reactivity worth distribution. (author)

  2. 3-D flux distribution and criticality calculation of TRIGA Mark-II

    International Nuclear Information System (INIS)

    Can, B.

    1982-01-01

    In this work, the static calculation of the (I.T.U. TRIGA Mark-II) flux distribution has been made. The three dimensional, r-θ-z, representation of the core has been used. In this representation, for different configuration, the flux distribution has been calculated depending on two group theory. The thermal-hydraulics, the poisoning effects have been ignored. The calculations have been made by using the three dimensional and multigroup code CAN. (author)

  3. Boron Neutron Capture Therapy at the TRIGA Mark II of Pavia, Italy - The BNCT of the diffuse tumours

    Energy Technology Data Exchange (ETDEWEB)

    Altieri, S.; Bortolussi, S.; Stella, S.; Bruschi, P.; Gadan, M.A. [University of Pavia (Italy); INFN - National Institute for Nuclear Physics, of Pavia (Italy)

    2008-10-29

    The selectivity based on the B distribution rather than on the irradiation field makes Boron neutron Capture Therapy (BNCT) a valid option for the treatment of the disseminated tumours. As the range of the high LET particles is shorter than a cell diameter, the normal cells around the tumour are not damaged by the reactions occurring in the tumoral cells. PAVIA 2001: first treatment of multiple hepatic metastases from colon ca by BNCT and auto-transplantation technique: TAOrMINA project. The liver was extracted after BPA infusion, irradiated in the Thermal Column of the Pavia TRIGA Mark II reactor, and re-implanted in the patient. Two patients were treated, demonstrating the feasibility of the therapy and the efficacy in destroying the tumoral nodules sparing the healthy tissues. In the last years, the possibility of applying BNCT to the lung tumours using epithermal collimated neutron beams and without explanting the organ, is being explored. The principal obtained results of the BNCT research are presented, with particular emphasis on the following aspects: a) the project of a new thermal column configuration to make the thermal neutron flux more uniform inside the explanted liver, b) the Monte Carlo study by means of the MCNP code of the thermal neutron flux distribution inside a patient's thorax irradiated with epithermal neutrons, and c) the measurement of the boron concentration in tissues by (n,{alpha}) spectroscopy and neutron autoradiography. The dose distribution in the thorax are simulated using MCNP and the anthropomorphic model ADAM. To have a good thermal flux distribution inside the lung epithermal neutrons must be used, which thermalize crossing the first tissue layers. Thermal neutrons do not penetrate and the obtained uniformity is poor. In the future, the construction of a PGNAA facility using a horizontal channel of the TRIGA Mark II is planned. With this method the B concentration can be measured also in liquid samples (blood, urine) and

  4. Analysis of the TRIGA Mark-II benchmark IEU-COMP-THERM-003 with Monte Carlo code MVP

    International Nuclear Information System (INIS)

    Mahmood, Mohammad Sayem; Nagaya, Yasunobu; Mori, Takamasa

    2004-03-01

    The benchmark experiments of the TRIGA Mark-II reactor in the ICSBEP handbook have been analyzed with the Monte Carlo code MVP using the cross section libraries based on JENDL-3.3, JENDL-3.2 and ENDF/B-VI.8. The MCNP calculations have been also performed with the ENDF/B-VI.6 library for comparison between the MVP and MCNP results. For both cores labeled 132 and 133, which have different core configurations, the ratio of the calculated to the experimental results (C/E) for k eff obtained by the MVP code is 0.999 for JENDL-3.3, 1.003 for JENDL-3.2, and 0.998 for ENDF/B-VI.8. For the MCNP code, the C/E values are 0.998 for both Core 132 and 133. All the calculated results agree with the reference values within the experimental uncertainties. The results obtained by MVP with ENDF/B-VI.8 and MCNP with ENDF/B-VI.6 differ only by 0.02% for Core 132, and by 0.01% for Core 133. (author)

  5. The application of the k0-standardization method at the TRIGA Mark II reactor, Ljubljana, Slovenia

    International Nuclear Information System (INIS)

    Jacimovic, Radojko; Benedik, Ljudmila; Stegnar, Peter; Smodis, Borut

    2002-01-01

    The k 0 -standardization method of neutron activation analysis (k 0 -NAA) was launched in the 1970s and since then continuously developed. Nowadays, k 0 -NAA became widespread as a practical analytical tool used to analyse different sample matrices. At the Jozef Stefan Institute (IJS), the KAYZERO/SOLCOI software package has been introduced for data processing after extensive testing and comparison with other available programs. In the process of validation of the software a suite of natural matrix reference materials (RMs) were used. Five certified reference materials (CRMs) from the Institute for Reference Materials and Measurements (IRMM), two standard reference materials (SRMs) from the National Institute of Standards and Technology (NIST), three RMs from the International Atomic Energy Agency (IAEA) and one RM from IJS were analysed. Altogether, results for ten elements in inorganic matrices and twenty-one elements in organic matrices, obtained by k 0 -instrumental neutron activation analysis (k 0 -INAA), were compared to certified values. The results obtained show good agreement with certified or assigned values except for Fe and U in inorganic matrices, and Al and Cr in organic matrices. (author)

  6. Operation, maintenance, and utilization of the 250 kW TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Dimic, V.; Gabrovsek, Z.

    1972-01-01

    The operational data in the years 1970, 1971 and until June 1972 are summarized in the report. No big difference in the total operational hours between different years is observed. Thermal power generation from first criticality in 1966 until 1972 is shown. In the last two years there was in an average 60 MWh generated per month. Only minor modifications have been made in the reporting period

  7. Feasibility study of k (0)-INAA at the ITU TRIGA Mark II research reactor, Turkey

    Czech Academy of Sciences Publication Activity Database

    Esen, A. N.; Haciyakupoglu, S.; Erenturk, S.; Kubešová, Marie; Kučera, Jan

    2016-01-01

    Roč. 309, č. 1 (2016), s. 179-184 ISSN 0236-5731. [14th International Conference on Modern Trends in Activation Analysis (MTAA) / 11th International conference on Nuclear Analytical Methods in the Life Science (NAMLS). Delft, 23.08.2015-23.08.2015] R&D Projects: GA MŠk(CZ) LM2011019 Institutional support: RVO:61389005 Keywords : Kayzero for Windows * k0-INAA * neutron flux parametrs * standard reference materials Subject RIV: CB - Analytical Chemistry, Separation Impact factor: 1.282, year: 2016

  8. The Ergonomically Principle Application On The Main Control Room At Modified Research Reactor TRIGA Mark II

    International Nuclear Information System (INIS)

    Santoso, Kussigit; Itjeu K; Piping S; Sudarmin; Bambang S; Suharyo W

    2000-01-01

    The main control room analysis has been done by using the application of ergonomically principle. The analysis has been stressed on the controller position and noisiness and lightness. The instrumentation position has been analyzed by using software DAP (Display Analysis Program) and noisiness and brightness has been measured by direct measurement at definite point. From the result, it is known that the analog panel display is not good, then it is advised to rearrange the data element and the character vertically or horizontally for reducing the position character complexities. From the noisiness and brightness measurement, it is know that it still fulfills the safety standard

  9. Post-Installation evaluation of the neutron radiography facility of ITU TRIGA Mark-II Reactor

    International Nuclear Information System (INIS)

    Yavuz, H.; Durmayaz, A.

    2008-01-01

    Results of the experiments for determining the characteristics of the previously described neutron radiography facility designed and built in the Istanbul Technical University are presented. The thermal and total neutron fluxes and the gamma exposure rates have been measured inside, at the exit of the neutron beam collimator, and at its surroundings. The ratio of neutron flux to gamma exposure rate at maximum power has been determined. The results have been compared to those measured in the absence of the collimator. The neutron fluxes have been determined by using the foil activation method with gold foils enclosed in cadmium capsules. The gamma exposure rates have been measured by using Li 7 F- CTLD 700 thermoluminescent dosemeters. (authors)

  10. 41Ar-concentration measurements at the Finnish TRIGA Mark II

    International Nuclear Information System (INIS)

    Tamminen, A.

    1970-01-01

    41 Ar-concentrations in the reactor hall and in the Ar-ventilation duct of FiR-1 (IRIGA Mark II, 250 kW) have been measured during normal operation conditions. Additional measurements have been performed varying Ar-ventilation and hall ventilation flow. A γ- and background compensated thin window proportional detector and a β-Geiger detector for 41 Ar-measurements are described. The hall concentration has also been estimated from background measurements with an unshielded Ge(Li)-detector. The saturation concentration in the reactor hall with and without the hall ventilation is about 1 x 10 -7 μCi/cm 3 and 3 x 10 -7 μCi/cm 3 , respectively. (author)

  11. Safety analysis calculations for a mixed and full FLIP core in a TRIGA Mark II

    International Nuclear Information System (INIS)

    Ringle, John C.; Hornyik, K.; Robinson, A.H.; Anderson, T.V.; Johnson, A.G.

    1976-01-01

    The Oregon State TRIGA Reactor will be reloading with FLIP fuel in August 1976. As we are the first Mark II TRIGA with a circular grid pattern and graphite reflector to utilize FLIP fuel, the safety analysis calculations performed at other facilities using FLIP were only of limited use to us. A multigroup, multiregion, one-dimensional diffusion theory code was used to calculate power densities in six different operational cores - mixed to full FLIP. Pulsing characteristics were obtained from a computer code based on point kinetics, with adiabatic heating of the fuel, linear temperature dependence of the specific heat, and prompt fuel temperature feedback coefficient. The results of all pertinent calculations will be presented. (author)

  12. Radioactive waste management plan during the TRIGA Mark II and III decommissioning

    International Nuclear Information System (INIS)

    Jung, K.J.; Park, S.K.; Geong, G.H.; Lee, K.W.; Chung, U.S.; Paik, S.T.

    2001-01-01

    The decontamination and decommissioning (D and D) project of TRIGA Mark-I and Mark-II (KRR 1 and 2) was started in January 1997 and will be completed by December 2002. In the first year of the project, work was performed in preparation of the decommissioning plan, start of the environmental impact assessment and setup licensing procedure and documentation for the project with cooperation of the Korea Institute of Nuclear Safety (KINS). In the second year, Hyundai Engineering Company (HEC) with British Nuclear Fuels pie (BNFL) as technical assisting partner was designated as the contractor to do design and licensing documentation for the D and D of both reactors. After pre-design, a hazard and operability (HAZOP) study checked each step of the work. At the end of 1998, the decommissioning plan documentation including environmental impact assessment report was finished and submitted to the Ministry of Science and Technology (MOST) for licensing. It is expected to be issued by the end of September 1999. Practical work will then be started around the end of 1999. The safe treatment and management of the radioactive waste arising from the D and D activities is of utmost importance for successful completion of the practical dismantling work. This paper summarizes general aspects of radioactive waste treatment and management plan for the TRIGA Mark-I and II decommissioning work. (author)

  13. Preliminary investigations of a mixed standard-flip core for a TRIGA Mark II

    International Nuclear Information System (INIS)

    Ringle, John C.; Johnson, A.G.; Anderson, T.V.

    1974-01-01

    Several years ago it became apparent that due to our rapidly- increasing use rate, we would need a substantial amount of new fuel by late 1974 or early 1975. After investigations and discussions with GA, we decided that FLIP fuel would best meet our requirements for maximum fuel economy and high peak pulsing power. A proposal was submitted to the AEC for fuel assistance, and late in 1973 we were awarded a grant of $61,875. This will allow us to buy 3 FLIP-fueled-follower control rods, 1 instrumented FLIP fuel element, and 26 standard FLIP elements, giving us then a mixed core of approximately one-third FLIP and two-thirds standard elements. License amendments to accommodate this change are rather straightforward; modifications to the Technical Specifications will be somewhat more involved. The largest revisions which we envision are to our Safety Analysis Report. Although a few reactors have operated with a full FLIP core, and a few others have converted to mixed standard-FLIP cores, none of these has a standard Mark II core configuration. Those who have already converted to a mixed core have data and calculations which may be helpful to us, but the extent to which we can use these remains to be seen. The present status of our investigations into the analysis of a mixed standard-FLIP core will be presented. Any problems in calculational methods, finding appropriate data, modifications to Technical Specifications, etc., will be identified, and suggestions and help in these areas will be welcomed. (author)

  14. Preliminary investigations of a mixed standard-flip core for a TRIGA Mark II

    Energy Technology Data Exchange (ETDEWEB)

    Ringle, John C; Johnson, A G; Anderson, T V [Oregon State University (United States)

    1974-07-01

    Several years ago it became apparent that due to our rapidly- increasing use rate, we would need a substantial amount of new fuel by late 1974 or early 1975. After investigations and discussions with GA, we decided that FLIP fuel would best meet our requirements for maximum fuel economy and high peak pulsing power. A proposal was submitted to the AEC for fuel assistance, and late in 1973 we were awarded a grant of $61,875. This will allow us to buy 3 FLIP-fueled-follower control rods, 1 instrumented FLIP fuel element, and 26 standard FLIP elements, giving us then a mixed core of approximately one-third FLIP and two-thirds standard elements. License amendments to accommodate this change are rather straightforward; modifications to the Technical Specifications will be somewhat more involved. The largest revisions which we envision are to our Safety Analysis Report. Although a few reactors have operated with a full FLIP core, and a few others have converted to mixed standard-FLIP cores, none of these has a standard Mark II core configuration. Those who have already converted to a mixed core have data and calculations which may be helpful to us, but the extent to which we can use these remains to be seen. The present status of our investigations into the analysis of a mixed standard-FLIP core will be presented. Any problems in calculational methods, finding appropriate data, modifications to Technical Specifications, etc., will be identified, and suggestions and help in these areas will be welcomed. (author)

  15. TRIGA reactor as an experimental tool

    Energy Technology Data Exchange (ETDEWEB)

    Nahrul Khair bin Alang Mohammad Rashid (PUSPATI, Selangor (Malaysia))

    1981-01-01

    Article reviewed on the general features, operation and capabilities, and utilization of a research reactor, PUSPATI TRIGA MARK II. The paper also described the arrangements for the use of the PUSPATI reactor.

  16. Triga reactor as an experimental tool

    International Nuclear Information System (INIS)

    Nahrul Khair bin Alang Mohammad Rashid

    1981-01-01

    Article reviewed on the general features, operation and capabilities, and utilization of a research reactor, PUSPATI TRIGA MARK II. The paper also described the arrangements for the use of the PUSPATI reactor

  17. Use of the TRIGA Reactor by the Radiochemistry Group of the Atominstitute of the Austrian Universities

    International Nuclear Information System (INIS)

    Bichler, M.; Buchtela, K.; Grass, F.; Ismail, S.

    1994-01-01

    The Radiochemistry Group of the Atominstitute of the Austrian Universities uses the TRIGA Mark II Reactor mainly for neutron activation analysis. Transport of samples to and from the irradiation positions in the reactor is performed by fast pneumatic transfer systems (transfer time 20 msec and 300 msec) and slow conventional transport facilities. Gamma-spectrometric instrumentation equipped with loss free counting systems is used to handle the high count rates up to 500 000 counts/sec. During the last years neutron activation analysis was applied to investigate environmental samples (soil, dust, incineration ash), geological samples (rocks, sediments, fossils, volcanic gases), biological materials (lichens, mushrooms and other plant materials, human diet, biological reference materials), raw materials (phosphate, coal) and archaeological materials (ancient glass). Lichen analysis was used for environmental monitoring. The content of some of the trace elements can be correlated with industrial activities, like manganese content with steel industry, the occurrence of vanadium and nickel with oil firing plants and stainless steel industry, selenium is found in lichen near coal firing plants. The amount of chlorine and sodium indicates the application of salt for road treatment during winter time, aluminum, scandium and hafnium content depends on the amount of dust in the environment. A further environmental application of neutron activation analysis is the determination of trace elements in volcanic gases. The halogens, arsenic, antimony, selenium, tellurium and mercury were determined and their daily output was calculated. The distribution of trace elements in fossils of known age gives us a geochemical key to condition and development of the paleo-environment. For this purpose we determined rare earth elements in 250 million years old microfossils (conodonts). Neutron activation analysis served also for some non scientific but nevertheless useful purposes: Organic

  18. Modification of NUR II neutron beam profile of MINT TRIGA MARK II research reactor for digital neutron radiography

    International Nuclear Information System (INIS)

    Muhammad Rawi Mohamed Zin; Azali Muhammad; Abdul Aziz Mohamed; Rafhayudi Jamro; Syed Nasaruddin Syed Idris; Ng Aik Hao; Rosly Jaafar

    2006-01-01

    A cone neutron beam collimated by a 5.4 cm aperture produced in the Neutron Radiography II (NUR II) via a step divergence collimator had to be modified to fulfill 5 cm x 6 cm dimension of the scintillation screen placed in the charge couple device (ccd) camera. The required convergence neutron beam was obtained by a simple collimator-beam plug plugged in front of the NUR II beam port. The calculations involved in designing the collimator-beam plug had to take into account not only the neutron beam profiling but also the neutron and gamma shielding and are discussed in this article. (Author)

  19. Research work with TRIGA Mark II at the Nuclear Chemistry Section of the 'J. Stefan' Institute in Ljubljana

    International Nuclear Information System (INIS)

    Byrne, A.R.; Dermelj, M.; Kosta, L.; Ravkin, V.; Stegnar, P.

    1978-01-01

    The general features of our research programme using TRIGA MK II, as outlined at the last TRIGA Reactor Users Conference in Vienna, September 28-30,1976, remain the same; namely, neutron activation analysis for trace and some minor elements. The four main areas presently investigated are a) environmental studies, b) life sciences research, c) standardization and d) methodology for specific problems arising in the first three topics

  20. Component failure data base of TRIGA reactors

    International Nuclear Information System (INIS)

    Djuricic, M.

    2004-10-01

    This compilation provides failure data such as first criticality, component type description (reactor component, population, cumulative calendar time, cumulative operating time, demands, failure mode, failures, failure rate, failure probability) and specific information on each type of component of TRIGA Mark-II reactors in Austria, Bangladesh, Germany, Finland, Indonesia, Italy, Indonesia, Slovenia and Romania. (nevyjel)

  1. Small Angle Neutron Scattering instrument at Malaysian TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mohd, Shukri; Kassim, Razali; Mahmood, Zal Uyun [Malaysian Inst. for Nuclear Technology Research (MINT), Bangi, Kajang (Malaysia); Radiman, Shahidan

    1998-10-01

    The TRIGA MARK II Research reactor at the Malaysian Institute for Nuclear Research (MINT) was commissioned in July 1982. Since then various works have been performed to utilise the neutrons produced from this steady state reactor. One of the project involved the Small Angle Neutron Scattering (SANS). (author)

  2. Neutron Field Characterization of Irradiation Locations Applied to the Slovenian TRIGA Reactor

    International Nuclear Information System (INIS)

    Barbot, Loic; Domergue, Christophe; Breaud, Stephane; Destouches, Christophe; Villard, Jean-Francois; Snoj, Luka; Stancar, Ziga; Radulovic, Vladimir; Trkov, Andrej

    2013-06-01

    This work deals with several neutron flux measurement instruments and particle transport calculations combined in a method to assess the neutron field in experimental locations in nuclear reactor core or reflector. First test of this method in the TRIGA Mark II of Slovenia led to the assessment of three energy groups neutron fluxes in central irradiation locations within reactor core. (authors)

  3. Best Safety Practices for the Operation of Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Boeck, H.; Villa, M. [Atominstitute of the Austrian Universities, 1020 Vienna (Austria)

    2002-07-01

    A survey on administrative, organisational and technical aspects for the safe and efficient operation of a 250 kW TRIGA Mark II research reactor is given. The replacement of the I and C system is discussed, maintenance procedures are presented and the fuel management is described. (author)

  4. Best Safety Practices for the Operation of Research Reactors

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2002-01-01

    A survey on administrative, organisational and technical aspects for the safe and efficient operation of a 250 kW TRIGA Mark II research reactor is given. The replacement of the I and C system is discussed, maintenance procedures are presented and the fuel management is described. (author)

  5. Conceptual design of a clinical BNCT beam in an adjacent dry cell of the Jozef Stefan Institute TRIGA reactor

    NARCIS (Netherlands)

    Maucec, M

    The MCNP4B Monte Carlo transport code is used in a feasibility study of the epithermal neutron boron neutron capture therapy facility in the thermalizing column of the 250-kW TRIGA Mark II reactor at the Jozef Stefan Institute (JSI). To boost the epithermal neutron flux at the reference irradiation

  6. Conceptual design of a clinical BNCT beam in an adjacent dry cell of the Jozef Stefan Institute TRIGA reactor

    NARCIS (Netherlands)

    Maucec, M

    2000-01-01

    The MCNP4B Monte Carlo transport code is used in a feasibility study of the epithermal neutron boron neutron capture therapy facility in the thermalizing column of the 250-kW TRIGA Mark II reactor at the Jozef Stefan Institute (JSI). To boost the epithermal neutron flux at the reference irradiation

  7. Present and possible utilization of PUSPATI reactor

    International Nuclear Information System (INIS)

    Gui Ah Auu.

    1983-01-01

    The utilization of PUSPATI TRIGA Mark II Reactor (PTR) has increased reasonably well since its commissioning last year. PTR was used mainly for training of operators, neutron flux measurements and neutron activation analysis. However, the present utilization data indicates that further increase in PTR utilization to include teaching and the usage of the beam ports is desirable. Some possible areas of PTR applications in the future in relevance to our needs are also described in this paper. (author)

  8. Main safety lessons from 5-year operation of the renovated Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    Anh, T.H.; Lam, P.V.; An, T.K.; Khang, N.P.; Tan, D.Q.

    1989-01-01

    The paper presents main safety related characteristics of the Dalat Nuclear Research Reactor (DNRR), which was reconstructed in 1982 at the site of the former TRIGA Mark II, while retaining some of its structures. Experience acquired from reactor operation is analysed. The programme of investigations aimed at better ensuring nuclear safety of the reactor, together with some of its results are presented. Finally some propositions to improve the present situation are suggested. (Authors). (2 Tables, 2 fig.)

  9. Neutronic study of nuclear reactors. Complete calculation of TRIGA MARKII reactor and calculations of fuel temperature coefficients. (Qualification of WIMS code)

    International Nuclear Information System (INIS)

    Benmansour, L.

    1992-01-01

    The present work shows a group of results, obtained by a neutronic study, concerning the TRIGA MARK II reactor and LIGHT WATER reactors. These studies aim to make cell and diffusion calculations. WIMS D-4 with extended library and DIXY programs are used and tested for those purposes. We also have proceeded to a qualification of WIMS code based on the fuel temperature coefficient calculations. 33 refs.; 23 figs.; 30 tabs. (author)

  10. Research reactors in Austria - Present situation

    International Nuclear Information System (INIS)

    Boeck, H.; Musilek, A.; Villa, M.

    2005-01-01

    In the past decades Austria operated three research reactors, the 10 MW ASTRA reactor at Seibersdorf, the 250 kW TRIGA reactor at the Atominstitut and the 1 kW Argonaut reactor at the Technical University in Graz. Since the shut down of the ASTRA on July 31th, 1999 and its immediate decommissioning reactor and the shut down of the Argonaut reactor in Graz on August 31st, 2004 only one reactor remains operational for keeping nuclear competence in Austria which is the 250 kW TRIGA Mark II reactor. (author)

  11. Self Assessment for the Safety of Research Reactor in Indonesia

    International Nuclear Information System (INIS)

    Melani, Ai; Chang, Soon Heung

    2008-01-01

    At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. National Nuclear Energy Agency (BATAN) has three research reactor; which are: Reactor Triga Mark II at Bandung, Reactor Kartini at Yogyakarta and Reactor Serbaguna (Multi Purpose Reactor) at Serpong. The Code of Conduct on the Safety of Research Reactors establishes 'best practice' guidelines for the licensing, construction and operation of research reactors. In this paper the author use the requirement in code of conduct to review the safety of research reactor in Indonesia

  12. Lessons Learnt in the Development of Level 1 PUSPATI TRIGA Reactor Probability Safety Assessment: A Collaboration Project under the Norwegian Extra Budgetary Fund

    International Nuclear Information System (INIS)

    Mazleha Maskin; Tom, P.P.; Ahmad Hassan Sallehudin Mohd Sarif; Faizal Mohamed; Mohd Fazli Zakaria; Muhamad Puad Abu

    2014-01-01

    This article reports about the lessons learnt from the development of level 1 probabilistic safety assessment (PSA) project that was implemented under the IAEA mentoring program for TRIGA MARK II PUSPATI research reactor (RTP). As a project that involved more than 3 organizations, a strategic planning of the management and implementation of individual assignment is truly a hectic task. This report compiles all related activities from the forming of the Malaysian PSA team up to the final report submitted to the IAEA. (author)

  13. The Chernobyl reactor accident and its impact on Austrian agriculture

    International Nuclear Information System (INIS)

    Horak, O.

    1986-09-01

    As a consequence of the Chernobyl reactor accident the environmental radioactivity in Austria increased far above the level recorded before. Radionuclides can enter into the foodchains by the contamination of agricultural products. Determining for the contamination is the behaviour of radionuclides in plants and soils, the development of vegetative plant mass at the moment of the accident and regional differences in fallout intensity. Contamination of plants is caused mainly by cesium-137 and cesium-134. Cs is taken up easily by plant foliage. Its mobility in the plant is high, even to fruits and seeds growing after the accident. Higher contaminations are recorded generally in winter cercals, rape, and fruits, while spring cercals, sugar beets and maize are nearly free from Cs-activity. Heavy contaminations with Cs appear in grassland vegetation as a result of combined uptake via leaves, plant base, and roots. The entry of caesium into the milk is one of the most serious consequences of the reactor accident. Transfer coefficients derived from prevailing experiments can be used for estimating the activity concentration in milk. Accordingly the threshold value of 5 nCi 137 Cs per liter milk should be reached when the daily intake by feeding is about 700 nCi. During the grazing season the Cs-availability for cattle is distinctly lower. (Author)

  14. Some possibilities of utilisation of TRIGA reactors in the future

    International Nuclear Information System (INIS)

    Stegnar, Peter; Byrne, Anthony R.

    2008-01-01

    Full text. In this presentation, some possibilities for the future use of TRIGA reactors are discussed. The use and practical applications of neutron activation analysis, both in instrumental and radiochemical analysis, is presented based on the experience of the Institute's TRIGA Mark II Reactor in Ljubljana. The limited use of isotope production for medicine and industry is also discussed as well as some other potential applications, i.e. prompt gamma neutron activation analysis and an approach to BNCT (Boron Neutron Capture Therapy). The possibility of using TRIGA reactors for training in nuclear safety, radiological protection and other relevant fields of science and technology is also addressed in the presentation

  15. Influence of regulatory requirements for nuclear power plants on the backfitting of Austrian research reactors

    International Nuclear Information System (INIS)

    Boeck, H.; Hammer, J.

    1985-01-01

    In general the licensing and backfitting activities have once more demonstrated the fact that safety assessment of a research reactor is by no means just a scaled-down version of a nuclear power plant licensing procedure. Naturally the risk potential is much lower, however, the very nature of research calls for much more flexibility in operation, for temporary installations and for experimental methods which cannot be covered by detailed regulations in advance. Therefore the application of nuclear power reactor criteria to such facilities has to be considered with extreme caution. If NPP standards are applicable at all, they have to be carefully interpreted in each individual case. It is interesting to compare the original reactor safety reports with their modern versions: emphasis has shifted from reactivity accident calculations to thermal-hydraulic considerations, to better instrumentation (both in quality and quantity) and to more effort in reducing, measuring and documenting all radioactive effluents. This tendency is also reflected in most of the backfitting requirements. In summary, the result of the lengthy licensing and backfitting process is certainly a considerable improvement in performance and safety of the Austrian research reactors

  16. Activation of concrete samples from the biological shield of the ASTRA reactor

    International Nuclear Information System (INIS)

    Smecka, F.

    2006-09-01

    Drill cores from the biological shield of the ASTRA reactor in Seibersdorf were taken and milled because of the different size of the Baryt crystals in the concrete in order to get homogenous samples. The powder samples were put into bore holes of a graphite block which was placed into the thermal column of the TRIGA Mark II reactor. The block was irradiated for 10 minutes at a reactor power of 25 kW. After one hour the dose rate was examined and the samples were ready for further save handling. The gamma spectrum was measured with a Ge detector and the results were compared with simulation data. (nevyjel)

  17. Simulation development for TRIGA reactor

    International Nuclear Information System (INIS)

    Handoyo, D.

    1997-01-01

    A simulator of the dynamic of TRIGA reactor has been made. this simulator is meant to study the reactor kinetic behavior and for operator training to more assure the safety and the reliability of the real operation of TRIGA reactor. the simulator consists of PC (Personal Computer) for processing the calculation of reactivity, neutron flux, period, ect and control panel for regulating the input data such as the change of power range, control rod position as well as cooling flow rate. the result will be displayed on screen monitor of personal computer as given in the real control room of TRIGA reactor. the output of simulator will be verified by comparing with measurement result in the real TRIGA MARK II reactor of Musashi institute of technology. for the change of reactivity of 0.3, 0.5 and 0.7 the reactor power and fuel temperature between the simulator and measurements are comparable

  18. Operation experience with the TRIGA reactor Wien 2004

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2004-01-01

    The TRIGA Mark-II reactor in Vienna is now in operation for more than 42 years. The average operation time is about 230 days per year with 90 % of this time at nominal power of 250 kW. The remaining 10 % operation time is used for students' training courses at low power level. Pulse operation is rather infrequent with about 5 to 10 pulses per year. The utilization of this facility is excellent, the number of students participating in practical exercises has strongly increased, and also training courses for outside groups such as the IAEA or for the 2004 Eugene Wigner Course are using the reactor, because it is the only TRIGA reactor remaining in Austria. Therefore, there is no need for decommissioning and it is intended to operate it as long as possible into the next decade. Nevertheless, in early 2004 it was decided to prepare a report on a decommissioning procedure for a typical TRIGA Mark II reactor which lists the volumes, the activity and the weight of individual materials such as concrete, aluminium, stainless steel, graphite and others which will accumulate during this process (a summary of possible activated and contaminated materials and the activity of a single TRIGA fuel element as a function of fuel type and decay time in Bq is presented). The status of the reactor (instrumentation, fuel elements, cooling circuit, ventilation system, re-inspection and maintenance program, cost/benefit) is outlined. (nevyjel)

  19. Effective cross sections of U-235 and Au in a TRIGA-type reactor core

    International Nuclear Information System (INIS)

    Harasawa, S.; Auu, G.A.

    1992-01-01

    The dependence of effective cross sections of gold and uranium for neutron spectrum in Rikkyo University Reactor (TRIGA Mark- II, RUR) fuel cell was studied using computer calculations. The dependence of thermal neutron spectrum with temperature was also investigated. The effective cross section of gold in water of the fuel cell at 32degC was 90.3 barn and the fission cross section of U-235, 483 barn. These two values are similar to the cross sections for neutron energy of 0.034 eV. (author)

  20. Data acquisition system for the 3 MW TRIGA reactor at AERE Savar

    International Nuclear Information System (INIS)

    Abudl Ahad, A.O.M.

    1998-01-01

    A 3 MW TRIGA Mark II research reactor control console has been studied in detail and the channels have been selected for monitoring, display and record using the microcomputer. Information from these channels are fed to the computer through hardware like buffer, AD converter, multiplexer, etc. for continues display and permanent records using video monitor, printer and diskettes. Besides, the information from the console, other information like operating time, power, total burnup of fuel, operating persons, etc. are also available, with very little modifications in both hardware and software, the data logging system is now running successfully. (author)

  1. Investigation of the basic reactor physics characteristics of the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Huy, Ngo Quang [Centre for Nuclear Technique Application, Ho Chi Minh City (Viet Nam); Thong, Ha Van; Khang, Ngo Phu [Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    The Dalat nuclear research reactor was reconstructed from TRIGA MARK II reactor, built in 1963 with nominal power of 250 KW, and reached its planned nominal power of 500 kW for the first time in Feb. 1984. The Dalat reactor has some characteristics distinct from the former TRIGA reactor. Investigation of its characteristics is carried out by the determination of the reactor physics parameters. This paper represents the experimental results obtained for the effective fraction of the delayed photoneutrons, the extraneous neutron source left after the reactor is shut down, the lowest power levels of reactor critical states, the relative axial and radial distributions of thermal neutrons, the safe positive reactivity inserted into the reactor at deep subcritical state, the reactivity temperature coefficient of water, the temperature on the surface of the fuel elements, etc. (author). 10 refs., 10 figs., 2 tabs.

  2. Diagnosis of electric equipment at the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Truong Sinh

    1999-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a pool type of its kind in the world: Soviet-designed core and control system harmoniously integrated into the left-over infrastructure of the former American-made TRIGA MARK II reactor, which includes the reactor tank and shielding, graphite reflector, beam tubes and thermal column. The reactor is mainly used for radioisotope and radiopharmaceutical production, elemental analysis using neutron activation techniques, neutron beam exploitation, silicon doping, and reactor physics experimentation. For safe operation of the reactor maintenance work has been carried out for the reactor control and instrumentation, reactor cooling, ventilation, radiomonitoring, mechanical, normal electric supply systems as well as emergency electric diesel generators and the water treatment station. Technical management of the reactor includes periodical maintenance as required by technical specifications, training, re-training and control of knowledge for reactor staff. During recent years, periodic preventive maintenance (PPM) has been carried out for the electric machines of the technological systems. (author)

  3. Overview of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Nguyen Thai Sinh; Luong Ba Vien

    2016-01-01

    The present reactor called Dalat Nuclear Research Reactor (DNRR) has been reconstructed from the former TRIGA Mark II reactor which was designed by General Atomic (GA, San Diego, California, USA), started building in early 1960s, put into operation in 1963 and operated until 1968 at nominal power of 250 kW. In 1975, all fuel elements of the reactor were unloaded and shipped back to the USA. The DNRR is a 500-kW pool-type research reactor using light water as both moderator and coolant. The reactor is used as a neutron source for the purposes of: (1) radioactive isotope production; (2) neutron activation analysis; and (3) research and training

  4. Installation, performance, safety aspects and technical data of the triple axis Spectrometer at TRIGA Reactor of AERE

    International Nuclear Information System (INIS)

    Yunus, S. M.; Kamal, I.; Datta, T. K.; Zakaria, A. K. M.; Ahmed, F. U.

    2004-02-01

    The technical data of the Triple Axis Neutro Spectrometer installed at the 3 MW TRIGA Mark II research reactor has been described. These are the reference data required for the operation, maintenance and use of the spectrometer. The detail information of the installation of the spectrometer has been given. Radiation safety features of the spectrometer and around the radial piercing beam port (where the spectrometer is installed) are described elaborately. The quality test experiments and the performance of the spectrometer as found from these tests are also described

  5. Decontamination and decommissioning project status of the TRIGA mark-2±3 research reactors

    International Nuclear Information System (INIS)

    Jung, K. J.; Baek, S. T.; Jung, W. S.; Park, S. K.; Jung, K. H.

    1999-01-01

    TRIGA Mark-II, the first research reactor in Korea, has operated since 1962, and the second one, TRIGA Mark-III since 1972. Both of them had their operation phased out in 1995 due to their lives and operation of the new research reactor, HANARO at the Korea Atomic Energy Research Institute (KAERI) in Taejeon. Decontamination and decommissioning (D and D) project of the TRIGA Mark-II and Mark-III was started in January 1997 and will be completed in December 2002. In the first year of the project, work was performed in preparation of the decommissioning plan, start of the environmental impact assessment and setup licensing procedure and documentation for the project with cooperation of Korea Institute of Nuclear Safety (KINS). In 1998, Hyundai Engineering Company (HEC) is the main contractor to do design and licensing documentation for the D and D of both reactors. British Nuclear Fuels plc (BNFL) is technical assisting partner of HEC. The decommissioning plan document was submitted to the Ministry of Science and Technology (MOST) for the decommissioning license in December 1998, and it expecting to be issued a license at the end of September 1999. The goal of this project is to release the reactor site and buildings as an unrestricted area. This paper summarizes current status and future plan for the D and D project

  6. Some corrosion effects of the aluminum tank surface of Dalat research reactor

    International Nuclear Information System (INIS)

    Nguyen Mong Sinh

    1995-01-01

    The Dalat Nuclear Research Reactor was reconstructed from the TRIGA-MARK-II reactor installed in 1963 with a nominal power of 250 kW. Reconstruction and upgrading of this reactor to nominal power of 500 kW had been completed in the end of 1983. The reactor was commissioned in the beginning of March 1984. The aluminum reactor tank and some components of the former reactor are more than 30 year old. The good quality of reactor water minimized the total corrosion rate of reactor material surface. But some local corrosion had been found out at the tank bottom especially in water stagnant areas. The corrosion processes could be due to the electrochemical reactions associated with different metals and alloys in the reactor water and keeping in touch with the surface of aluminum reactor tank. (orig.)

  7. Status report of Indonesian research reactors

    International Nuclear Information System (INIS)

    Arbie, B.; Supadi, S.

    1995-01-01

    A general description of the three Indonesia research reactors, their irradiation facilities and future prospect are given. The 250 kW Triga Mark II in Bandung has been in operation since 1965 and in 1972 its designed power was increased to 1000 kW. The core grid from the previous 250 kW Triga Mark II was then used by Batan for designing and constructing the Kartini reactor in Yogyakarta. This reactor commenced its operation in 1979. Both Triga reactors have served a wide spectrum of utilization such as for manpower training in nuclear engineering, radiochemistry, isotope production, and beam research in solid state physics. The Triga reactor management in Bandung has a strong cooperation with the Bandung Institute of Technology and the one in Yogyakarta with the Gadjah Mada University which has a Nuclear Engineering Department at its Faculty of Engineering. In 1976 there emerged an idea to have a high flux reactor appropriate for Indonesia's intention to prepare an infrastructure for both nuclear energy and non-energy industry era. Such an idea was then realized with the achievement of the first criticality of the RSG-GAS reactor at the Serpong area. It is now expected that by early 1992 the reactor will reach its full 30 MW power level and by the end of 1992 the irradiation facilities be utilizable fully for future scientific and engineering work. As a part of the national LEU fuel development program a study has been underway since early 1989 to convert the RSG-GAS reactor core from using oxide fuel to using higher loading silicide fuel. (author)

  8. Modeling the PUSPATI TRIGA Reactor using MCNP code

    International Nuclear Information System (INIS)

    Mohamad Hairie Rabir; Mark Dennis Usang; Naim Syauqi Hamzah; Julia Abdul Karim; Mohd Amin Sharifuldin Salleh

    2012-01-01

    The 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency achieved initial criticality on June 28, 1982. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes. This paper describes the reactor parameters calculation for the PUSPATI TRIGA REACTOR (RTP); focusing on the application of the developed reactor 3D model for criticality calculation, analysis of power and neutron flux distribution and depletion study of TRIGA fuel. The 3D continuous energy Monte Carlo code MCNP was used to develop a versatile and accurate full model of the TRIGA reactor. The model represents in detailed all important components of the core and shielding with literally no physical approximation. (author)

  9. Isothermal temperature reactivity coefficient measurement in TRIGA reactor

    International Nuclear Information System (INIS)

    Zagar, T.; Ravnik, M.; Trkov, A.

    2002-01-01

    Direct measurement of an isothermal temperature reactivity coefficient at room temperatures in TRIGA Mark II research reactor at Jozef Stefan Institute in Ljubljana is presented. Temperature reactivity coefficient was measured in the temperature range between 15 o C and 25 o C. All reactivity measurements were performed at almost zero reactor power to reduce or completely eliminate nuclear heating. Slow and steady temperature decrease was controlled using the reactor tank cooling system. In this way the temperatures of fuel, of moderator and of coolant were kept in equilibrium throughout the measurements. It was found out that TRIGA reactor core loaded with standard fuel elements with stainless steel cladding has small positive isothermal temperature reactivity coefficient in this temperature range.(author)

  10. Summary of current research projects at the Atominstitute of the Austrian Universities

    International Nuclear Information System (INIS)

    Boeck, H.; Buchberger, T.; Buchtela, K.; Grass, F.; Hammer, J.; Kasa, T.; Schindler, P.; Weber, H.W.; Westphal, G.P.

    1986-01-01

    The 250 kW TRIGA Mark II reactor Vienna, with pulsing capability up to 250 MW is used as a university reactor for basic and applied research, education and training. The reactor is presently operated with a mixed core using 72 standard TRIGA fuel elements, 54 of them are still from first criticality (Al-clad), 9 of them were added later (SST-clad) and 9 are FLIP elements in the C ring. As experimental facilities, four beam tubes, one thermal column, one neutron radiography collimator installed in the previous thermalizing column, one slow and one fast pneumatic transfer system and five irradiation tubes are available. The experimental facilities are mainly used for students' education and training. Industrial research and routine service irradiations are only performed if a certain amount of scientific output can be expected. In many cases special experiments are designed and tested at the Atominstitute and later on transferred to more powerful neutron sources such as the ILL high flux reactor in Grenoble/France

  11. Decontamination of soil from the research reactor site

    International Nuclear Information System (INIS)

    Won, H. Z.; Kim, K. N.; Choi, W. K.; Jeong, J. H.; Oh, W. J.

    2002-01-01

    The two research reactors (TRIGA MARK II and III) in Korea are to be decommissioned in the near future. When the reactors are completely dismantled, the site may remain contaminated due to the long period of operation. We assume that the site is radioactively contaminated by Co-60. Soils gathered from the research reactor site were artificially contaminated with Co 2+ ion. The desorption characteristics of Co 2+ ion from the soil surface by citric acid solution were investigated. Decontamination performances of citric acid and EDTA on soil stored in the radioactive waste drums was examined. The feasibility test of recycling the citric acid was also performed. We concluded that the radioactive waste volume could be reduced significantly by soil washing with a citric acid solution

  12. Monte Carlo modelling of TRIGA research reactor

    Science.gov (United States)

    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.

  13. Current status of operation, utilization and refurbishment of the Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    Pham Duy Hien.

    1993-01-01

    The reconstructed nuclear research reactor at Dalat, Vietnam has been put into operation since March 1984. Up to present a cumulative operation time of 13,172 hrs at nominal power (500 kW) has been recorded. Production of radioisotopes for medical uses, element analysis by using activation techniques, as well as fundamental and applied research with filtered neutrons are the main activities of reactor utilizations. The problems facing Dalat Nuclear Research Institute are the ageing of the re-used TRIGA-MARK-II reactor components (especially the corrosion of the reactor tank), as well as the obsolescence of many equipment and components of the reactor control and instrumentation system. Refurbishment works are being in process with the technical and financial supports from the Vietnam government and the IAEA. (author). 7 refs, 2 tabs, 10 figs

  14. Basic research using the 250 KW research reactor triga in Ljubljana, Yugoslavia

    International Nuclear Information System (INIS)

    Dimic, V.

    1983-01-01

    The 25 KW Triga Mark II reactor of J. 'Stefan Institute' was commissioned on May 1966. During the last two years, it has been operated for about 4200 hr/year. According to experience gained with the reactor, most of the cost of reactor operation will be earned through isotope production for local hospitals and industries, performing low cost applied experiments and organizing training courses. The rest was provided through the Research Communities of the Republic of Slovenia. The reactor has been operated for 15 years without major problems and many basic research programmes have been performed. The research is being conducted in the following mainfields: solid state physics, neutron dosimetry, neutron radiography and autoradiography, reactor physics, examination of nuclear fuel using gamma scanning, irradiation of semiconducting materials and neutron activation analysis. (A.J)

  15. Calculation to experiment comparison of SPND signals in various nuclear reactor environments

    Energy Technology Data Exchange (ETDEWEB)

    Barbot, Loic; Radulovic, Vladimir; Fourmentel, Damien [CEA, DEN, DER, Instrumentation, Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance, (France); Snoj, Luka [Jozef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, (Slovenia); Tarchalski, Mikolaj [National Centre for Nuclear Research, ulica Andrzeja Soltana 7, 05-400 Otwock (Swierk), (Poland); Dewynter-Marty, Veronique [CEA, DEN, DANS, DRSN, SIREN, LESCI, Saclay, F-91191 Gif sur Yvette, (France); Malouch, Fadhel [CEA, DEN, DANS, DM2S, SERMA, Saclay, F-91191 Gif sur Yvette, (France)

    2015-07-01

    In the perspective of irradiation experiments in the future Jules Horowitz Reactor (JHR), the Instrumentation Sensors and Dosimetry Laboratory of CEA Cadarache (France) is developing a numerical tool for SPND design, simulation and operation. In the frame of the SPND numerical tool qualification, dedicated experiments have been performed both in the Slovenian TRIGA Mark II reactor (JSI) and very recently in the French CEA Saclay OSIRIS reactor, as well as a test of two detectors in the core of the Polish MARIA reactor (NCBJ). A full description of experimental set-ups and neutron-gamma calculations schemes are provided in the first part of the paper. Calculation to experiment comparison of the various SPNDs in the different reactors is thoroughly described and discussed in the second part. Presented comparisons show promising final results. (authors)

  16. Austrian highlights

    International Nuclear Information System (INIS)

    Jones, Simon

    2001-01-01

    An overview of recent development in the Austrian hydroelectric industry is presented, and details of the installed capacity, the Austrian government's power market reform package, and the promotion of small-scale hydroelectric power plants are given. The operation of Verbund - Austria's largest power generator and distributor - and the restructuring of the Verbund's main Austrian Hydro Power (AHP) generating group are discussed. The export of power, the joint venture of Verbund with CIR Energia in Italy to market power to commercial and industrial users, and the controversy surrounding the Freudenau run-of-the river plant which successfully tested a matrix turbine are reported

  17. The research reactor TRIGA Mainz. A neutron source for versatile applications in research and education

    International Nuclear Information System (INIS)

    Eberhardt, K.; Kronenberg, A.

    2000-01-01

    Currently, four research reactors with a thermal power ranging from 0.1 to 23 MW th are in operation in Germany and one new reactor (20 MW th ) is under construction. The TRIGA Mark II reactor at the Institut fuer Kernchemie became first critical on August 3, 1965. It can be operated in the steady state mode with a maximum power of 100 kW th and in the pulse mode with a peak power of 250 MW th . A survey of the research programmes carried out at the TRIGA Mainz is given covering a wide range of applications in basic and applied science in nuclear chemistry, nuclear- and particle physics. Furthermore, the reactor is used for neutron activation analysis and for education and training of students and technical personal. (orig.) [de

  18. Planning and implementation of Istanbul Technical University TRIGA research reactor program

    International Nuclear Information System (INIS)

    Aybers, N.; Yavuz, H.; Bayulken, A.

    1982-01-01

    The Istanbul Technical University TRIGA Research Reactor at the Institute for Nuclear Energy, which went critical on March 11, 1979 is basically a pulsing type TRIGA Mark - II reactor. Completion of the ITU-TRR contributed to broaden the role of the Institute for Nuclear Energy of the Technical University in Istanbul in the nuclear field by providing for the first time adequate on-campus experimental facilities for nuclear engineering studies to ITU students. The research program which is currently under planning at ITU-NEE encompasses: a) Neutron activation analysis studies by techniques and applications to chemistry, mining, materials research, archaeological and biomedical studies; b) applications of Radioisotopes; c) Radiography with reactor neutron beams; d) Radiation Pulsing

  19. Burnup dependent core neutronic calculations for research and training reactors via SCALE4.4

    International Nuclear Information System (INIS)

    Tombakoglu, M.; Cecen, Y.

    2001-01-01

    In this work, the full core modelling is performed to improve neutronic analyses capability for nuclear research reactors using SCALE4.4 code system. KENOV.a module of SCALE4.4 code system is utilized for full core neutronic analysis. The ORIGEN-S module is coupled with the KENOV.a module to perform burnup dependent neutronic analyses. Results of neutronic calculations for 1 st cycle of Cekmece TR-2 research reactor are presented. In particular, coupling of KENOV.a and ORIGEN-S modules of SCALE4.4 is discussed. The preliminary results of 2-D burnup dependent neutronic calculations are also given. These results are extended to burnup dependent core calculations of TRIGA Mark-II research reactors. The code system developed here is similar to the code system that couples MCNP and ORIGEN2.(author)

  20. A binary mixed integer coded genetic algorithm for multi-objective optimization of nuclear research reactor fuel reloading

    International Nuclear Information System (INIS)

    Binh, Do Quang; Huy, Ngo Quang; Hai, Nguyen Hoang

    2014-01-01

    This paper presents a new approach based on a binary mixed integer coded genetic algorithm in conjunction with the weighted sum method for multi-objective optimization of fuel loading patterns for nuclear research reactors. The proposed genetic algorithm works with two types of chromosomes: binary and integer chromosomes, and consists of two types of genetic operators: one working on binary chromosomes and the other working on integer chromosomes. The algorithm automatically searches for the most suitable weighting factors of the weighting function and the optimal fuel loading patterns in the search process. Illustrative calculations are implemented for a research reactor type TRIGA MARK II loaded with the Russian VVR-M2 fuels. Results show that the proposed genetic algorithm can successfully search for both the best weighting factors and a set of approximate optimal loading patterns that maximize the effective multiplication factor and minimize the power peaking factor while satisfying operational and safety constraints for the research reactor.

  1. A binary mixed integer coded genetic algorithm for multi-objective optimization of nuclear research reactor fuel reloading

    Energy Technology Data Exchange (ETDEWEB)

    Binh, Do Quang [University of Technical Education Ho Chi Minh City (Viet Nam); Huy, Ngo Quang [University of Industry Ho Chi Minh City (Viet Nam); Hai, Nguyen Hoang [Centre for Research and Development of Radiation Technology, Ho Chi Minh City (Viet Nam)

    2014-12-15

    This paper presents a new approach based on a binary mixed integer coded genetic algorithm in conjunction with the weighted sum method for multi-objective optimization of fuel loading patterns for nuclear research reactors. The proposed genetic algorithm works with two types of chromosomes: binary and integer chromosomes, and consists of two types of genetic operators: one working on binary chromosomes and the other working on integer chromosomes. The algorithm automatically searches for the most suitable weighting factors of the weighting function and the optimal fuel loading patterns in the search process. Illustrative calculations are implemented for a research reactor type TRIGA MARK II loaded with the Russian VVR-M2 fuels. Results show that the proposed genetic algorithm can successfully search for both the best weighting factors and a set of approximate optimal loading patterns that maximize the effective multiplication factor and minimize the power peaking factor while satisfying operational and safety constraints for the research reactor.

  2. Research reactor`s role in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Choi, C-O [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    1996-12-31

    After a TRIGA MARK-II was constructed in 1962, new research activity of a general nature, utilizing neutrons, prevailed in Korea. Radioisotopes produced from the MARK-II played a good role in the 1960`s in educating people as to what could be achieved by a neutron source. Because the research reactor had implanted neutron science in the country, another TRIGA MARK-III had to be constructed within 10 years after importing the first reactor, due to increased neutron demand from the nuclear community. With the sudden growth of nuclear power, however, the emphasis of research changed. For a while research activities were almost all oriented to nuclear power plant technology. However, the specifics of nuclear power plant technology created a need for a more highly capable research reactor like HANARO 30MWt. HANARO will perform well with irradiation testing and other nuclear programs in the future, including: production of key radioisotopes, doping of silicon by transmutation, neutron activation analysis, neutron beam experiments, cold neutron source. 3 tabs., 2 figs.

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

    Science.gov (United States)

    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. Copyright © 2012 Elsevier Ltd. All rights reserved.

  4. Fuel element burnup determination in HEU-LEU mixed TRIGA research reactor core

    International Nuclear Information System (INIS)

    Zagar, Tomaz; Ravnik, Matjaz

    2000-01-01

    This paper presents the results of a burnup calculations and burnup measurements for TRIGA FLIP HEU fuel elements and standard TRIGA LEU fuel elements used simultaneously in small TRIGA Mark II research reactor in Ljubljana, Slovenija. The fuel element burnup for approximately 15 years of operation was calculated with two different in house computer codes TRIGAP and TRIGLAV (both codes are available at OECD NEA Data Bank). The calculation is performed in one-dimensional radial geometry in TRIGAP and in two-dimensional (r,φ) geometry in TRIGLAV. Inter-comparison of results shows important influence of in-core water gaps, irradiation channels and mixed rings on burnup calculation accuracy. Burnup of 5 HEU and 27 LEU fuel elements was also measured with reactivity method. Measured and calculated burnup values are inter-compared for these elements (author)

  5. Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

    2014-01-01

    The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

  6. Investigation of fiberoptic behaviour during gamma irradiation. Part of a coordinated programme on non-destructive techniques for reactor fuel characterization

    International Nuclear Information System (INIS)

    Boeck, H.

    1981-03-01

    Radiation induced effects in glass-rods and fiberoptics have been studied to determine parameters affecting the application of these materials in endoscopes operating in severe radiation environments such as the core of a nuclear power plant or the spent fuel element storage pool. Different glass and fiber types have been investigated and various transmission properties were found. The samples were irradiated in the thermal column of the TRIGA Mark II reactor, Vienna. The radiation induced transmission loss was measured approximately 1 hour after the reactor shutdown. Saturation effects in the transmission loss were observed and changes in glass and fiber recovery vs time as a function of radiation dose and photo bleaching methods were studied. Photo bleaching was investigated with a quartz lamp, an arc lamp and an UV-laser light. (author)

  7. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Hampel, G.; Eberhardt, K.; Trautmann, N.

    2006-01-01

    The TRIGA Mark II reactor at the Institut fuer Kernchemie became first critical on August 3 rd , 1965. It can be operated in the steady state mode with a maximum power of 100 kWth and in the pulse mode with a peak power of 250 MWth. A survey of the research programmes performed at the TRIGA Mainz is given covering applications in basic research as well as applied science in nuclear chemistry and nuclear physics. Furthermore, the reactor is used for neutron activation analysis and for education and training of scientists, teachers, students and technical personal. Important projects for the future of the TRIGA Mainz are the UCN (ultra cold neutrons) experiment, fast chemical separation, medical applications and the use of the NAA as well as the use of the reactor facility for the training of students in the fields of nuclear chemistry, nuclear physics and radiation protection. Taking into account the past and future operation schedule and the typically low burn-up of TRIGA fuel elements (∝4 g U-235/a), the reactor can be operated for at least the next decade taking into account the fresh fuel elements on stock and without changing spent fuels. (orig.)

  8. Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors

    International Nuclear Information System (INIS)

    Uddin, M.N.; Sarker, M.M.; Khan, M.J.H.; Islam, S.M.A.

    2009-01-01

    The aim of this paper is to present the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through the analysis of the integral parameters of TRX and BAPL benchmark lattices of thermal reactors for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. In this process, the 69-group cross-section library for lattice code WIMS was generated using the basic evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 with the help of nuclear data processing code NJOY99.0. Integral measurements on the thermal reactor lattices TRX-1, TRX-2, BAPL-UO 2 -1, BAPL-UO 2 -2 and BAPL-UO 2 -3 served as standard benchmarks for testing nuclear data files and have also been selected for this analysis. The integral parameters of the said lattices were calculated using the lattice transport code WIMSD-5B based on the generated 69-group cross-section library. The calculated integral parameters were compared to the measured values as well as the results of Monte Carlo Code MCNP. It was found that in most cases, the values of integral parameters show a good agreement with the experiment and MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through benchmarking the integral parameters of TRX and BAPL lattices and can also be essential to implement further neutronic analysis of TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh.

  9. Status report of Indonesian research reactor

    International Nuclear Information System (INIS)

    Arbie, B.; Supadi, S.

    1992-01-01

    A general description of three Indonesian research reactor, its irradiation facilities and its future prospect are described. Since 1965 Triga Mark II 250 KW Bandung, has been in operation and in 1972 the design powers were increased to 1000 KW. Using core grid form Triga 250 KW BATAN has designed and constructed Kartini Reactor in Yogyakarta which started its operation in 1979. Both of this Triga type reactors have served a wide spectrum of utilization such as training manpower in nuclear engineering, radiochemistry, isotope production and beam research in solid state physics. Each of this reactor have strong cooperation with Bandung Institute of Technology at Bandung and Gajah Mada University at Yogyakarta which has a faculty of Nuclear Engineering. Since 1976 the idea to have high flux reactor has been foreseen appropriate to Indonesian intention to prepare infrastructure for nuclear industry for both energy and non-energy related activities. The idea come to realization with the first criticality of RSG-GAS (Multipurpose Reactor G.A. Siwabessy) in July 1987 at PUSPIPTEK Serpong area. It is expected that by early 1992 the reactor will reached its full power of 30 MW and by end 1992 its expected that irradiation facilities will be utilized in the future for nuclear scientific and engineering work. (author)

  10. Research reactor's role in Korea

    International Nuclear Information System (INIS)

    Choi, C-O.

    1995-01-01

    After a TRIGA MARK-II was constructed in 1962, new research activity of a general nature, utilizing neutrons, prevailed in Korea. Radioisotopes produced from the MARK-II played a good role in the 1960's in educating people as to what could be achieved by a neutron source. Because the research reactor had implanted neutron science in the country, another TRIGA MARK-III had to be constructed within 10 years after importing the first reactor, due to increased neutron demand from the nuclear community. With the sudden growth of nuclear power, however, the emphasis of research changed. For a while research activities were almost all oriented to nuclear power plant technology. However, the specifics of nuclear power plant technology created a need for a more highly capable research reactor like HANARO 30MWt. HANARO will perform well with irradiation testing and other nuclear programs in the future, including: production of key radioisotopes, doping of silicon by transmutation, neutron activation analysis, neutron beam experiments, cold neutron source. 3 tabs., 2 figs

  11. Related activities on management of ageing of Dalat Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lam, Pham Van [Reactor Dept., Nuclear Research Institute, Dalat (Viet Nam)

    1998-10-01

    The Dalat Nuclear Research Reactor (DNRR) is a pool type research reactor which was reconstructed in 1982 from the previous 250 kW TRIGA-MARK II reactor. The reactor core, the control and instrumentation system, the primary and secondary cooling systems as well as other associated systems were newly designed and installed. The renovated reactor reached its initial criticality in November 1983 and attained its nominal power of 500 kW in February 1984. Since then DNRR has been operated safely. Retained structures of the former reactor such as the reactor aluminum tank, the graphite reflector, the thermal column, the horizontal beam tubes and the radiation concrete shielding are 35 years old. During the recent years, in-service inspection has been carried out, the reactor control and instrumentation system were renovated due to ageing and obsolescence of its components, reactor general inspection and refurbishment were performed. Efforts are being made to cope with ageing of old reactor components to maintain safe operation of the DNRR. (author)

  12. Dose calculation in biological samples in a mixed neutron-gamma field at the TRIGA reactor of the University of Mainz

    DEFF Research Database (Denmark)

    Schmitz, T.; Blaickner, M.; Schütz, C.

    2010-01-01

    and pin-diodes. Material and methods. When L-α-alanine is irradiated with ionizing radiation, it forms a stable radical which can be detected by electron spin resonance (ESR) spectroscopy. The value of the ESR signal correlates to the amount of absorbed dose. The dose for each pellet is calculated using......To establish Boron Neutron Capture Therapy (BNCT) for non-resectable liver metastases and for in vitro experiments at the TRIGA Mark II reactor at the University of Mainz, Germany, it is necessary to have a reliable dose monitoring system. The in vitro experiments are used to determine the relative......-calculations for mixed radiation fields and the Hansen & Olsen alanine detector response model. With the acquired data about the background dose and charged particle spectrum, and with the acquired information of the neutron flux, we are capable of calculating the dose to the tissue. Conclusion. Monte Carlo simulation...

  13. Study on the decommissioning of research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Doo Hwan; Jun, Kwan Sik; Choi, Yoon Dong; Lee, Tae Yung; Kwon, Sang Woon; Lee, Jong Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-01-01

    Currently, KAERI operates TRIGA Mark-II and TRIGA Mark-III research reactors as a general purpose research and training facility. As these are, however, situated at Seoul office site of KAERI which is scheduled to be transferred to KEPCO as well as 30 MW HANARO research reactor which is expected to reach the first criticality in 1995 is under construction at head site of KAERI, decommissioning of TRIGA reactors has become an important topic. The objective of this study is to prepare and present TRIGA facility decontamination and decommissioning plan. Estimation of the radioactive inventory in TRIGA research reactor was carried out by the use of computational method. In addition, summarized in particular were the methodologies associated with decontamination, segmenting processes for activated metallic components, disposition of wastes. Particular consideration in this study was focused available technology applicable to decommissioning of TRIGA research reactor. State-of-the-art summaries of the available technology for decommissioning presented here will serve a useful document for preparations for decommissioning in the future. 6 figs, 41 tabs, 30 refs. (Author).

  14. RIA Analysis of Unprotected TRIGA Reactor

    Directory of Open Access Journals (Sweden)

    M.H. Altaf

    2017-07-01

    Full Text Available An RIA (reactivity initiated accident analysis has been carried out for the TRIGA Mark II research reactor considering both step and ramp reactivity ranges within 0.5 % dk/k (< $1 to 2.0 % dk/k (>$2. The insertion time was set at 10 s. Based on the fact that a reactor becomes unprotected if scram does not work at the event of danger, to define unprotected conditions, the time to actuate scram (trip was taken as close to total simulation time. In this long duration of scram inactivity, it is obtained from the present analysis that the reactor remained safe to up to 1.8 % dk/k ($2.57 for step reactivity and 1.99 % dk/k ($2.84 for ramp reactivity. In addition to negative temperature coefficient of reativity, probably the longer time of reactivity insertion keeps TRIGA safe even at larger magnitudes of reactivity during unprotected reactor transients. Coupled point kinetics, neutronics, and thermal hydraulics code EUREKA-2/R has been utilized for this work. It appears that EUREKA-2/RR predicts the sequence of unprotected transient scenario of TRIGA core with good approximation and the results will definitely be helpful for the reactor operators.

  15. Physical Characteristics of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Ngo Quang Huy

    1994-10-01

    The operation of the TRIGA MARK II reactor of nominal power 250 KW has been stopped as all the fuel elements have been dismounted and taken away in 1968. The reconstruction of the reactor was accomplished with Russian technological assistance after 1975. The nominal power of the reconstructed reactor is of 500 KW. The recent Dalat reactor is unique of its kind in the world: Russian-designed core combined with left-over infrastructure of the American-made TRIGA II. The reactor was loaded in November 1983. It has reached physical criticality on 1/11/1983 (without central neutron trap) and on 18/12/1983 (with central neutron trap). The power start up occurred in February 1984 and from 20/3/1984 the reactor began to be operated at the nominal power 500 KW. The selected reports included in the proceedings reflect the start up procedures and numerous results obtained in the Dalat Nuclear Research Institute and the Centre of Nuclear Techniques on the determination of different physical characteristics of the reactor. These characteristics are of the first importance for the safe operation of the Dalat reactor

  16. Fuel burnup analysis for the Moroccan TRIGA research reactor

    International Nuclear Information System (INIS)

    El Bakkari, B.; El Bardouni, T.; Nacir, B.; El Younoussi, C.; Boulaich, Y.; Boukhal, H.; Zoubair, M.

    2013-01-01

    Highlights: ► A fuel burnup analysis of the 2 MW TRIGA MARK II Moroccan research reactor was established. ► Burnup calculations were done by means of the in-house developed burnup code BUCAL1. ► BUCAL1 uses the MCNP tallies directly in the calculation of the isotopic inventories. ► The reactor life time was found to be 3360 MW h considering full power operating conditions. ► Power factors and fluxes of the in-core irradiation positions are strongly affected by burnup. -- Abstract: The fundamental advantage and main reason to use Monte Carlo methods for burnup calculations is the possibility to generate extremely accurate burnup dependent one group cross-sections and neutron fluxes for arbitrary core and fuel geometries. Yet, a set of values determined for a material at a given position and time remains accurate only in a local region, in which neutron spectrum and flux vary weakly — and only for a limited period of time, during which changes of the local isotopic composition are minor. This paper presents the approach of fuel burnup evaluation used at the Moroccan TRIGA MARK II research reactor. The approach is essentially based upon the utilization of BUCAL1, an in-house developed burnup code. BUCAL1 is a FORTRAN computer code designed to aid in analysis, prediction, and optimization of fuel burnup performance in nuclear reactors. The code was developed to incorporate the neutron absorption reaction tally information generated directly by MCNP5 code in the calculation of fissioned or neutron-transmuted isotopes for multi-fueled regions. The fuel cycle length and changes in several core parameters such as: core excess reactivity, control rods position, fluxes at the irradiation positions, axial and radial power factors and other parameters are estimated. Besides, this study gives valuable insight into the behavior of the reactor and will ensure better utilization and operation of the reactor during its life-time and it will allow the establishment of

  17. Validation study of the reactor physics lattice transport code WIMSD-5B by TRX and BAPL critical experiments of light water reactors

    International Nuclear Information System (INIS)

    Khan, M.J.H.; Alam, A.B.M.K.; Ahsan, M.H.; Mamun, K.A.A.; Islam, S.M.A.

    2015-01-01

    Highlights: • To validate the reactor physics lattice code WIMSD-5B by this analysis. • To model TRX and BAPL critical experiments using WIMSD-5B. • To compare the calculated results with experiment and MCNP results. • To rely on WIMSD-5B code for TRIGA calculations. - Abstract: The aim of this analysis is to validate the reactor physics lattice transport code WIMSD-5B by TRX (thermal reactor-one region lattice) and BAPL (Bettis Atomic Power Laboratory-one region lattice) critical experiments of light water reactors for neutronics analysis of 3 MW TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh. This analysis is achieved through the analysis of integral parameters of five light water reactor critical experiments TRX-1, TRX-2, BAPL-UO 2 -1, BAPL-UO 2 -2 and BAPL-UO 2 -3 based on evaluated nuclear data libraries JEFF-3.1 and ENDF/B-VII.1. In integral measurements, these experiments are considered as standard benchmark lattices for validating the reactor physics lattice transport code WIMSD-5B as well as evaluated nuclear data libraries. The integral parameters of the said critical experiments are calculated using the reactor physics lattice transport code WIMSD-5B. The calculated integral parameters are compared to the measured values as well as the earlier published MCNP results based on the Chinese evaluated nuclear data library CENDL-3.0 for assessment of deterministic calculation. It was found that the calculated integral parameters give mostly reasonable and globally consistent results with the experiment and the MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are well consistent with each other. Therefore, this analysis reveals the validation study of the reactor physics lattice transport code WIMSD-5B based on JEFF-3.1 and ENDF/B-VII.1 libraries and can also be essential to

  18. Present and future use of TRIGA reactors in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Menke, H.; Junker, D.; Krauss, O.

    1986-01-01

    In the Federal Republic of Germany nine research reactors are presently in operation, three of which are TRIGA reactors. These are the TRIGA Mark I reactors at Hannover and Heidelberg with a steady state power of 250 kW and the TRIGA Mark II reactor at Mainz with a steady power of 100 kW and a peak pulsing power of 250 MW. The decommissioning of a number of research reactors, including the TRIGA Mark III reactor at Neuherberg near Munich, is reason enough to think about the present and future use of our reactors. The German TRIGA reactors met a lively interest of scientists, since they went into operation. Presently they are well used especially in biomedical (Hannover, Heidelberg) and basic research (Mainz). In the course of about 20 years of operation the techniques and requirements of experiments changed and consequently the use of the reactors too. Certainly this will be so in the future. But thanks to its versatile experimental facilities, this type of reactor can meet the various experimental demands. So we are looking forward to a good utilisation of our German TRIGA reactors in future and taking into account the low costs for personal, energy and fuel, we are quite confident that they will be in operation still for many years. (author)

  19. University Reactor Sharing Program. Final report, September 30, 1992--September 29, 1994

    International Nuclear Information System (INIS)

    Wehring, B.W.

    1995-01-01

    Over the past 20 years, the number of nuclear reactors on university campuses in the US declined from more than 70 to less than 40. Contrary to this trend, The University of Texas at Austin constructed a new reactor facility at a cost of $5.8 million. The new reactor facility houses a new TRIGA Mark II reactor which replaces an in-ground TRIGA Mark I reactor located in a 50-year old building. The new reactor facility was constructed to strengthen the instruction and research opportunities in nuclear science and engineering for both undergraduate and graduate students at The University of Texas. On January 17, 1992, The University of Texas at Austin received a license for operation of the new reactor. Initial criticality was achieved on March 12, 1992, and full power operation, on March 25, 1992. The UT-TRIGA research reactor provides hands-on education, multidisciplinary research and unique service activities for academic, medical, industrial, and government groups. Support by the University Reactor Sharing Programs increases the availability of The University of Texas reactor facility for use by other educational institutions which do not have nuclear reactors

  20. Instrumentation renewal at the FIR 1 research reactor in Finland

    International Nuclear Information System (INIS)

    Bars, Bruno; Kall, Leif

    1982-01-01

    The Finnish TRIGA Mark II reactor (FIR 1 100 kW, later 250 kW steady state power and pulsing capability up to 250 MW) has been in operation for 20 years. The reactor is the only research reactor in Finland and is an important research training and service facility, which obviously will be operated for 10...20 years ahead. The mechanical parts of the reactor are in good shape. Some minor modifications have previously been made in the instrumentation. However, the original instrumentation could hardly have been used for 10...20 years ahead without extensive modifications and modernization. After a careful evaluation and planning process the whole reactor instrumentation was renewed in 1981 at a cost of about 400 000 dollar. The renewal was carried out in cooperation with the Central Research Institute for Physics (KFKI) at the Hungarian Academy of Sciences, which delivered the nuclear part of the instrumentation and with the Finnish company Valmet Oy Instrument Works, which delivered the conventional instrumentation, including the automatic power control system and the control console. The instrumentation, which is located in-a new isolated control room is based on modern industrial standard modular units with standardized signal ranges, electronic testing possibilities, galvanically isolated outputs etc. The instrument renewal project was brought successfully to completion in November 1981 after only about 10 working days of shut down time. The reactor is now in routine operation and the experiences gained from the new instrumentation are excellent. (author)

  1. Performance Monitoring for Nuclear Safety Related Instrumentation at PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

    2015-01-01

    The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on performance monitoring for nuclear safety related instrumentation in TRIGA PUSPATI Reactor (RTP) of based on various parameter of reactor safety instrument channel such as log power, linear power, Fuel temperature, coolant temperature will take into consideration. Methodology of performance on estimation and monitoring is to evaluate and analysis of reactor parameters which is important of reactor safety and control. And also to estimate power measurement, differential of log and linear power and fuel temperature during reactor start-up, operation and shutdown .This study also focus on neutron power fluctuation from fission chamber during reactor start-up and operation. This work will present result of performance monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that performance of nuclear safety related instrumentation will improved the reactor control and safety parameter during reactor start-up, operation and shutdown. (author)

  2. Nuclear Education and Training Courses as a Commercial Product of a Low Power Research Reactor

    International Nuclear Information System (INIS)

    Böck, H.; Villa, M.; Steinhauser, G.

    2013-01-01

    The Vienna University of Technology (VUT) operates a 250 kW TRIGA Mark II research reactor at the Atominstitut (ATI) since March 1962. This reactor is uniquely devoted to nuclear education and training with the aim to offer an instrument to perform academic research and training. During the past decade a number of requests to the Atominstitut asked for the possibility to offer this reactor for external training courses. Over the years, such courses have been developed as regular courses for students during their academic curricula at the VUT/ATI. The courses cover such subjects as “Reactor physics and kinetics”, and “Reactor instrumentation and control”, in total about 20 practical exercises. Textbooks have been developed in English language for both courses. Target groups for commercial courses are other universities without an access to research reactors (i.e., the Technical University of Bratislava, Slovak Republic, or the University of Manchester, UK), international organisations (i.e., IAEA Dept of Safeguards, training section), research centres (ie. Mol, Belgium) for retraining of their reactor staff or nuclear power plants for staff retraining. These courses have been very successful during the past five years in such a manner that the Atominstitut has now to decline new course applications as the reactor is also used for Masters thesis and PhD work which requires full power operation while courses require low power operation. The paper describes typical training programs, target groups and possible transfers of these courses to other reactors. (author)

  3. Optimum burnup of BAEC TRIGA research reactor

    International Nuclear Information System (INIS)

    Lyric, Zoairia Idris; Mahmood, Mohammad Sayem; Motalab, Mohammad Abdul; Khan, Jahirul Haque

    2013-01-01

    Highlights: ► Optimum loading scheme for BAEC TRIGA core is out-to-in loading with 10 fuels/cycle starting with 5 for the first reload. ► The discharge burnup ranges from 17% to 24% of U235 per fuel element for full power (3 MW) operation. ► Optimum extension of operating core life is 100 MWD per reload cycle. - Abstract: The TRIGA Mark II research reactor of BAEC (Bangladesh Atomic Energy Commission) has been operating since 1986 without any reshuffling or reloading yet. Optimum fuel burnup strategy has been investigated for the present BAEC TRIGA core, where three out-to-in loading schemes have been inspected in terms of core life extension, burnup economy and safety. In considering different schemes of fuel loading, optimization has been searched by only varying the number of fuels discharged and loaded. A cost function has been defined and evaluated based on the calculated core life and fuel load and discharge. The optimum loading scheme has been identified for the TRIGA core, the outside-to-inside fuel loading with ten fuels for each cycle starting with five fuels for the first reload. The discharge burnup has been found ranging from 17% to 24% of U235 per fuel element and optimum extension of core operating life is 100 MWD for each loading cycle. This study will contribute to the in-core fuel management of TRIGA reactor

  4. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    International Nuclear Information System (INIS)

    Muswema, J.L.; Ekoko, G.B.; Lukanda, V.M.; Lobo, J.K.-K.; Darko, E.O.; Boafo, E.K.

    2015-01-01

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  5. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    Energy Technology Data Exchange (ETDEWEB)

    Muswema, J.L., E-mail: jeremie.muswem@unikin.ac.cd [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Ekoko, G.B. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Lukanda, V.M. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Democratic Republic of the Congo' s General Atomic Energy Commission, P.O. Box AE1 (Congo, The Democratic Republic of the); Lobo, J.K.-K. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Darko, E.O. [Radiation Protection Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra (Ghana); Boafo, E.K. [University of Ontario Institute of Technology, 2000 Simcoe St. North, Oshawa, ONL1 H7K4 (Canada)

    2015-01-15

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  6. Current status of operation and utilization of the Dalat research reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Le Van So

    2004-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor using the Soviet WWR-SM fuel assembly with 36% enrichment of U-235. It was upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analyses and research purposes. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for physics experiments and training purpose. From the first start-up to the end of December 2002, it totaled about 24,700 hrs of operation and the total energy released was 490 MWd. After 10 years of operation with the core of 89-fuel assembly configuration, in April 1994, the first refueling work was done and the 100-fuel assembly configuration was set-up. The second fuel reloading was executed in March 2002. At present time, the working configuration of the reactor core consists of 104 fuel assemblies. This fuel reloading will ensure efficient exploitation of the reactor for about 3 years with 1200-1300 hrs per year at nominal power. The current status of operation and utilization and some activities related to the reactor core management of the DNRR are presented and discussed in this paper. (author)

  7. On Austrian regional economics

    NARCIS (Netherlands)

    Heijman, W.J.M.; Leen, A.R.

    2004-01-01

    The aim of this research note is two-fold, firstly, to clarify the growing interaction between regional science and Austrian economics and their awareness of each other. We elucidate the Austrian methodology, called praxeology, which is especially misunderstood in regional science. Secondly, we

  8. Calculation of Kinetic Parameters of TRIGA Reactor

    International Nuclear Information System (INIS)

    Snoj, Luka; Kavcic, Andrej; Zerovnik, Gasper; Ravnik, Matjaz

    2008-01-01

    Modern Monte Carlo transport codes in combination of fast computer clusters enable very accurate calculations of the most important reactor kinetic parameters. Such are the effective delayed neutron fraction, β eff , and mean neutron generation time, Λ. We calculated the β eff and Λ for various realistic and hypothetical annular TRIGA Mark II cores with different types and amount of fuel. It can be observed that the effective delayed neutron fraction strongly depends on the number of fuel elements in the core or on the core size. E.g., for 12 wt. % uranium standard fuel with 20 % enrichment, β eff varies from 0.0080 for a small core (43 fuel rods) to 0.0075 for a full core (90 fuel rods). It is interesting to note that calculated value of β eff strongly depends also on the delayed neutron nuclear data set used in calculations. The prompt neutron life-time mainly depends on the amount (due to either content or enrichment) of 235 U in the fuel as it is approximately inversely proportional to the average absorption cross-section of the fuel. E.g., it varies from 28 μs for 30 wt. % uranium content fuelled core to 48 μs for 8.5 wt. % uranium content LEU fuelled core. The results are especially important for pulse mode operation and analysis of the pulses. (authors)

  9. Research work at the TRIGA Mainz reactor

    International Nuclear Information System (INIS)

    Trautmann, Norbert

    1976-01-01

    In the last two years the research activities at the TRIGA Mark II reactor in Mainz have mainly been concentrated on the investigation of short- lived nuclides of medium mass number produced by thermal-neutron induced fission of 235 U and other fissile materials. For the identification of these nuclides and for detailed studies of their properties rapid chemical separation procedures in combination with high-resolution gamma-ray and neutron spectroscopy as well as mass-separated samples have been used. Fast, discontinuous separation techniques are illustrated by a procedure for technetium. Continuous separation methods from aqueous solutions and in the gas phase, accomplished by combining a gas jet recoil transport system with an on-line operating solvent extraction technique and a thermo- chromatographic method, are presented. The application of such procedures to decay scheme and delayed neutron studies is demonstrated by a few examples. The experimental set-up and the method for nuclear spin - and magnetic moment measurements on alkali isotopes far from the region of beta-stability applying the nuclear radiation detected optical pumping technique to mass- separated samples of neutron-rich alkali nuclides are briefly described. (author)

  10. An automatic device for sample insertion and extraction to/from reactor irradiation facilities

    International Nuclear Information System (INIS)

    Alloni, L.; Venturelli, A.; Meloni, S.

    1990-01-01

    At the previous European Triga Users Conference in Vienna,a paper was given describing a new handling tool for irradiated samples at the L.E.N.A plant. This tool was the first part of an automatic device for the management of samples to be irradiated in the TRIGA MARK ii reactor and successively extracted and stored. So far sample insertion and extraction to/from irradiation facilities available on reactor top (central thimble,rotatory specimen rack and channel f),has been carried out manually by reactor and health-physics operators using the ''traditional'' fishing pole provided by General Atomic, thus exposing reactor personnel to ''unjustified'' radiation doses. The present paper describes the design and the operation of a new device, a ''robot''type machine,which, remotely operated, takes care of sample insertion into the different irradiation facilities,sample extraction after irradiation and connection to the storage pits already described. The extraction of irradiated sample does not require the presence of reactor personnel on the reactor top and,therefore,radiation doses are strongly reduced. All work from design to construction has been carried out by the personnel of the electronic group of the L.E.N.A plant. (orig.)

  11. Current status of operation and utilization of the Dalat Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien

    2006-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool-type reactor using the Soviet VVR-M2 fuel assembly with 36% enrichment of U-235. It was renovated and upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analysis, scientific research and training. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for reactor physics and thermal hydraulics experiments. From the first start-up to the end of December 2003, it totaled about 26,000 hrs of operation and the total energy released was about 515 MWd. After 10 years of operation with the core of 89-fuel assembly configuration, in April 1994, the first refueling work was done and the 100-fuel assembly configuration was set-up. The second fuel reloading was executed in March 2002. At present time, the working configuration of the reactor core consists of 104 fuel assemblies. The next fuel reloading has been planned at the end of 2004. The current status of operation and utilization of the DNRR is presented and discussed in this paper. (author)

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

    International Nuclear Information System (INIS)

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

    1992-01-01

    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)

  13. Operator reliability study for Probabilistic Safety Analysis of an operating research reactor

    International Nuclear Information System (INIS)

    Mohamed, F.; Hassan, A.; Yahaya, R.; Rahman, I.; Maskin, M.; Praktom, P.; Charlie, F.

    2015-01-01

    Highlights: • Human Reliability Analysis (HRA) for Level 1 Probabilistic Safety Analysis (PSA) is performed on research nuclear reactor. • Implemented qualitative HRA framework is addressed. • Human Failure Events of significant impact to the reactor safety are derived. - Abstract: A Level 1 Probabilistic Safety Analysis (PSA) for the TRIGA Mark II research reactor of Malaysian Nuclear Agency has been developed to evaluate the potential risk in its operation. In conjunction to this PSA development, Human Reliability Analysis (HRA) is performed in order to determine human contribution to the risk. The aim of this study is to qualitatively analyze human actions (HAs) involved in the operation of this reactor according to the qualitative part of the HRA framework for PSA which is namely the identification, qualitative screening and modeling of HAs. By performing this framework, Human Failure Events (HFEs) of significant impact to the reactor safety are systematically analyzed and incorporated into the PSA structure. A part of the findings in this study will become the input for the subsequent quantitative part of the HRA framework, i.e. the Human Error Probability (HEP) quantification

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

    International Nuclear Information System (INIS)

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

    2015-01-01

    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. - Highlights: • Neutron flux redistribution due to control rod movement in JSI TRIGA has been studied. • Detector response sensitivity to the control rod position has been minimized. • Optimal radial and axial detector positions have been determined

  15. Results of Operation and Utilization of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Luong Ba Vien; Le Vinh Vinh; Duong Van Dong; Nguyen Xuan Hai; Pham Ngoc Son; Cao Dong Vu

    2014-01-01

    The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kW was reconstructed and upgraded from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The renovated reactor was put into operation on 20 March 1984. It was designed for the purposes of radioisotope production (RI), neutron activation analysis (NAA), basic and applied researches, and nuclear education and training. During the last 30 years of operation, the DNRR was efficiently utilized for producing many kinds of radioisotopes and radiopharmaceuticals used in nuclear medicine centers and other users in industry, agriculture, hydrology and scientific research; developing a combination of nuclear analysis techniques (INAA, RNAA, PGNAA) and physic-chemical methods for quantitative analysis of about 70 elements and constituents in various samples; carrying out experiments on the reactor horizontal beam tubes for nuclear data measurement, neutron radiography and nuclear structure study; and establishing nuclear training and education programs for human resource development. This paper presents the results of operation and utilization of the DNRR. In addition, some main reactor renovation projects carried out during the last 10 years are also mentioned in the paper. (author)

  16. Status of Dalat research reactor and progress of new reactor plan in Vietnam

    International Nuclear Information System (INIS)

    Dien, Nguyen Nhi; Vien, Luong Ba

    2005-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500-kW pool-type reactor loaded with the Soviet WWR-M2 Fuel Assemblies (FA), moderated and cooled by light water. The reactor was reconstructed from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The first criticality of the renovated reactor was achieved on 1 st November 1983, and then on 20 March 1984 the reactor was officially inaugurated and its activities restarted. During the last twenty years, the DNRR has played an important role as a large national research facility to implement researches and applications, and its utilization has been broadened in various fields of human life. However, due to the limitation of the neutron flux and power level, the out-of date design of the experimental facilities and the ageing of the reactor facilities, it cannot meet the increasing user's demands even in the existing utilization areas. In addition, the utilization demands of the Research Reactor (RR) will be increased along with the development of the nation's economy growth. In this aspect, it is necessary to have in Vietnam a new high performance multipurpose RR with a sufficient neutron flux and power level. According to the last draft of a national strategy for atomic energy development submitted to the Government for consideration and approval, it is expected that a new high power RR would be put into operation before 2020. The operation and utilization status of the DNRR is presented and some preliminary results of the national research project on new reactor plan for Vietnam are discussed in this paper

  17. Physical Characteristics of the Dalat Nuclear Research Reactor; Cac dac trung vat ly lo cua lo phan ung hat nhan Da Lat

    Energy Technology Data Exchange (ETDEWEB)

    Huy, Ngo Quang [ed.; Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    The operation of the TRIGA MARK II reactor of nominal power 250 KW has been stopped as all the fuel elements have been dismounted and taken away in 1968. The reconstruction of the reactor was accomplished with Russian technological assistance after 1975. The nominal power of the reconstructed reactor is of 500 KW. The recent Dalat reactor is unique of its kind in the world: Russian-designed core combined with left-over infrastructure of the American-made TRIGA II. The reactor was loaded in November 1983. It has reached physical criticality on 1/11/1983 (without central neutron trap) and on 18/12/1983 (with central neutron trap). The power start up occurred in February 1984 and from 20/3/1984 the reactor began to be operated at the nominal power 500 KW. The selected reports included in the proceedings reflect the start up procedures and numerous results obtained in the Dalat Nuclear Research Institute and the Centre of Nuclear Techniques on the determination of different physical characteristics of the reactor. These characteristics are of the first importance for the safe operation of the Dalat reactor.

  18. Neutron flux parameters for k{sub 0}-NAA method at the Malaysian nuclear agency research reactor after core reconfiguration

    Energy Technology Data Exchange (ETDEWEB)

    Yavar, A.R. [School of Applied Physics, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia); Sarmani, S. [School of Chemical Sciences and Food Technology, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia); Wood, A.K. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, Kajang, Selangor 43000 (Malaysia); Fadzil, S.M. [School of Applied Physics, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia); Masood, Z. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, Kajang, Selangor 43000 (Malaysia); Khoo, K.S., E-mail: khoo@ukm.m [School of Applied Physics, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia)

    2011-02-15

    The Malaysian Nuclear Agency (MNA) research reactor, commissioned in 1982, is a TRIGA Mark II swimming pool type reactor. When the core configuration changed in June 2009, it became essential to re-determine such neutron flux parameters as thermal to epithermal neutron flux ratio (f), epithermal neutron flux shape factor ({alpha}), thermal neutron flux ({phi}{sub th}) and epithermal neutron flux ({phi}{sub epi}) in the irradiation positions of MNA research reactor in order to guarantee accuracy in the application of k{sub 0}-neutron activation analysis (k{sub 0}-NAA).The f and {alpha} were determined using the bare bi-isotopic monitor and bare triple monitor methods, respectively; Au and Zr monitors were utilized in present study. The results for four irradiation positions are presented and discussed in the present work. The calculated values of f and {alpha} ranged from 33.49 to 47.33 and -0.07 to -0.14, respectively. The {phi}{sub th} and the {phi}{sub epi} were measured as 2.03 x 10{sup 12} (cm{sup -2} s{sup -1}) and 6.05 x 10{sup 10} (cm{sup -2} s{sup -1}) respectively. These results were compared to those of previous studies at this reactor as well as to those of reactors in other countries. The results indicate a good conformity with other findings.

  19. Publications of the Austrian Research Centre Seibersdorf 1976-1985

    International Nuclear Information System (INIS)

    Ranz, F.; Nevyjel, A.

    1989-02-01

    About 3000 publications, written by staff members of the Austrian Research Centre Seibersdorf (OEFZS) within the period 1976-1985 are cited. The bibliography includes citations of journal articles, proceedings, books, technical reports as well as dissertations and diploma works, carried out in Seibersdorf by students of Austrian universities. It covers the subject areas of chemistry, physics, biology, radiation protection, reactor safety, isotope applications, materials technology, environmental research, mathematics and information, electronics and agriculture. 10 refs. (Author)

  20. Medical and radiobiological applications at the research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Hampel, G.; Grunewald, C.; Kratz, J.-V.; Schmitz, T.; Schutz, C.; Werner, S.; Appelman, K.; Moss, R.; Blaickner, M.; Nawroth, T.; Otto, G.; Schmidberger, H.

    2010-01-01

    At the University of Mainz, Germany, a boron neutron capture therapy (BNCT) project has been started with the aim to expand and advance the research on the basis of the TAOrMINA protocol for the BNCT treatment of liver metastases of colorectal cancer. Irradiations take place at the TRIGA Mark II reactor. Biological and clinical research and surgery take place at the University and its hospital of Mainz. Both are situated in close vicinity to each other, which is an ideal situation for BNCT treatment, as similarly performed in Pavia, in 2001 and 2003. The application of BNCT to auto-transplanted organs requires development in the methodology, as well as regard to the irradiation facility and is part of the complex, interdisciplinary treatment process. The additional high surgical risk of auto-transplantation is only justified when a therapeutic benefit can be achieved. A BNCT protocol including explantation and conservation of the organ, neutron irradiation and re-implantation is logistically a very challenging task. Within the last years, research on all scientific, clinical and logistical aspects for the therapy has been performed. This includes work on computational modelling for the irradiation facility, tissue and blood analysis, radiation biology, dosimetry and surgery. Most recently, a clinical study on boron uptake in both healthy and tumour tissue of the liver and issues regarding dosimetry has been started, as well as a series of cell-biology experiments to obtain concrete results on the relative biological effectiveness (RBE) of ionizing radiation in liver tissue. (author)

  1. A neutron tomography facility at a low power research reactor

    CERN Document Server

    Körner, S; Von Tobel, P; Rauch, H

    2001-01-01

    Neutron radiography (NR) provides a very efficient tool in the field of non-destructive testing as well as for many applications in fundamental research. A neutron beam penetrating a specimen is attenuated by the sample material and detected by a two-dimensional (2D) imaging device. The image contains information about materials and structure inside the sample because neutrons are attenuated according to the basic law of radiation attenuation. Contrary to X-rays, neutrons can be attenuated by some light materials, as for example, hydrogen and boron, but penetrate many heavy materials. Therefore, NR can yield important information not obtainable by more traditional methods. Nevertheless, there are many aspects of structure, both quantitative and qualitative, that are not accessible from 2D transmission images. Hence, there is an interest in three-dimensional neutron imaging. At the 250 kW TRIGA Mark II reactor of the Atominstitut in Austria a neutron tomography facility has been installed. The neutron flux at ...

  2. Reactor controller design using genetic algorithms with simulated annealing

    International Nuclear Information System (INIS)

    Erkan, K.; Buetuen, E.

    2000-01-01

    This chapter presents a digital control system for ITU TRIGA Mark-II reactor using genetic algorithms with simulated annealing. The basic principles of genetic algorithms for problem solving are inspired by the mechanism of natural selection. Natural selection is a biological process in which stronger individuals are likely to be winners in a competing environment. Genetic algorithms use a direct analogy of natural evolution. Genetic algorithms are global search techniques for optimisation but they are poor at hill-climbing. Simulated annealing has the ability of probabilistic hill-climbing. Thus, the two techniques are combined here to get a fine-tuned algorithm that yields a faster convergence and a more accurate search by introducing a new mutation operator like simulated annealing or an adaptive cooling schedule. In control system design, there are currently no systematic approaches to choose the controller parameters to obtain the desired performance. The controller parameters are usually determined by test and error with simulation and experimental analysis. Genetic algorithm is used automatically and efficiently searching for a set of controller parameters for better performance. (orig.)

  3. A CAMAC based real-time noise analysis system for nuclear reactors

    International Nuclear Information System (INIS)

    Ciftcioglu, O.

    1987-01-01

    A CAMAC based real-time noise analysis system was designed for the TRIGA MARK II nuclear reactor at the Institute for Nuclear Energy, Istanbul. The input analog signals obtained from the radiation detectors are introduced to the system through CAMAC interface. The signals coverted into digital form are processed by a PDP-11 computer. The fast data processing based on auto/cross power spectral density computations is carried out by means of assembly written FFT algorithms in real-time and the spectra obtained are displayed on a CAMAC driven display system as an additional monitoring device. The system has the advantage of being software programmable and controlled by a CAMAC system so that it is operated under porgram control for reactor surveillance, anomaly detection and diagnosis. The system can also be used for the identification of nonstationary operational characteristics of the reactor in long term by comparing the noise power spectra with the corresponding reference noise patterns prepared in advance. (orig.)

  4. Maintenance of nuclear knowledge in an antinuclear environment

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2008-01-01

    In this work authors present the maintenance of nuclear knowledge in an antinuclear environment in Austria. Participation of the TRIGA Mark II research reactor in the Atominstitut in different courses, in research projects and education is presented.

  5. Validation study of SRAC2006 code system based on evaluated nuclear data libraries for TRIGA calculations by benchmarking integral parameters of TRX and BAPL lattices of thermal reactors

    International Nuclear Information System (INIS)

    Khan, M.J.H.; Sarker, M.M.; Islam, S.M.A.

    2013-01-01

    Highlights: ► To validate the SRAC2006 code system for TRIGA neutronics calculations. ► TRX and BAPL lattices are treated as standard benchmarks for this purpose. ► To compare the calculated results with experiment as well as MCNP values in this study. ► The study demonstrates a good agreement with the experiment and the MCNP results. ► Thus, this analysis reflects the validation study of the SRAC2006 code system. - Abstract: The goal of this study is to present the validation study of the SRAC2006 code system based on evaluated nuclear data libraries ENDF/B-VII.0 and JENDL-3.3 for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. This study is achieved through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors. In integral measurements, the thermal reactor lattices TRX-1, TRX-2, BAPL-UO 2 -1, BAPL-UO 2 -2 and BAPL-UO 2 -3 are treated as standard benchmarks for validating/testing the SRAC2006 code system as well as nuclear data libraries. The integral parameters of the said lattices are calculated using the collision probability transport code PIJ of the SRAC2006 code system at room temperature 20 °C based on the above libraries. The calculated integral parameters are compared to the measured values as well as the MCNP values based on the Chinese evaluated nuclear data library CENDL-3.0. It was found that in most cases, the values of integral parameters demonstrate a good agreement with the experiment and the MCNP results. In addition, the group constants in SRAC format for TRX and BAPL lattices in fast and thermal energy range respectively are compared between the above libraries and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation study of the SRAC2006 code system based on evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 and can also be essential to implement further neutronics calculations

  6. Computational analysis of the dose rates at JSI TRIGA reactor irradiation facilities.

    Science.gov (United States)

    Ambrožič, K; Žerovnik, G; Snoj, L

    2017-12-01

    The JSI TRIGA Mark II, IJS research reactor is equipped with numerous irradiation positions, where samples can be irradiated by neutrons and γ-rays. Irradiation position selection is based on its properties, such as physical size and accessibility, as well as neutron and γ-ray spectra, flux and dose intensities. This paper presents an overview on the neutron and γ-ray fluxes, spectra and dose intensities calculations using Monte Carlo MCNP software and ENDF/B-VII.0 nuclear data libraries. The dose-rates are presented in terms of ambient dose equivalents, air kerma, and silicon dose equivalent. At full reactor power the neutron ambient dose equivalent ranges from 5.5×10 3 Svh -1 to 6×10 6 Svh -1 , silicon dose equivalent from 6×10 2 Gy/h si to 3×10 5 Gy/h si , and neutron air kerma from 4.3×10 3 Gyh -1 to 2×10 5 Gyh -1 . Ratio of fast (1MeVreactor power from 3.4×10 3 Svh -1 to 3.6×10 5 Svh -1 and γ air kerma range 3.1×10 3 Gyh -1 to 2.9×10 5 Gyh -1 . Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. Current status and ageing management of the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen Nhi Dien [Nuclear Research Institute, Dalat (Viet Nam)

    2000-10-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor loaded with the Soviet WWR-M2 fuel elements, moderated and cooled by light water. It was reconstructed and upgraded from the former 250 kW TRIGA Mark-II reactor built in 1963. The first criticality of the renovated reactor was in November 1983 and it has been put in regular operation at nominal power since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs every 4 weeks, for radioisotope production, neutron activation analyses and other research purposes. The remaining time is devoted to maintenance work and to short runs for reactor physics studies as well. From its first start-up to the end of 1998, it totaled about 20,000 hrs of operation at nominal power. After ten years of operation, reactor general inspection and refurbishment were implemented in the 1992-1996 period. In April 1994, refueling work was executed with adding of 11 fresh fuel elements to the reactor core. At present, the reactor has been working with 100-fuel element configuration. Corrosion study has been implemented by visual inspection of the reactor pool tank and some other inside components which remain unchanged from the previous TRIGA reactor. The inspections were carried out with the assistance of some experts from other countries. Some visual inspection results have been obtained and the nature of the electrochemical corrosion and related aspects were little by little identified. In this paper, the operation status of the Dalat reactor is presented, and some activities related to the ageing management of the reactor pool tank and its inside components are also discussed. (author)

  8. Current status and ageing management of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien

    2000-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor loaded with the Soviet WWR-M2 fuel elements, moderated and cooled by light water. It was reconstructed and upgraded from the former 250 kW TRIGA Mark-II reactor built in 1963. The first criticality of the renovated reactor was in November 1983 and it has been put in regular operation at nominal power since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs every 4 weeks, for radioisotope production, neutron activation analyses and other research purposes. The remaining time is devoted to maintenance work and to short runs for reactor physics studies as well. From its first start-up to the end of 1998, it totaled about 20,000 hrs of operation at nominal power. After ten years of operation, reactor general inspection and refurbishment were implemented in the 1992-1996 period. In April 1994, refueling work was executed with adding of 11 fresh fuel elements to the reactor core. At present, the reactor has been working with 100-fuel element configuration. Corrosion study has been implemented by visual inspection of the reactor pool tank and some other inside components which remain unchanged from the previous TRIGA reactor. The inspections were carried out with the assistance of some experts from other countries. Some visual inspection results have been obtained and the nature of the electrochemical corrosion and related aspects were little by little identified. In this paper, the operation status of the Dalat reactor is presented, and some activities related to the ageing management of the reactor pool tank and its inside components are also discussed. (author)

  9. Technology Transfer Programme In Reactor Digital Instrumentation And Control System (REDICS) Project: Knowledge, Experiences And Future Expectations

    International Nuclear Information System (INIS)

    Nurfarhana Ayuni Joha; Mohamad Puad Abu; Izhar Abu Hussin; Ridzuan Abdul Mutalib; Zareen Khan Abdul Jalil Khan; Mohd Khairulezwan Abdul Manan; Mohd Sabri Minhat; Mohd Idris Taib

    2013-01-01

    The PUSPATI TRIGA MARK II research reactor in Malaysia was commissioned in 1982. After 31 years of operation, Nuclear Malaysia is taking an approach for a better research and development in nuclear radiations as well as the technical services that provided. Reactor TRIGA PUSPATI (RTP) is currently upgrading its control console from analogue to digital system. The Reactor Digital Instrumentation and Control System (ReDICS) project is done on cooperation with Korea Atomic Energy Research Institute (KAERI), Korea including the technical part from the design stage until commissioning as well as the Technology Transfer Program (TTP). TTP in this ReDICS project is a part of Human Resource and System Development Program. It was carried out from the design stage until the commissioning of the system. It covers all subjects related to the design on the digital system and the requirements for the operation of RTP. The objective of this paper is to share the knowledge and experiences gained through this ReDICS project. This paper will also discuss the future expectations from this ReDICS project for Nuclear Malaysia and its personnel, as well as to the country. (author)

  10. Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia

    Science.gov (United States)

    Bortolussi, S.; Protti, N.; Ferrari, M.; Postuma, I.; Fatemi, S.; Prata, M.; Ballarini, F.; Carante, M. P.; Farias, R.; González, S. J.; Marrale, M.; Gallo, S.; Bartolotta, A.; Iacoviello, G.; Nigg, D.; Altieri, S.

    2018-01-01

    University of Pavia is equipped with a TRIGA Mark II research nuclear reactor, operating at a maximum steady state power of 250 kW. It has been used for many years to support Boron Neutron Capture Therapy (BNCT) research. An irradiation facility was constructed inside the thermal column of the reactor to produce a sufficient thermal neutron flux with low epithermal and fast neutron components, and low gamma dose. In this irradiation position, the liver of two patients affected by hepatic metastases from colon carcinoma were irradiated after borated drug administration. The facility is currently used for cell cultures and small animal irradiation. Measurements campaigns have been carried out, aimed at characterizing the neutron spectrum and the gamma dose component. The neutron spectrum has been measured by means of multifoil neutron activation spectrometry and a least squares unfolding algorithm; gamma dose was measured using alanine dosimeters. Results show that in a reference position the thermal neutron flux is (1.20 ± 0.03) ×1010 cm-2 s-1 when the reactor is working at the maximum power of 250 kW, with the epithermal and fast components, respectively, 2 and 3 orders of magnitude lower than the thermal component. The ratio of the gamma dose with respect to the thermal neutron fluence is 1.2 ×10-13 Gy/(n/cm2).

  11. Experimental study of radiation dose rate at different strategic points of the BAEC TRIGA Research Reactor.

    Science.gov (United States)

    Ajijul Hoq, M; Malek Soner, M A; Salam, M A; Haque, M M; Khanom, Salma; Fahad, S M

    2017-12-01

    The 3MW TRIGA Mark-II Research Reactor of Bangladesh Atomic Energy Commission (BAEC) has been under operation for about thirty years since its commissioning at 1986. In accordance with the demand of fundamental nuclear research works, the reactor has to operate at different power levels by utilizing a number of experimental facilities. Regarding the enquiry for safety of reactor operating personnel and radiation workers, it is necessary to know the radiation level at different strategic points of the reactor where they are often worked. In the present study, neutron, beta and gamma radiation dose rate at different strategic points of the reactor facility with reactor power level of 2.4MW was measured to estimate the rising level of radiation due to its operational activities. From the obtained results high radiation dose is observed at the measurement position of the piercing beam port which is caused by neutron leakage and accordingly, dose rate at the stated position with different reactor power levels was measured. This study also deals with the gamma dose rate measurements at a fixed position of the reactor pool top surface for different reactor power levels under both Natural Convection Cooling Mode (NCCM) and Forced Convection Cooling Mode (FCCM). Results show that, radiation dose rate is higher for NCCM in compared with FCCM and increasing with the increase of reactor power. Thus, concerning the radiological safety issues for working personnel and the general public, the radiation dose level monitoring and the experimental analysis performed within this paper is so much effective and the result of this work can be utilized for base line data and code verification of the nuclear reactor. Copyright © 2017 Elsevier Ltd. All rights reserved.

  12. Experience in utilizing research reactors in Yugoslavia

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J.; Raisic, N. [Boris Kidric Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia); Copic, M.; Gabrovsek, Z. [Jozef Stefan Institute Ljubljana (Yugoslavia)

    1972-07-01

    The nuclear institutes in Yugoslavia possess three research reactors. Since 1958, two heavy-water reactors have been in operation at the 'Boris Kidric' Institute, a zero-power reactor RB and a 6. 5-MW reactor RA. At the Jozef Stefan Institute, a 250-kW TRIGA Mark II reactor has been operating since 1966. All reactors are equipped with the necessary experimental facilities. The main activities based on these reactors are: (1) fundamental research in solid-state and nuclear physics; (2) R and D activities related to nuclear power program; and (3) radioisotope production. In fundamental physics, inelastic neutron scattering and diffraction phenomena are studied by means of the neutron beam tubes and applied to investigations of the structures of solids and liquids. Valuable results are also obtained in n - γ reaction studies. Experiments connected with the fuel -element development program, owing to the characteristics of the existing reactors, are limited to determination of the fuel element parameters, to studies on the purity of uranium, and to a small number of capsule irradiations. All three reactors are also used for the verification of different methods applied in the analysis of power reactors, particularly concerning neutron flux distributions, the optimization of reactor core configurations and the shielding effects. An appreciable irradiation space in the reactors is reserved for isotope production. Fruitful international co-operation has been established in all these activities, on the basis of either bilateral or multilateral arrangements. The paper gives a critical analysis of the utilization of research reactors in a developing country such as Yugoslavia. The investments in and the operational costs of research reactors are compared with the benefits obtained in different areas of reactor application. The impact on the general scientific, technological and educational level in the country is also considered. In particular, an attempt is made ro

  13. Experience in utilizing research reactors in Yugoslavia

    International Nuclear Information System (INIS)

    Pop-Jordanov, J.; Raisic, N.; Copic, M.; Gabrovsek, Z.

    1972-01-01

    The nuclear institutes in Yugoslavia possess three research reactors. Since 1958, two heavy-water reactors have been in operation at the 'Boris Kidric' Institute, a zero-power reactor RB and a 6. 5-MW reactor RA. At the Jozef Stefan Institute, a 250-kW TRIGA Mark II reactor has been operating since 1966. All reactors are equipped with the necessary experimental facilities. The main activities based on these reactors are: (1) fundamental research in solid-state and nuclear physics; (2) R and D activities related to nuclear power program; and (3) radioisotope production. In fundamental physics, inelastic neutron scattering and diffraction phenomena are studied by means of the neutron beam tubes and applied to investigations of the structures of solids and liquids. Valuable results are also obtained in n - γ reaction studies. Experiments connected with the fuel -element development program, owing to the characteristics of the existing reactors, are limited to determination of the fuel element parameters, to studies on the purity of uranium, and to a small number of capsule irradiations. All three reactors are also used for the verification of different methods applied in the analysis of power reactors, particularly concerning neutron flux distributions, the optimization of reactor core configurations and the shielding effects. An appreciable irradiation space in the reactors is reserved for isotope production. Fruitful international co-operation has been established in all these activities, on the basis of either bilateral or multilateral arrangements. The paper gives a critical analysis of the utilization of research reactors in a developing country such as Yugoslavia. The investments in and the operational costs of research reactors are compared with the benefits obtained in different areas of reactor application. The impact on the general scientific, technological and educational level in the country is also considered. In particular, an attempt is made ro

  14. Characteristics and uses of a 250 kW TRIGA reactor

    International Nuclear Information System (INIS)

    Dimic, V.

    1985-01-01

    The 250 kW TRIGA Mark II reactor is a light water reactor with solid fuel elements in which the zirconium hydride moderator is homogeneously distributed between enriched uranium. Therefore the reactor has the large prompt negative temperature coefficient of reactivity, the fuel also has very high retention of radioactive fission products. The reactor core is a cylindrical configuration with an annular graphite reflector. The experimental facilities include a rotary specimen rack, a central incore radiation thimble, a pneumatic transfer system, and pulsing capability. Other experimental facilities include two radial and two tangential beam tubes, a graphite thermal column, and a graphite thermalizing column. At the steady state power of 250 kW the peak flux is 1x10 13 n/cm 2 s in the central test position. In addition, pulsing to about 2000 MW is usually provided giving peak fluxes of about 2x10 16 n/cm 2 sec. All TRIGA reactors produce a core-average thermal neutron flux of about 10 7 n.v per watt. Only with very large accelerators could such a high neutron flux be achieved. In order to give an appreciation for the research conducted at research reactors, the types of research could be summarized as follows: thermal neutron scattering, neutron radiography, neutron and nuclear physics, activation analysis, radiochemistry, biology and medicine, and teaching and training. Typical applied research with a 250 kW reactor has been conducted in medicine in biology, archeology, metallurgy and materials science, engineering and criminology. It is well known that research reactors have been used routinely to produce isotopes for industry and medicine. In some instances, reactors are the preferred method of isotope production. We can conclude that the 250 kW TRIGA research reactor is a useful and wide ranging source of radiation for basic and applied research. The operation cost for this instrument is relatively low. (author)

  15. The Austrian Space Plan

    Science.gov (United States)

    Pseiner, K.; Balogh, W.

    2002-01-01

    After several years of preparation and discussion among the involved players, the Austrian Space Plan was approved for implementation in November 2001. Based on careful benchmarking and analysis of the capabilities of the Austrian space sector it aims to create excellent conditions for the sector's further development. The new space strategy embraces Austria's participation in the mandatory and optional programmes of the European Space Agency and establishes a National Space Programme supported by separate funding opportunities. A set of clearly-defined indicators ensures that the progress in implementing the Space Plan can be objectively judged through independent, annual reviews. The National Space Programme promotes international cooperation in space research and space activities with the aim to strengthen the role of space science and to better prepare Austrian space industry for the commercial space market. In the framework of the Space Plan the Austrian Space Agency has been tasked with integrating the industry's growing involvement in aeronautics activities to better utilize synergies with the space sector. This paper reviews the various steps leading to the approval of the new space strategy and discusses the hurdles mastered in this process. It reports on the Space Plan's first results, specifically taking into account projects involving international cooperation. For the first the Austria aerospace-sector can rely on an integrated strategy for aeronautics- and space activities which is firmly rooted in the efforts to enhance the country's R&D activities. It may also act as a useful example for other small space- using countries planning to enhance their involvement in space activities.

  16. An Overview of Strategic Utilization Plan for the Moroccan Nuclear Research Reactor over the Period of 2010–2015

    International Nuclear Information System (INIS)

    Jibre, A.; Boufraqech, A.

    2013-01-01

    The National Centre for Nuclear Energy, Science and Technology (CNESTEN), a Moroccan state-owned company, is setting up a strategic utilization plan for its recently commissioned and licensed nuclear research reactor, Triga Mark II, 2 MW, over the period of 2010–2015. This strategic plan is aiming to efficiently and effectively meet existing and potential needs: research and development, education and training, and generally all related products and services, both at national and regional level, within a sustainable framework. For that purpose, CNESTEN’s vision is to develop and strengthen its position in the market place by fully integrating both operational and logistical issues in being strategically led, market oriented, competitively focused, operationally efficient, revenue generating applications emphasized, and human resources driven. In terms of existing and potential services and products to be delivered from the research reactor, CNESTEN is more focusing on education and training, for which an international training centre is under development; radioisotopes production, for both medical and industrial uses for which CNESTEN has a leading national position; analytical techniques such as NAA and PGNAA; neutron beam techniques such as neutron imaging and neutron diffraction; and irradiation services for NTD. (author)

  17. TRIGLAV-W a Windows computer program package with graphical users interface for TRIGA reactor core management calculations

    International Nuclear Information System (INIS)

    Zagar, T.; Zefran, B.; Slavic, S.; Snoj, L.; Ravnik, M.

    2006-01-01

    TRIGLAV-W is a program package for reactor calculations of TRIGA Mark II research reactor cores. This program package runs under Microsoft Windows operating system and has new friendly graphical user interface (GUI). The main part of the package is the TRIGLAV code based on two dimensional diffusion approximation for flux distribution calculation. The new GUI helps the user to prepare the input files, runs the main code and displays the output files. TRIGLAV-W has a user friendly GUI also for the visualisation of the calculation results. Calculation results can be visualised using 2D and 3D coloured graphs for easy presentations and analysis. In the paper the many options of the new GUI are presented along with the results of extensive testing of the program. The results of the TRIGLAV-W program package were compared with the results of WIMS-D and MCNP code for calculations of TRIGA benchmark. TRIGLAV-W program was also tested using several libraries developed under IAEA WIMS-D Library Update Project. Additional literature and application form for TRIGLAV-W program package beta testing can be found at http://www.rcp.ijs.si/triglav/. (author)

  18. Development of Power Controller System based on Model Reference Adaptive Control for a Nuclear Reactor

    International Nuclear Information System (INIS)

    Mohd Sabri Minhat; Izhar Abu Hussin; Ridzuan Abdul Mutalib

    2014-01-01

    The Reactor TRIGA PUSPATI (RTP)-type TRIGA Mark II was installed in the year 1982. The Power Controller System (PCS) or Automated Power Controller System (APCS) is very important for reactor operation and safety reasons. It is a function of controlled reactivity and reactor power. The existing power controller system is under development and due to slow response, low accuracy and low stability on reactor power control affecting the reactor safety. The nuclear reactor is a nonlinear system in nature, and it is power increases continuously with time. The reactor parameters vary as a function of power, fuel burnup and control rod worth. The output power value given by the power control system is not exactly as real value of reactor power. Therefore, controller system design is very important, an adaptive controller seems to be inevitable. The method chooses is a linear controller by using feedback linearization, for example Model Reference Adaptive Control. The developed APCS for RTP will be design by using Model Reference Adaptive Control (MRAC). The structured of RTP model to produce the dynamic behaviour of RTP on entire operating power range from 0 to 1MWatt. The dynamic behavior of RTP model is produced by coupling of neutronic and thermal-hydraulics. It will be developed by using software MATLAB/Simulink and hardware module card to handle analog input signal. A new algorithm for APCS is developed to control the movement of control rods with uniformity and orderly for RTP. Before APCS test to real plant, simulation results shall be obtained from RTP model on reactor power, reactivity, period, control rod positions, fuel and coolant temperatures. Those data are comparable with the real data for validation. After completing the RTP model, APCS will be tested to real plant on power control system performance by using real signal from RTP including fail-safe operation, system reliable, fast response, stability and accuracy. The new algorithm shall be a satisfied

  19. Moroccan TRIGA nuclear reactor, an important tool for the development of research, education and training

    International Nuclear Information System (INIS)

    Caoui, A.

    2011-01-01

    Full text: The construction of the Nuclear Research Center of Maamora (NRCM) will enable to the National Center for Nuclear Energy, Sciences and Techniques (CNESTEN) to fulfill its missions for promotion of nuclear techniques in socioeconomic fields, act as technical support for the authorities, and contribute to the introduction of nuclear power for electricity generation considered in the new energy strategy as alternative option for the period 2020-2030. The CNESTEN has commisioned its nuclear research reactor Triga Mark II of 2000 KW on 2007 for wich the operating authorization was delivered on 2009. This research reactor is the keystone structure of the NRCM, its existing and planed utilization include: production of radioisotopes for medical use, neutron activation analysis, non-destructive examination techniques, neutron scattering, reactor physics research and training. In term of human ressources development, CNESTEN is more focusing on education and training for wich an international training Center is under development. The TRIGA research reactor will be an important component of this center. In order to promote the utilization of the reserch reactor in socio-economical sectors at national level, CNESTEN organizea meetings, schools and conferences around each of the reactor applications, and offers the opportunity to researchers, students, socio-economic operators to know more about reactor utilization within scientific visits, courses and training programs. At the international level, CNESTEN strengthens its international partenership. The regional and international cooperation with IAEA, AFRA and bilateral parteners (USA, France), constitutes the platform for capacity building in different areas of CNESTEN RIGA research reactor utilization

  20. Dose estimation in B16 tumour bearing mice for future irradiation in the thermal column of the TRIGA reactor after B/Gd/LDL adduct infusion

    Energy Technology Data Exchange (ETDEWEB)

    Protti, N., E-mail: nicoletta.protti@pv.infn.it [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy); Ballarini, F.; Bortolussi, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy); Bruschi, P. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy); Stella, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy); Geninatti, S.; Alberti, D.; Aime, S. [University of Torino, Chemistry Department, via Nizza 52, 10126 Torino (Italy); Altieri, S. [University of Pavia, Department of Nuclear and Theoretical Physics, via Bassi 6, 27100 Pavia (Italy)] [National Institute of Nuclear Physics (INFN) Section of Pavia, via Bassi 6, 27100 Pavia (Italy)

    2011-12-15

    To test the efficacy of a new {sup 10}B-vector compound, the B/Gd/LDL adduct synthesised at Torino University, in vivo irradiations of murine tumours are in progress at the TRIGA Mark II reactor of the Pavia University. A localised B16 melanoma tumour is generated in C57BL/6 mice and subsequently infused with the adduct. During the irradiation, the mouse will be put in a shield to protect the whole body except the tumour in the back-neck area. To optimise the treatment set-up, MCNP simulations were performed. A very simplified mouse model was built using MCNP geometry capabilities, as well as the geometry of the shield made of 99% {sup 10}B enriched boric acid. A hole in the shield is foreseen in correspondence of the back-neck region. Many configurations of the shield were tested in terms of neutron flux, dose distribution and mean induced activity in the tumour region and in the radiosensitive organs of the mouse. In the final set-up, up to five mice can be treated simultaneously in the reactor thermal column and the neutron fluence in the tumour region for 10 min of irradiation is of about 5 Multiplication-Sign 10{sup 12} cm{sup -2}.

  1. Operational experience with the TRIGA reactor of the University of Pavia

    International Nuclear Information System (INIS)

    Borio di Tigliole, A.; Alloni, D.; Cagnazzo, M.; Coniglio, M.; Lana, F.; Losi, A.; Magrotti, G.; Manera, S.; Marchetti, F.; Pappalardo, P.; Prata, M.; Salvini, A.; Scian, G.; Vinciguerra, G.

    2008-01-01

    The TRIGA Mark II research reactor of the University of Pavia is in operation since 1965. The annual operational time at nominal power (250 kW) is in the range of 300 - 400 hours depending upon the time schedule of some experiments and research activities. The reactor is mainly used for NAA activities and BNCT research. Few tens of hours per year are dedicated also to electronic devices irradiation and student training courses. Few homemade upgrading of the reactor were realized in the past two years: components of the secondary/tertiary cooling circuit were substituted and a new radiation area monitoring system was installed. Also the Instrumentation and Control (I and C) system was almost completely refurbished. The presentation describes the major extraordinary maintenance activities implemented and the status of main reactor systems: - The I and C System: complete substitution, channel-by-channel without changing the operating and safety logics; - Tertiary and secondary water-cooling circuits: complete substitution of the tertiary water-cooling circuit and partial substitution of the components of the secondary water-cooling circuit; - Reactor Building Air Filtering and Ventilation System: installation of a computerized air filtering and ventilation system; - Radiation Area Monitoring System: new system based on a commercial micro-computer and an home-made software developed on Lab-View platform. The system is made of a network of different instruments coupled, trough a serial bus line RS232, with a data acquisition station; - Fuel Elements: at the moment, the core is made of 48 Aluminium clad and 34 SST clad TRIGA fuel elements controlled periodically for their elongation and/or bowing. All components and systems undergo ordinary maintenance according to the Technical Prescriptions and to the 'Good Practice Procedures'. In summary, the TRIGA reactor of the University of Pavia shows a very good technical state and, at the moment, there are no political or

  2. Basic research using the 250 kW research reactor of the Jozef Stefan Institute

    International Nuclear Information System (INIS)

    Dimic, V.

    1984-01-01

    The 250 kW TRIGA Mark II reactor is a light water reactor with solid fuel elements in which the zirconium hydride moderator is homogeneously distributed between enriched uranium. The reactor therefore has a large prompt negative temperature coefficient of reactivity; the fuel also has a very high retention of radioactive fission products. The experimental facilities include a rotary specimen rack, a central in-core radiation thimble, a pneumatic transfer system and pulsing capability. Other experimental facilities include two radial and two tangential beam tubes, a graphite thermal column and a graphite thermalizing column. At the steady state power of 250 kW the peak flux is 1x10 13 n/cm 2 in the central test position. In addition, pulsing to about 2000 MW is usually provided giving peak fluxes of about 2x10 16 n/cm 2 sec. All TRIGA reactors produce a core-average thermal neutron flux of about 10 7 n.v. per watt. Only with very large accelerators can such high fluxes be achieved. The types of research could be summarized as follows: thermal neutron scattering, neutron radiography, neutron and nuclear physics, activation analysis, radiochemistry, biology and medicine, and teaching and training. Typical applied research with a 250 kW reactor has been conducted in medicine, in biology, archaeology, metallurgy and materials science, engineering and criminology. It is well known that research reactors have been used routinely to produce isotopes for industry and medicine. We can conclude that the 250 kW TRIGA reactor is a useful and wide ranging source of radiation for basic and applied research. The operation cost for this instrument is relatively low. (author)

  3. Using a research reactor to teach practical radiation protection

    International Nuclear Information System (INIS)

    Musilek, A.; Steinhauser, G.

    2010-01-01

    To teach students about the practical handling of radioactive materials and the related radiation protection, it is advantageous to be able to produce radioactive material with specific properties. Through the neutron activation of specific samples, radio-nuclides can be produced that are precisely tailored for particular experiments, both in type of radiation (beta, gamma) as well as in activity and half-life. At the Atominstitut in Vienna, a 250 kW TRIGA Mark II research reactor is used for the production of these nuclides. In this paper, four practical exercises are presented, covering many questions and challenges that occur in radiation protection. The first exercise uses neutron activation of sodium-chloride to cover theoretical aspects of the calculation of dose rates (using dose rate constants) through the activation of Na-23, Cl-35 and Cl-37 (including cross sections, half-life, inverse square law), as well as a practical examination (handling of dose rate meters). The second exercise gives students the opportunity to decontaminate a laboratory after an incident under realistic circumstances. For this exercise, KNO 3 is activated in the reactor. The resulting K-nuclide produces no risk of inadequate decontamination for the laboratory, since the half-life of K-42 is only 12 h. The third exercise is designed to teach students how to deal with unsealed radioactive material by irradiation of ammonium dihydrogenphosphate. In this case, an only-beta-active (P-32) fertilizer is produced, which is applied to plants in subsequent chemical processing. In the following step, the 'quality of this fertilizer' is determined by measuring the absorbed activity of the plant leaves using a GM counter. The fourth exercise is another approach in working with unsealed radioactive material. It simulates the PUREX process to separate uranium from fission products using a liquid - liquid extraction. (authors)

  4. Optimization of reactor power by taking into consideration temperature increase in a reactor pumped 3He-Xe laser

    International Nuclear Information System (INIS)

    Cetin, Fuesun

    2009-01-01

    In nuclear pumped lasers, gas parameters are optimized in a manner such that output power is increased for constructing a high power laser. Since output power increases with the increase of energy deposited in the gas, high output power requires high pumping power. However, the high energy loading results in elevated gas temperature. Temperature increase of this magnitude can detrimentally influence the laser gain and efficiency, since it negatively impacts several important laser kinetic.processes. This fact may cause laser output to abruptly terminate before the peak of the pump pulse [1-3]. A nuclear pumped laser using a volumetric energy source through the 3 He(n, p) 3 H reaction has here been considered. It is assumed that TRIGA Mark II Reactor at Istanbul Technical University is used for nuclear pumping as the neutron source. In the previous papers, the optimal parameters for improving both output power and optical homogeneity were determined [4-5]. Spatial and temporal variations of gas temperature during pumping pulse for maximum peak power (1200 MW) were determined for various operating pressures in Ref. [6]. It was seen that gas temperature reaches up to 1000 0 K near the peak of the pumping pulse for the initial pressures of 1-4 atm. This means that laser output may terminate before the peak of the pump pulse due to overheating of laser gas. Under these conditions, a question arises about a further optimisation taking into consideration gas temperature. This question has been examined in this study. Experimental results (Batyrbekov et al, 1989) showed that temperature rise up to 650 C had no influence on Xe laser characteristics [ 7]. Therefore, It has here been assumed that the lasing will terminate when gas temperature reaches 1000 0 K for a Xe-laser with 3 He buffer gas. Under these conditions optimum reactor power is investigated by taking into consideration lasing duration also. (orig.)

  5. Assessment of structural materials inside the reactor pool of the Dalat research reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Luong Ba Vien; Nguyen Minh Tuan; Trang Cao Su

    2010-01-01

    Originally the Dalat Nuclear Research Reactor (DNRR) was a 250-kW TRIGA MARK II reactor, started building from early 1960s and achieved the first criticality on February 26, 1963. During the 1982-1984 period, the reactor was reconstructed and upgraded to 500kW, and restarted operation on March 20, 1984. From the original TRIGA reactor, only the pool liner, beam ports, thermal columns, and graphite reflector have been remained. The structural materials of pool liner and other components of TRIGA were made of aluminum alloy 6061 and aluminum cladding fuel assemblies. Some other parts, such as reactor core, irradiation rotary rack around the core, vertical irradiation facilities, etc. were replaced by the former Soviet Union's design with structural materials of aluminum alloy CAV-1. WWR-M2 fuel assemblies of U-Al alloy 36% and 19.75% 235 U enrichment and aluminum cladding have been used. In its original version, the reactor was setting upon an all-welded aluminum frame supported by four legs attached to the bottom of the pool. After the modification made, the new core is now suspended from the top of the pool liner by means of three aluminum concentric cylindrical shells. The upper one has a diameter of 1.9m, a length of 3.5m and a thickness of 10mm. This shell prevents from any visual access to the upper part of the pool liner, but is provided with some holes to facilitate water circulation in the 4cm gap between itself and the reactor pool liner. The lower cylindrical shells act as an extracting well for water circulation. As reactor has been operated at low power of 500 kW, it was no any problem with degradation of core structural materials due to neutron irradiation and thermal heat, but there are some ageing issues with aluminum liner and other structures (for example, corrosion of tightening-up steel bolt in the fourth beam port and flood of neutron detector housing) inside the reactor pool. In this report, the authors give an overview and assessment of

  6. Fluence measurement at the neutron time of flight experiment at CERN

    CERN Document Server

    Weiss, Christina; Jericha, Erwin

    At the neutron time of flight facility n_TOF at CERN a new spallation target was installed in 2008. In 2008 and 2009 the commissioning of the new target took place. During the summer 2009 a fission chamber of the Physikalisch Technische Bundesanstalt (PTB) Braunschweig was used for the neutron fluence measurement. The evaluation of the data recorded with this detector is the primary topic of this thesis. Additionally a neutron transmission experiment with air has been performed at the TRIGA Mark II reactor of the Atomic Institute of the Austrian Universities (ATI). The experiment was implemented to clarify a question about the scattering cross section of molecular gas which could not be answered clearly via the literature. This problem came up during the evaluations for n_TOF.

  7. Austrian emission under international comparison

    International Nuclear Information System (INIS)

    Anderl, M.; Gager, M.; Gugele, B.; Huttunen, K.; Kurzweil, A.; Poupa, S.; Ritter, M.; Wappel, D.; Wieser, M.

    2004-01-01

    A comparison between anthropogenic emissions of CO 2 , CH 4 , N 2 O, SO 2 , NO x , volatile organic compounds (NMVOC), NH 3 and CO from the European Union, European Union candidate countries and Austria is presented. Data covers the years 1999-2001 and the emissions values per habitant are provided as well as a comparison against the Kyoto goals. In the middle of the European mean values are the austrian emissions values, austrian SO 2 emissions are the smallest, however CH 4 , CO and NMVOC emissions are over the European mean values. 8 figs., 6 tabs. (nevyjel)

  8. Conceptual Design of a Clinical BNCT Beam in an Adjacent Dry Cell of the Jozef Stefan Institute TRIGA Reactor

    International Nuclear Information System (INIS)

    Maucec, Marko

    2000-01-01

    The MCNP4B Monte Carlo transport code is used in a feasibility study of the epithermal neutron boron neutron capture therapy facility in the thermalizing column of the 250-kW TRIGA Mark II reactor at the Jozef Stefan Institute (JSI). To boost the epithermal neutron flux at the reference irradiation point, the efficiency of a fission plate with almost 1.5 kg of 20% enriched uranium and 2.3 kW of thermal power is investigated. With the same purpose in mind, the TRIGA reactor core setup is optimized, and standard fresh fuel elements are concentrated partly in the outermost ring of the core. Further, a detailed parametric study of the materials and dimensions for all the relevant parts of the irradiation facility is carried out. Some of the standard epithermal neutron filter/moderator materials, as well as 'pressed-only' low-density Al 2 O 3 and AlF 3 , are considered. The proposed version of the BNCT facility, with PbF 2 as the epithermal neutron filter/moderator, provides an epithermal neutron flux of ∼1.1 x 10 9 n/cm 2 .s, thus enabling patient irradiation times of nfast /φ epi -13 Gy.cm 2 /n and [overdot]D γ /φ epi -13 Gy.cm 2 /n), the in-air performances of the proposed beam are comparable to all existing epithermal BNCT facilities. The design presents an equally efficient alternative to the BNCT beams in TRIGA reactor thermal columns that are more commonly applied. The cavity of the dry cell, a former JSI TRIGA reactor spent-fuel storage facility, adjacent to the thermalizing column, could rather easily be rearranged into a suitable patient treatment room, which would substantially decrease the overall developmental costs

  9. The Austrian Research Centers activities in energy risks

    International Nuclear Information System (INIS)

    Sdouz, Gert

    1998-01-01

    Among the institutions involved in energy analyses in Austria the risk context is being treated by three different entities: the Energy Consumption Agency, internationally known as EVA, the Federal Environmental Protection Agency, or Urnweltbundesarnt assessing mainly the environmental risks involved and the Austrian Research Centers, working on safety and risk evaluation. The Austrian Research Center Seibersdorf draws form its proficiency in Reactor Safety and Fusion Research, two fields of experience it has been involved in since its foundation, for some 40 years now. Nuclear energy is not well accepted by the Austrian population. Therefore in our country only energy systems with advanced safety level might be accepted in the far future. This means that the development of methods to compare risks is an important task. The characteristics of energy systems featuring advanced safety levels are: A very low hazard potential and a focus on deterministic safety instead of probabilistic safety, meaning to rely on inherently safe physics concepts, confirmed by probabilistic safety evaluation results. This can be achieved by adequate design of fusion reactors, advanced fission reactors and all different renewable sources of energy

  10. Visit of the Austrian Ambassador

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    The Austrian Ambassador Wolfgang Petritsch (light raincoat) learns about superconducting magnets at the LHC magnet test facility in building SM18 during a visit to CERN. The blue pipe-like structure in the left background is String 2: the 120-m long full-scale model of an LHC cell, which is used to test LHC systems.

  11. Austrian natural scientists in exile

    International Nuclear Information System (INIS)

    Broda, E.

    1978-01-01

    This text was written by E. Broda for the international symposium for exploration of the Austrian exile from 1934 to 1945 (“Internationales Symposiums zur Erforschung des österreichischen Exils von 1934 bis 1945”) in the year 1978. The article is about the specific problems of the Austrian scientific landscape, caused by the political events in the first half of the 20th century. The focus is primarily on the enormous ‘brain drain’, triggered by political repression in the period of Nazi rule (1938 - 1945), the Austro-fascism period (1934 - 1938) and the economic regression, anti-intellectual and anti-Semitic sentiment in the Country since 1918. The article emphasizes the importance of exile organizations, such as the ‘Free Austrian Movement’ or the ‘Association of Austrian Engineers, Chemists and Scientific Workers in Great Britain’ for the reconstruction of a scientific culture in Austria, after the Second World War. (rössner) [de

  12. Fuel Management at the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Pham, V.L.; Nguyen, N.D.; Luong, B.V.; Le, V.V.; Huynh, T.N.; Nguyen, K.C. [Nuclear Research Institute, 01 Nguyen Tu Luc Street, Dalat City (Viet Nam)

    2011-07-01

    The Dalat Nuclear Research Reactor (DNRR) is a pool type research reactor which was reconstructed in 1982 from the old 250 kW TRIGA-MARK II reactor. The spent fuel storage was newly designed and installed in the place of the old thermalizing column for biological irradiation. The core was loaded by Russian WWR-M2 fuel assemblies (FAs) with 36% enrichment. The reconstructed reactor reached its initial criticality in November 1983 and attained it nominal power of 500 kW in February 1984. The first fuel reloading was executed in April 1994 after more than 10 years of operation with 89 highly enriched uranium (HEU) FAs. The third fuel reloading by shuffling of HEU FAs was executed in June 2004. After the shuffling the working configuration of reactor core kept unchanged of 104 HEU FAs. The fourth fuel reloading was executed in November 2006. The 2 new HEU FAs were loaded in the core periphery, at previous locations of wet irradiation channel and dry irradiation channel. After reloading the working configuration of reactor core consisted of 106 HEU FAs. Contracts for reactor core conversion between USA, Russia, Vietnam and the International Atomic Energy Agency for Nuclear fuel manufacture and supply for DNRR and Return of Russian-origin non-irradiated highly enriched uranium fuel to the Russian Federation have been realized in 2007. According to the results of design and safety analyses performed by the joint study between RERTR Program at Argonne National Laboratory and Vietnam Atomic Energy Institute the mixed core configurations of irradiated HEU and new low enriched uranium (LEU) FAs has been created on 12 September, 2007 and on 20 July, 2009. After reloading in 2009, the 14 HEU FAs with highest burnup were removed from the core and put in the interim storage in reactor pool. The works on full core conversion for the DNRR are being realized in cooperation with the organizations, DOE and IAEA. Contract for Nuclear fuel manufacture and supply of 66 LEU FAs for DNRR

  13. Status of neutron beam utilization at the Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    Dien, Nguyen Nhi; Hai, Nguyen Canh

    2003-01-01

    The 500-kW Dalat nuclear research reactor was reconstructed from the USA-made 250-kW TRIGA Mark II reactor. After completion of renovation and upgrading, the reactor has been operating at its nominal power since 1984. The reactor is used mainly for radioisotope production, neutron activation analysis, neutron beam researches and reactor physics study. In the framework of the reconstruction and renovation project of the 1982-1984 period, the reactor core, the control and instrumentation system, the primary and secondary cooling systems, as well as other associated systems were newly designed and installed by the former Soviet Union. Some structures of the reactor, such as the reactor aluminum tank, the graphite reflector, the thermal column, horizontal beam tubes and the radiation concrete shielding have been remained from the previous TRIGA reactor. As a typical configuration of the TRIGA reactor, there are four neutron beam ports, including three radial and one tangential. Besides, there is a large thermal column. Until now only two-neutron beam ports and the thermal column have been utilized. Effective utilization of horizontal experimental channels is one of the important research objectives at the Dalat reactor. The research program on effective utilization of these experimental channels was conducted from 1984. For this purpose, investigations on physical characteristics of the reactor, neutron spectra and fluxes at these channels, safety conditions in their exploitation, etc. have been carried out. The neutron beams, however, have been used only since 1988. The filtered thermal neutron beams at the tangential channel have been extracted using a single crystal silicon filter and mainly used for prompt gamma neutron activation analysis (PGNAA), neutron radiography (NR) and transmission experiments (TE). The filtered quasi-monoenergetic keV neutron beams using neutron filters at the piercing channel have been used for nuclear data measurements, study on

  14. Mr. Wolfgang Petritsch, Austrian Ambassador

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    Dr.Peter Schmid/CERN/EP, Dr.Wolfgang Petritsch, Austrian Ambassador, Permanent representative at UN, Mrs.Nora Petritsch, Dr.Kurt Hubner/CERN/AC, Mrs. Frederike Klaus-Salesin, Adviser, Mrs.Andrea Strohmeier, Secretary of the Ambassador, Mr.Heinz Klaus, Attaché, Dr.Theodor Tortschanoff/CERN/LHC, Mr.Peter Storer, Advisor. Dr.Peter Schmid/CERN/EP, Dr.Wolfgang Petritsch, Austrian Ambassador, Permanent representative at UN, Mrs.Nora Petritsch, Dr.Kurt Hubner/CERN/AC, Mrs. Frederike Klaus-Salesin, Adviser, Mrs.Andrea Strohmeier, Secretary of the Ambassador, Mr.Heinz Klaus, Attaché, Dr.Theodor Tortschanoff/CERN/LHC, Mr.Peter Storer, Advisor.

  15. From the 'Austrian Foundation for Atomic Energy Research' to the 'Seibersdorf Laboratories'

    International Nuclear Information System (INIS)

    Rößner, M.

    2013-01-01

    The aim of this thesis is the description of the process of institutionalization of nuclear research in Austria in the context of the „Atoms for Peace“ program in the 1950s. This aspect of the history of Austrian nuclear research has been relatively unexplored. The focus of this work is the presentation of measures that have been put in Austria to participate in the 'Atoms for Peace' program. Moreover, the expectations and goals of the Austrian nuclear program are analyzed. For this purpose, foundation, structure and research activities of the “Austrian Atomic Energy Commission”, the “Austrian Society for the Study of Atomic Energy” and the “Nuclear Reactor Centre Seibersdorf“ in the period from 1954 until about 1970 are examined. To establish a relationship with the international historical research of the history of nuclear research, the Austrian situation is compared to the Swiss and the German. It turns out that the Austrian expectations and objectives in nuclear research at the beginning of the period of observation roughly corresponded with the international trends. It also follows that by the establishment of the SGAE and the “Nuclear Reactor Centre Seibersdorf“ the development course of Austrian nuclear research occupied a special position compared to foreign institutions.(author) [de

  16. The reception of Austrian economics in Italy

    Directory of Open Access Journals (Sweden)

    Antonio Magliulo

    2018-04-01

    Full Text Available Nowadays the Austrian School enjoys high reputation in Italy: books by Mises, Hayek and other Austrian economists are constantly republished and reviewed with great interest, both inside and outside academic circles. The situation was very different decades ago, when just a few Italian economists devoted attention to the Austrian School. This work studies the reception of Austrian Economics in Italy, from the beginning to our days, so as to bring out, by way of comparison, relevant features of Italian economic culture. We will try to offer just an overview of the entire story, in an attempt to provide useful elements for a deeper analysis of further topics and periods.

  17. Technical report on treatment of radioactive slurry liquid waste

    International Nuclear Information System (INIS)

    Jeong, Gyeong Hwan; Jo, Eun Sung; Park, Seung Kook; Jung, Ki Jung

    1999-06-01

    By literature survey, this report deals with the technology on typical pre-treatment and filtration of radioactive slurry liquid waste, produced during the operation of TRIGA Mark-II, III research reactor, and produced during the decommission/decontamination of TRIGA Mark-II, III research reactor. It is reviewed pre-treatment procedure, both physical and chemical that optimise the dewatering characteristics, and also surveyed types of dewatering devices based on centrifuges, vacuum and pressure filters with particular reference to various combined field approaches using two or more complementary driving forces to achieve better performance. Dewatering operations and devises on filtration of radioactive slurry liquid waste are also analysed. (author)

  18. Computational analysis of Bangladesh 3 MW TRIGA research reactor using MCNP4C, JENDL-3.3 and ENDF/B-Vl data libraries

    International Nuclear Information System (INIS)

    Huda, M.Q.

    2006-01-01

    The three-dimensional continuous energy Monte Carlo code MCNP4C was used to develop a versatile and accurate full-core model of the 3 MW TRIGA MARK II research reactor at Atomic Energy Research Establishment, Savar, Dhaka, Bangladesh. The model represents in detail all components of the core with literally no physical approximation. All fresh fuel and control elements as well as the vicinity of the core were precisely described. Validation of the JENDL-3.3 and ENDF/BVI continuous energy cross-section data for MCNP4C was performed against some well-known benchmark lattices. For TRIGA analysis, data from JENDL-3.3 and ENDF/B-VI in combination with the JENDL-3.2 and ENDF/B-V data files (for nat Zr, nat Mo, nat Cr, nat Fe, nat Ni, nat Si, and nat Mg) at 300 K evaluations were used. Full S(α, β) scattering functions from ENDF/B-V for Zr in ZrH, H in ZrH and water molecule, and for graphite were used in both cases. The validation of the model was performed against the criticality and reactivity benchmark experiments of the TRIGA reactor. There is ∼20.0% decrease of thermal neutron flux occurs when the thermal library is removed during the calculation. Effect of erbium isotope that is present in the TRIGA fuel was also studied. In addition to the effective multiplication values, the well-known integral parameters: δ 28 , δ 25 , ρ 25 , and C * were calculated and compared for both JENDL3.3 and ENDF/B-VI libraries and were found to be in very good agreement. Results are also reported for most of the analyses performed by JENDL-3.2 and ENDF/B-V data libraries

  19. The Forgotten Austrian Economics Language

    Directory of Open Access Journals (Sweden)

    Elena Bianca Vieru

    2013-02-01

    Full Text Available In light of the current events, namely the crisisthat economy has to face for quite someyears now, plenty of questions are raised, not only among specialists in the field but also amongordinary people as they prove to be most impoverished by these imbalances. Thus, this paper aims, asa first objective, to explain, froma general perspective and using an inductive-subjectivemethodology based on a brief survey as well as on observation, two of the most important causes that,according to the Austrian Business Cycle Theory, are the leading motives for triggering crises. Weare referring particularly to an excessivestate interventionismmanifested throughout itsexpansionary monetary policy.Secondly, we seek to establish the interconnections between theseelements and the case of the Great Depression as well as the current recession. The results we cameacross point out towards the same pattern designed by the Austrian economists, although thecircumstances are, each time, different. Hence, the contribution of this paper consists of handling thedetails that surround the subject by extracting only the essential aspects regarding the triggering ofcrises; we refer to the main ideas that need to be underlined for a better comprehension of the topic.

  20. CFD modeling and thermal-hydraulic analysis for the passive decay heat removal of a sodium-cooled fast reactor

    International Nuclear Information System (INIS)

    Hung, T.C.; Dhir, V.K.; Chang, J.C.; Wang, S.K.

    2011-01-01

    Research highlights: → The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. → The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). → The most important conclusion is that all obtained values of DNBR, fuel center and surface temperature, cladding surface temperature and coolant temperature across the hottest channel are largely far to compromise safety of the reactor. - Abstract: In this study, a pool-typed design similar to sodium-cooled fast reactor (SFR) of the fourth generation reactors has been modeled using CFD simulations to investigate the characteristics of a passive mechanism of Shutdown Heat Removal System (SHRS). The main aim is to refine the reactor pool design in terms of temperature safety margin of the sodium pool. Thus, an appropriate protection mechanism is maintained in order to ensure the safety and integrity of the reactor system during a shutdown mode without using any active heat removal system. The impacts on the pool temperature are evaluated based on the following considerations: (1) the aspect ratio of pool diameter to depth, (2) the values of thermal emissivity of the surface materials of reactor and guard vessels, and (3) innerpool liner and core periphery structures. The computational results show that an optimal pool design in geometry can reduce the maximum pool temperature down to ∼551 o C which is substantially lower than ∼627 o C as calculated for the reference case. It is also concluded that the passive Reactor Air Cooling System (RACS) is effective in removing decay heat after shutdown. Furthermore, thermal radiation from the surface of the reactor vessel is found to be important; and thus, the selection of the vessel surface materials with a high emissivity would be a

  1. Study on the management of radioactive solid wastes for the KRR-I and II dismantling activities

    International Nuclear Information System (INIS)

    Lee, D. G.; Kim, H. R.; Park, S. K.; Lee, B. J.; Jung, K. H.; Baek, S. T.; Jung, U. S.; Jung, K. J.

    2000-01-01

    KRR-1(TRIGA Mark II) and KRR-2(TRIGA Mark-III) have been operated 33 years and 23 years, respectively, and now are about to be decommissioned as they reach the end of their useful lives. In the decommissioning of the reactors, the treatment of radioactive wastes is practical issues and, therefore, the plan on it has to be essentially established prior to the actual decontamination and decommissioning activities. In the present study, the classification, radiological status, classification criteria and package on the radioactive solid wastes in the TRIGA Mark-II and III are investigated for the investigated for the purpose of the effective management plan of them

  2. Ten years of TRIGA reactor research at the University of Texas

    International Nuclear Information System (INIS)

    O'Kelly, Sean

    2002-01-01

    The 1 MW TRIGA Research Reactor at the Nuclear Engineering Teaching Laboratory is the second TRIGA at the University of Texas at Austin (UT). A small (10 kW-1963, 250 kW-1968) TRIGA Mark I was housed in the basement of the Engineering Building until is was shutdown and decommissioned in 1989. The new TRIGA Mark II with a licensed power of 1.1 MW reached initial criticality in 1992. Prior to 1990, reactor research at UT usually consisted of projects requiring neutron activation analysis (NAA) but the step up to a much larger reactor with neutron beam capability required additional personnel to build the neutron research program. The TCNS is currently used to perform Prompt Gamma Activation Analysis to determine hydrogen and boron concentrations of various composite materials. The early 1990s was a very active period for neutron beam projects at the NETL. In addition to the TCNS, a real-time neutron radiography facility (NIF) and a high-resolution neutron depth profiling facility (NDP) were installed in two separate beam ports. The NDP facility was most recently used to investigate alpha damage on stainless steel in support of the U.S. Nuclear Weapons Stewardship programs. In 1999, a sapphire beam filter was installed in the NDP system to reduce the fast neutron flux at the sample location. A collaborative effort was started in 1997 between UT-Austin and the University of Texas at Arlington to build a reactor-based, low-energy positron beam (TIPS). The limited success in obtaining funding has placed the project on hold. The Nuclear and Radiation Engineering Program has grown rapidly and effectively doubled in size over the past 5 years but years of low nuclear research funding, an overall stagnation in the U.S. nuclear power industry and a persuasive public distrust of nuclear energy has caused a precipitous decline in many programs. Recently, the U.S. DOE has encouraged University Research Reactors (URR) in the U.S. to collaborate closely together by forming URR

  3. Austrian emission inventory for dust

    International Nuclear Information System (INIS)

    Winiwarter, W.; Trenker, C.; Hoeflinger, W.

    2001-09-01

    For the first time, Austrian emissions of anthropogenic particulate matter emissions to the atmosphere have been estimated. Results have been reported as total suspended particles (TSP) as well as for the fractions of particles smaller than 10 μm or 2.5 μm aerodynamic diameter (PM 10 , PM 2.5 ), respectively. Base years for the inventory were 1990, 1995 and 1999. Excluded from this assessment is wind blown dust, which has been considered a natural source here. National statistics have been applied, specifically those also used previously in the Austrian air pollution inventory (OLI). Emission factors have been taken from literature compilations, only for exceptional cases specific Austrian assessments were performed or original literature on emission measurements was consulted. Resuspension of dust by road traffic emerged as the most important source. For the size fraction of PM 10 this source contributed about half of the emissions, when applying the calculation scheme by the U.S. EPA. While this scheme is widely used and well documented, its validity is currently subject of intense scientific debate. As these results do not seem to coincide with ambient air measurements, resuspension of road dust is considered separately and not now included in the national total. The sum of all other sources increases from 75,000 t of TSP in 1990 and 1995 to 77,000 t in 1999, while both PM 10 and PM 2.5 exhibit decreasing tendency (at 45,000 t and 26,000 t in 1999, respectively). The increase in TSP derives from increasing traffic and friction related emissions (tire wear, break wear), decrease of the finer particulate matter is due to reductions in firewood consumption for domestic heating. Most important source sectors are fugitive emissions from material transfer in industry as well as the building industry and the tilling of agricultural land. Common to these sources is the high uncertainty of available data. Wood combustion is the most important of the non

  4. The radiation protection units of the Austrian fire brigades

    International Nuclear Information System (INIS)

    Aspek, W.; Schoenhacker, S.

    2009-01-01

    Since the 1960s, Austrian fire brigades have been involved in radiation protection. With the preparations for the NPP Zwentendorf and the building of the research reactor in Seibersdorf, the first radiation protection units of the fire brigade were founded. 45 years later: The NPP Zwentendorf never saw its start-up, the use of nuclear energy for the production of electricity is prohibited by a constitutional law, and the research reactor is being decommissioned. What's left are the radiation protection units of the fire brigades. The contribution gives an overview of similarities and differences of the radiation protection units in the nine federal states of Austria, with a special focus on equipment, training and organisation. Nation-wide guidelines and regulations for the tactics of first responders at radiological emergencies are presented and a couple of incidents will be analysed. (orig.)

  5. The consumer in Austrian economics and the Austrian perspective on consumer policy

    NARCIS (Netherlands)

    Leen, A.R.

    1999-01-01

    In this thesis I examined the place of the competitive-entrepreneurial consumer in Austrian economic thought. For a neoclassical economist, competition among consumers is hard to find. For an Austrian economist, however, it is a necessity. The introduction puts forward the problem that although an

  6. Planning, Management and Organizational Aspects of the Decommissioning of Nuclear Facilities in Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Mollah, A. S.; Begum, A.; Pal, D. [Bangladesh Atomic Energy Commission Agargaon, Dhaka (Bangladesh)

    2013-08-15

    This report summarizes the main results obtained by the Bangladesh Atomic Energy Commission in the decommissioning of spent {sup 60}Co gamma irradiator at GammaTech Limited, Chittagong, and preparation of decommissioning plan of the 3 MW TRIGA Mark-II research reactor in Bangladesh. (author)

  7. Nondestructive method for assessment of nuclear fuel

    International Nuclear Information System (INIS)

    Kristof, E.; Pregl, G.; Krajnik, J.; Glumac, B.; Jencic, I.; Kerzic, J.; Moskon, F.; Zitnik, F.

    1983-01-01

    Description of the development of the gamma spectrometry determination of an amount of a certain radioactive fission product considering local variations of the linear attenuation coefficient of gamma rays and preliminary experiment using fuel element of TRIGA Mark II reactor in Ljubljana is given.(author)

  8. Bayesian statistics applied to neutron activation data for reactor flux spectrum analysis

    International Nuclear Information System (INIS)

    Chiesa, Davide; Previtali, Ezio; Sisti, Monica

    2014-01-01

    Highlights: • Bayesian statistics to analyze the neutron flux spectrum from activation data. • Rigorous statistical approach for accurate evaluation of the neutron flux groups. • Cross section and activation data uncertainties included for the problem solution. • Flexible methodology applied to analyze different nuclear reactor flux spectra. • The results are in good agreement with the MCNP simulations of neutron fluxes. - Abstract: In this paper, we present a statistical method, based on Bayesian statistics, to analyze the neutron flux spectrum from the activation data of different isotopes. The experimental data were acquired during a neutron activation experiment performed at the TRIGA Mark II reactor of Pavia University (Italy) in four irradiation positions characterized by different neutron spectra. In order to evaluate the neutron flux spectrum, subdivided in energy groups, a system of linear equations, containing the group effective cross sections and the activation rate data, has to be solved. However, since the system’s coefficients are experimental data affected by uncertainties, a rigorous statistical approach is fundamental for an accurate evaluation of the neutron flux groups. For this purpose, we applied the Bayesian statistical analysis, that allows to include the uncertainties of the coefficients and the a priori information about the neutron flux. A program for the analysis of Bayesian hierarchical models, based on Markov Chain Monte Carlo (MCMC) simulations, was used to define the problem statistical model and solve it. The first analysis involved the determination of the thermal, resonance-intermediate and fast flux components and the dependence of the results on the Prior distribution choice was investigated to confirm the reliability of the Bayesian analysis. After that, the main resonances of the activation cross sections were analyzed to implement multi-group models with finer energy subdivisions that would allow to determine the

  9. The Austrian school in Bulgaria: A history

    Directory of Open Access Journals (Sweden)

    Nikolay Nenovsky

    2018-04-01

    Full Text Available The main goal of this study is to highlight the acceptance, dissemination, interpretation, criticism and make some attempts at contributing to Austrian economics made in Bulgaria during the last 120 years. We consider some of the main characteristics of the Austrian school, such as subjectivism and marginalism, as basic components of the economic thought in Bulgaria and as incentives for the development of some original theoretical contributions. Even during the first few years of Communist regime (1944–1989, with its Marxist monopoly over intellectual life, the Austrian school had some impact on the economic thought in the country. Subsequent to the collapse of Communism, there was a sort of a Renaissance and rediscovery of this school. Another contribution of our study is that it illustrates the adaptability and spontaneous evolution of ideas in a different and sometimes hostile environment.

  10. “What is so Austrian about Austrian Economics?”

    OpenAIRE

    David Colander

    2009-01-01

    Modern mainstream economics is a plurocracy in which there is no orthodoxy of ideas, only an orthodoxy of method. Given the training it provides its students, mainstream economic’s natural domain is science. With the mainstream’s acceptance of complexity views of the economy, Austrian economist’s views can now get a hearing within the mainstream. Thus, within the science of economics, there is no need for a separate Austrian economics. However, there is a need for Austrian economics in politi...

  11. The Continuing Relevance of Austrian Capital Theory

    DEFF Research Database (Denmark)

    Foss, Nicolai Juul

    2012-01-01

    The article presents a speech by Professor Nicolai J. Foss of Copenhagen Business School, delivered at the Austrian Scholars Conference held on March 8, 2012 in Auburn, Alabama, in which he discussed the knowledge essays by economist Friedrich A. von Hayek, the concept of capital theory and the w......The article presents a speech by Professor Nicolai J. Foss of Copenhagen Business School, delivered at the Austrian Scholars Conference held on March 8, 2012 in Auburn, Alabama, in which he discussed the knowledge essays by economist Friedrich A. von Hayek, the concept of capital theory...... and the works of Hayek on political philosophy and cultural evolution....

  12. Multi-step Monte Carlo calculations applied to nuclear reactor instrumentation - source definition and renormalization to physical values

    Energy Technology Data Exchange (ETDEWEB)

    Radulovic, Vladimir; Barbot, Loic; Fourmentel, Damien; Villard, Jean-Francois [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 St Paul-Lez-Durance, (France); Snoj, Luka; Zerovnik, Gasper [Jozef Stefan Institute, Reactor Physics Department, Jamova cesta 39, SI-1000 Ljubljana, (Slovenia); Trkov, Andrej [IAEA, Vienna International Centre, PO Box 100, A-1400 Vienna, (Austria)

    2015-07-01

    were recently irradiated in the Jozef Stefan Institute TRIGA Mark II reactor in Ljubljana, Slovenia, and provides recommendations on how they can be overcome. The paper concludes with a discussion on the renormalization of the results from the second step calculations, to obtain accurate physical values. (authors)

  13. Guido von Pirquet: Austrian pioneer of astronautics

    Science.gov (United States)

    Sykora, F.

    1977-01-01

    The works of Guido von Pirquet, Austrian pioneer of rocketry, were assessed. Major emphasis was given to Pirquet's calculation of the route to Venus which in fact was followed by the first Russian rocket to Venus. Of interest also is Pirquet's valuable construction of a space station and his analysis of interstellar space flight.

  14. The Austrian x red pine hybrid

    Science.gov (United States)

    W. B. Critchfield

    1963-01-01

    The genetic improvement of red pine (Pinus resinosa Ait.) presents tree breeders with one of their most difficult problems. Not only is this valuable species remarkably uniform, but until 1955 it resisted all attempts to cross it with other pines. In that year red pine and Austrian pine (P. nigra var. austriaca [...

  15. The Austrian Toxoplasmosis Register, 1992-2008.

    Science.gov (United States)

    Prusa, Andrea-Romana; Kasper, David C; Pollak, Arnold; Gleiss, Andreas; Waldhoer, Thomas; Hayde, Michael

    2015-01-15

    We aimed to determine the incidence of primary gestational infections with Toxoplasma gondii and congenital toxoplasmosis in Austria, a country with a nationwide prenatal serological screening program since 1974. We analyzed retrospective data from the Austrian Toxoplasmosis Register of pregnant women with Toxoplasma infection and their offspring with births between 1992 and 2008, identified by the prenatal mandatory screening program. Treatment was administered to women from diagnosis of a Toxoplasma infection until delivery. Infected infants were treated up to 1 year of life routinely. Clinical manifestations in infected infants were monitored at least for 1 year and documented in the register. The Austrian Toxoplasmosis Register included 2147 pregnant women with suspected Toxoplasma infection. Annually, 8.5 per 10 000 women acquired Toxoplasma infection during pregnancy, and 1.0 per 10 000 infants had congenital toxoplasmosis (13% mean transmission rate). Our data showed that women treated according to the Austrian scheme had a 6-fold decrease in the maternofetal transmission rate compared to women without treatment. Results from the Austrian Toxoplasmosis Register show the efficiency of the prenatal screening program. Our results are of clinical relevance for infants, healthcare systems, and policy makers to consider preventive Toxoplasma screening as a potential tool to reduce the incidence of congenital toxoplasmosis. © The Author 2014. Published by Oxford University Press on behalf of the Infectious Diseases Society of America. All rights reserved. For Permissions, please e-mail: journals.permissions@oup.com.

  16. MATSIM -The Development and Validation of a Numerical Voxel Model based on the MATROSHKA Phantom

    Science.gov (United States)

    Beck, Peter; Rollet, Sofia; Berger, Thomas; Bergmann, Robert; Hajek, Michael; Latocha, Marcin; Vana, Norbert; Zechner, Andrea; Reitz, Guenther

    The AIT Austrian Institute of Technology coordinates the project MATSIM (MATROSHKA Simulation) in collaboration with the Vienna University of Technology and the German Aerospace Center. The aim of the project is to develop a voxel-based model of the MATROSHKA anthro-pomorphic torso used at the International Space Station (ISS) as foundation to perform Monte Carlo high-energy particle transport simulations for different irradiation conditions. Funded by the Austrian Space Applications Programme (ASAP), MATSIM is a co-investigation with the European Space Agency (ESA) ELIPS project MATROSHKA, an international collaboration of more than 18 research institutes and space agencies from all over the world, under the science and project lead of the German Aerospace Center. The MATROSHKA facility is designed to determine the radiation exposure of an astronaut onboard ISS and especially during an ex-travehicular activity. The numerical model developed in the frame of MATSIM is validated by reference measurements. In this report we give on overview of the model development and compare photon and neutron irradiations of the detector-equipped phantom torso with Monte Carlo simulations using FLUKA. Exposure to Co-60 photons was realized in the standard ir-radiation laboratory at Seibersdorf, while investigations with neutrons were performed at the thermal column of the Vienna TRIGA Mark-II reactor. The phantom was loaded with passive thermoluminescence dosimeters. In addition, first results of the calculated dose distribution within the torso are presented for a simulated exposure in low-Earth orbit.

  17. Aeroradiometric conducted by the Austrian police

    International Nuclear Information System (INIS)

    Timal, G.

    2009-01-01

    The Austrian Police has specially trained and equipped radiation protection personnel which are intervention personnel for radiological emergencies, following the law of the Intervention Regulation, BGBl. II Nr. 145/2007. The training which consists of three consecutive courses follows the Intervention Regulation and the Austrian Standard S5207. It is held at the certified Security Academy of the Federal Ministry of the Interior in Traiskirchen near Vienna. As a follow-up training, there are special courses held for the conduction of aeroradiometric measures (radiation measurements by helicopters). All over Austria, the Police have ten aeroradiometric sets at their disposal which can be brought into action within almost no time. The contribution informs about the technics involved, the installation of the system in the helicopter and about the training for the aeroradiometric specialists. Furthermore, practical knowledge from flights conducted at trainings and exercises will be included. (orig.)

  18. Current status of operation and utilization of the Dalat Research Reactor

    International Nuclear Information System (INIS)

    Dien, Nguyen Nhi

    2006-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool-type reactor using the HEU (36% enrichment) WWR-M2 fuel assemblies. It was renovated and upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in the 1st November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analysis, scientific research and training. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for reactor physics and thermal hydraulics experiments. From the first start-up to the end of December 2004, it totaled about 27,253 hrs of operation and the total energy released was about 543 MWd. The first fuel reloading was executed in April 1994 after more than 10 years of operation with 89 fuel assemblies (FA). The 11 new FAs were added in the core periphery, at previous beryllium element locations. After reloading the working configuration of reactor core consisted of 100 FAs. The second fuel reloading was executed in March 2002. The 4 new FAs were added in the core periphery, at previous beryllium element locations. The working configuration of 104 FAs ensured efficient exploitation of the DNRR at nominal power for about 3000 hrs since March 2002. In order to provide excess reactivity for the reactor operation without the need to discharge high burned FAs, in June 2004, the fuel shuffling of the reactor core was done. 16 FAs with low burn-up from the core periphery were moved toward the core center and 16 FAs with high-burn-up from the core center were moved toward the core periphery. This operation provided additional reactivity of about 0.85 β eff that the current reactor configuration using re-shuffled HEU fuel is expected to allow normal operation until June 2006. In 1999, the request of returning to Russia HEU fuels from foreign

  19. The voice of Austrians at CERN

    CERN Multimedia

    2009-01-01

    On 7 May the Austrian Minister for Science announced that, after over 50 years of membership, Austria would withdraw from CERN. By 18 May the Austrian Chancellor had reversed the decision. The Bulletin spoke to some of the Austrian community at CERN about the rollercoaster of events in between. var flash_video_player=get_video_player_path(); insert_player_for_external('Video/Public/Movies/2009/CERN-MOVIE-2009-056/CERN-MOVIE-2009-056-0753-kbps-640x360-25-fps-audio-64-kbps-44-kHz-stereo', 'mms://mediastream.cern.ch/MediaArchive/Video/Public/Movies/2009/CERN-MOVIE-2009-056/CERN-MOVIE-2009-056-Multirate-200-to-753-kbps-640x360-25-fps.wmv', 'false', 533, 300, 'https://mediastream.cern.ch/MediaArchive/Video/Public/Movies/2009/CERN-MOVIE-2009-056/CERN-MOVIE-2009-056-posterframe-640x360-at-10-percent.jpg', '1180837', true, 'Video/Public/Movies/2009/CERN-MOVIE-2009-056/CERN-MOVIE-2009-056-0600-kbps-maxH-360-25-fps-audio-128-kbps-48-kHz-stereo.mp4'); To watch this video in German click here. There was jubil...

  20. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

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

  1. Reactor

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  2. Product Liability: A Neo-Austrian Based Perspective

    NARCIS (Netherlands)

    Folmer, H.; Heijman, W.J.M.; Leen, A.R.

    2002-01-01

    The paper is an exercise in a neo-Austrian based economic analysis of product liability. After a short historical introduction, we take two of the basic premises of Austrian economic thought and see which system of product liability results. If costs are subjective and entrepreneurship is the

  3. Current utilization and long term strategy of the Finnish TRIGA research reactor FiR 1

    International Nuclear Information System (INIS)

    Auterinen, Iiro; Salmenhaara, Seppo

    2008-01-01

    FiR 1 (TRIGA Mark II, 250 kW) has an important international role in the development of boron neutron capture therapy (BNCT) for cancer. The safety and efficacy of BNCT is studied for several different cancers: - primary glioblastoma, a highly malignant brain tumour (since 1999); - recurrent glioblastoma or anaplastic astrocytoma (since 2001); - recurrent inoperable head and neck carcinoma (since 2003). It is one of the few facilities in the world providing this kind of treatments. The successes in the BNCT development have now created a demand for these treatments, although they are given on an experimental basis. Well over 100 patients treated now since May 1999: - at least 1 patient irradiation / week, often 2 (Tuesday and Thursday) - patients are referred to BNCT-treatments from several hospitals, also outside research protocols; - the hospitals pay for the treatment. The FiR 1 reactor has proven to be a reliable neutron source for the BNCT treatments; no patient irradiations have been cancelled because of a failure of the reactor. The BNCT facility has become a center of extensive academic research especially in medical physics. Nuclear education and training continue to play also a role at FiR 1 in the form of university courses and training of nuclear industry personnel. FiR 1 is one of the two sources in Scandinavia for short lived radioisotopes used in tracer studies in industry. The main isotope produced is Br-82 in the form of either KBr or ethylene bromide. Other typical isotopes are Na-24, Ar-41, La-140. The isotopes are used mainly in tracer studies in industry (Indmeas Inc., Finland). Typical activity of one irradiated Br-sample is 20 - 80 GBq; total activity produced in one year is over 3 TBq; the reactor operating time needed for the isotope production is one or two days per week. Accelerator based neutron sources are developed for BNCT. The prospect is that when BNCT will achieve a status of a fully accepted and efficient treatment modality for

  4. Report on the Austrian Mining Conference 1981

    Energy Technology Data Exchange (ETDEWEB)

    Steinmetz, R

    1982-02-01

    The conference took place in Leoben from 19 to 22 May, 1981, under the auspices of the Montanuniversitaet Leoben and the Bergmaennischer Verband of Austria. A total of 14 talks were held, which are summarized in brief. Main topics of the talks concerned prospects of the international coal industry, concepts of Austria' energy supply, coal exploration in Austria, uranium reserves of Austria, development of international coal trade, brown coal deposits of Hungary, aspects of overburden removal in surface mines and of roadway drivage in underground mines, prediction of rock behavior in deep mines, hydraulic salt mining, and protection of an iron ore preparation plant in India by the Austrian VOEST-ALPINE AG. (In German)

  5. Container construction for the Pu-Be source at the Atominstitut Wien

    International Nuclear Information System (INIS)

    Tatlisu Halit

    2003-07-01

    The aim of this study was to construct a neutron source container as small as possible. For this purpose an aluminum container was ordered to reserve the Pu-Be neutron source of the TRIGA Mark-II research reactor at the Atominstitute of Austrian Universities, Vienna. The important point is the shielding of the neutrons according to the radiation protection policy at ATI. Fast neutrons, which emitted from the source, cannot be shielded directly. They have to be moderated by a suitable moderator material and then they can be absorbed using a strong neutron absorber material. The most effective moderators are elements with low atomic number; therefore hydrogen-containing materials are the major component of neutron shielding. As a moderator and absorber material together we have chosen borated polyethylene among the various materials considering its properties. It contains H and C, which are suitable moderator materials and B for neutron absorption. It is important to quickly moderate the neutron to low energy, where it can be absorbed with boron owing to the high absorption cross section. The constructed shielding, which consists of borated polyethylene, was placed into the ordered A1 container. At the end we measured the emitted radiation dose using a neutron counter at different distances from the container. (author)

  6. The Austrian Approach: Entering the World of Children.

    Science.gov (United States)

    Feistritzer, Patricia; Balcerack, Carl

    1979-01-01

    This photo-essay describes a Waldorf School. Developed by Austrian Rudolf Steiner, the Waldorf plan is dedicated to allowing the child a childlike environment. It emphasizes storytelling, creative dramatics, flexibility, improvisation, crafts, and movement. (SJL)

  7. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

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

  8. Greetings from Austrian Radiation Protection Association

    International Nuclear Information System (INIS)

    Hajek, M.; Brandl, A.

    2015-01-01

    Austrian Radiation Protection Association (OVS) share with others a long-standing tradition of common endeavours and close collaboration. We have been and are able to influence the European radiation protection environment and IRPA initiatives and policies. We are intrigued by the breadth and comprehensive nature of the symposium programme, covering the most important sub-fields in our profession, and spanning topics from radiation dosimetry to radiobiology, from instrumentation and measurement to radioecology, and from radiation protection for workers and in medicine to our professional responsibilities towards the general public. These topics are timeless and current, providing testimony to the fact that the science of radiation protection is not exhausted. Novel applications of ionizing and non-ionizing radiation, including new modalities in the fields of medical therapy and diagnosis, a resurgence of nuclear energy generation in some parts of the globe, combined with increased efforts for decontamination and decommissioning of existing sites and facilities, they are all attest to the continued need for further research and our professional input and discussion. The national radiation protection associations will have a role to play in both, the advocacy of increased efforts to educate and train our future professionals and the retention of those professionals in our field.

  9. Natural radionuclides in Austrian bottled mineral waters

    International Nuclear Information System (INIS)

    Gabriele Wallner; Tania Jabbar

    2010-01-01

    All commercially available mineral waters of Austrian origin were investigated with regard to the natural radionuclides 228 Ra, 226 Ra, 210 Pb, 210 Po, 238 U and 234 U. From 1 to 1.5 L of sample the nuclides were extracted and measured sequentially: the radium isotopes as well as 210 Pb were measured by liquid scintillation counting after separation on a membrane loaded with element-selective particles (Empore Radium Disks), 210 Po was determined by α-particle spectroscopy after spontaneous deposition onto a copper planchette and uranium was determined also by α-particle spectroscopy after anion separation and microprecipitation with NdF 3 . The calculated committed effective doses for adults, teens and babies were compared to the total indicative dose of 0.1 mSv/year given in the EC Drinking Water Directive. The dominant portion of the committed effective dose was due to 228 Ra. Highly mineralised waters showed also higher 226 Ra and 228 Ra levels. (author)

  10. [Fight against epidemics: Austrian prisoners in Troyes].

    Science.gov (United States)

    Hetzel, Géraldine

    2014-01-01

    The victories near Ulm and Elchingen, where the Napoleonic army took 60000 prisoners between 15th and 20th of October 1805, lead to the arrival at Troyes (county "Aube") of nearly 2000 Austrian soldiers to be held inside former monasteries among whose, mainly the Jacobinians casern where more than half of them stayed. At the beginning of 1806, the government sent the epidemics medical practitioner Dr Desgenettes on an inspection tour to control the state of health of the populations of places where foreign prisoners were held, which lead him through several counties of the North-eastern part of France, where he surveyed several diseases ranging from all kinds offevers up to dysentery, scabies or gangrenes. With the means of acid fumigations invented by the chemist Guyton Morveau from Dijon, the authorities took care of combating and preventing the epidemics in the caserns. As soon as October 1805, the epidemics medical practitioner Dr Pigeotte from Troyes wrote to the county governor his observations recommending a better diet, airing of the rooms and also calls to take some exercise. All these precepts showed an astonishing modernity.

  11. HORA - an Austrian platform for natural hazards

    Science.gov (United States)

    Hlatky, T.

    2009-04-01

    HORA - an Austrian platform for natural hazards as a new way in risk communication One initiatives launched in Austria demonstrate that public participation not only bears the risk of a partial transfer of responsibility by the authorities; it may above all prepare the ground for entirely new approaches and create new links. The recent installation of the first internet risk zoning system in Austria underscores the importance of involving private parties in natural disaster protection. This public-private partnership (PPP) between the Federal Ministry of Agriculture, Forestry, Environment and Water Management (BMLFUW) and the Austrian Insurance Association (VVO) was launched in the wake of the 2002 flood disaster. The first project phase, the Austrian flood risk zoning system called HORA (screenshot see fig. 1), has now been accessible on the Web since 1st June 2006. In accordance with a risk partnership concluded between federal government, insurance companies and private parties, the project initiators seek to offer the public a preliminary risk assessment tool for evaluation of their home, industrial enterprise, of infrastructure. Digital risk maps shall provide information on 30-year, 100-year and 200-year flood events as they occur alongside the 26.000-km-long domestic river network. The probability with which a certain block of land is immersed in water during a flood event can be calculated by means of hydraulic engineering methods. These have traditionally relied on statistical figures, which are known to be very inaccurate, especially when major events such as flooding are concerned. The Vienna University of Technology (TU) (Institute of Hydraulic and Water Resources Engineering) has dedicated many years to developing more accurate, process oriented risk assessment techniques. The starting points was to identify different flood-triggering processes and to divide them into specific categories as long-duration rainfalls, short-duration rainfalls, storms

  12. Austrian Economics and the Transaction Cost Approach to the Firm

    Directory of Open Access Journals (Sweden)

    Nicolai J. Foss

    2009-10-01

    Full Text Available As the transaction cost theory of the firm was taking shape in the 1970s, another important movement in economics was emerging: a revival of the ‘Austrian’ tradition in economic theory associated with such economists as Ludwig von Mises and F. A. Hayek (1973; Dolan, 1976; Spadaro, 1978. As Oliver Williamson has pointed out, Austrian economics is among the diverse sources for transaction cost economics. In particular, Williamson frequently cites Hayek (e.g., Williamson, 1985, p. 8; 1991, p. 162, particularly Hayek’s emphasis on adaptation as a key problem of economic organisation (Hayek, 1945. Following Williamson’s lead, a reference to Hayek’s ‘The Use of Knowledge in Society’ (Hayek, 1945 has become almost mandatory in discussions of economic organisation (e.g., Ricketts, 1987, p. 59; Milgrom and Roberts, 1992, p. 56; Douma and Schreuder 1991, p. 9. However, there are many other potential links between Austrian and transaction cost economics that have not been explored closely and exploited.This article argues that characteristically Austrian ideas about property, entrepreneurship, economic calculation, tacit knowledge, and the temporal structure of capital have important implications for theories of economic organisation, transaction cost economics in particular. Austrian economists have not, however, devoted substantial attention to the theory of the firm, preferring to focus on business-cycle theory, welfare economics, political economy, comparative economic systems, and other areas. Until recently the theory of the firm was an almost completely neglected area in Austrian economics, but over the last decade, a small Austrian literature on the firm has emerged. While these works cover a wide variety of theoretical and applied topics, their authors share the view that Austrian insights have something to offer students of firm organisation.

  13. Research activities at the TRIGA Mainz

    International Nuclear Information System (INIS)

    Eberhardt, K.; Trautmann, N.

    2002-01-01

    The TRIGA Mark II reactor of the Mainz University became first critical on August 3, 1965. It can be operated in the steady state mode with a maximum power of 100 kW and in the pulse mode with a peak power of 250 MW. The TRIGA Mainz is mainly used for neutron activation analysis, isotope production, basic research in nuclear chemistry and nuclear physics as well as for education and training

  14. Short-time activation analysis with and without a 6LiD converter

    International Nuclear Information System (INIS)

    Grass, F.; Holzner, H.; Ritschel, A.; Ismail, S.S.; Dorner, J.

    1994-01-01

    Neutron activation analysis (NAA) at various irradiation and measurement systems of the Institute's TRIGA mark II reactor provides a choice of sample oriented analyzing systems. This is demonstrated on the analysis of waste products, on an analysis of the phase content of a high-T c superconductor and on a fluorine analysis in a standard reference material. (author) 17 refs.; 4 figs.; 5 tabs

  15. Radioactive slurry waste treatment (1) - flucculant dose effects on filtration

    International Nuclear Information System (INIS)

    Jung, K. H.; Park, S. K.; Jung, W. S.; Baek, S. T.; Jung, K. J.

    1999-01-01

    During the past four decades, the radioactive slurry liquid waste(RSLW) is produced by operation of TRIGA Mark - II and III research reactors, producing radioisotopes and studying on RI utilization. Vacuum filtration of RSLW and flocculated RSLW with cationic, anionic and nonionic flocculants has been investigated. Test results show that critical dose of flocculant is obtained by the estimation of settling rate, cake moisture content and specific cake residence

  16. The {sup 99m}Tc generator using poly zirconium chloride (PZC)

    Energy Technology Data Exchange (ETDEWEB)

    Wan Awang, Wan Anuar; Dahalan, Rehir; Kasim, Shaaban [Medical Technology Div., Malaysian Inst. for Nuclear Technology Research (MINT), Selangor (Malaysia)

    1998-10-01

    The {sup 99m}Tc generator system has been prepared using poly zirconium chloride (PZC) to replace alumina (Al{sub 2}O{sub 3}) as a adsorbent. The Mo-98 (MoO{sub 3}) was irradiated using our 1 MW TRIGA MARK II research reactor. The amount of Mo-99 adsorbed to the PZC has been studied and the yield from the elution was about 20%. (author)

  17. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

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

  18. Substitution of the old console with a fully computerized one. Major maintenance and enhancements of the ventilation and air conditioning system of the reactor building. Research activities at the TRIGA L.E.N.A. plant in Pavia, Italy

    International Nuclear Information System (INIS)

    Orvini, E.; Piazzoli, A.; Borio, A.

    2008-01-01

    The TRIGA Mark II reactor of the University of Pavia was operated in the last two years on a routine basis accomplishing different purposes: - Development of B.N.C.T. for diffused tumours of liver; - Neutron activation analysis in matrix of geochemistry, archaeology and environment interest; - Electron spin resonance (ESR) study of radical processes; - Study of trace elements impact in environmental matrix and human health; - High purity control on electronic samples-microchips; - Fast neutron radiation damage investigation; - Certification of standard reference materials and data quality assurance by neutron activation analysis; - Age evaluation by Ar-K method in geological matrix; - Trace elements determination for provenience studies in archaeology; - Basic experiments on fission of Am-242 layers for the space nuclear engine project; - In field search of explosive using prompt gamma emission induced by neutron capture on nitrates. In the period of time between July 1998 and June 2000 the reactor was operated at full power (i.e. 250 kW) for a total amount of 1375 hours. The total fuel element burn-up was 15.07 MWD. During this period of time two major upgrading activities were planned: the installation of a new Instrumentation and Control System (ICS) for the reactor and the installation of a new Air Conditioning and Filtering System (ACFS) for the reactor building. The new ICS is a microprocessor-based design, incorporating the use of one logarithmic wide range neutron flux monitoring channel (NLW-1000), two current mode neutron monitoring safety channels (NP-1000 and NPP-1000) and a linear multi-range neutron flux monitoring channel (Keithley 485). The ICS configuration was personalized by General Atomic according to the requirements and to the technical prescriptions of the Pavia reactor, especially for what concerns the SCRAM inputs and the detectors architecture. Besides, since one the two safety channels, the NPP-1000, has been developed as an advanced

  19. Attitudes of Austrian Psychotherapists Towards Process and Outcome Monitoring.

    Science.gov (United States)

    Kaiser, Tim; Schmutzhart, Lisa; Laireiter, Anton-Rupert

    2018-03-08

    While monitoring systems in psychotherapy have become more common, little is known about the attitudes that mental health practitioners have towards these systems. In an online survey among 111 Austrian psychotherapists and trainees, attitudes towards therapy monitoring were measured. A well-validated questionnaire measuring attitudes towards outcome monitoring, the Outcome Measurement Questionnaire, was used. Clinicians' theoretical orientations as well as previous knowledge and experience with monitoring systems were associated with positive attitudes towards monitoring. Possible factors that may have led to these findings, like the views of different theoretical orientations or obstacles in Austrian public health care, are discussed.

  20. Accredited training on radiation protection for the Austrian police

    International Nuclear Information System (INIS)

    Timal, G.

    2009-01-01

    In Austria, radiological emergencies are handled following the Intervention Regulation, in force since 2007. This regulation also defines duration and content for the training of radiation protection personnel, taking advantage of the standard OeNORM S 5207 published in 2005. Radiation protection personnel of the Austrian police are trained at the Federal Security Academy in Traiskirchen near Vienna. The Federal Security Academy is a training centre certified by the Austrian Standards Institute. The poster describes the modular organisation of the training and its duration and content as well as the further trainings available to the radiation protection personnel of the Police. (orig.)

  1. An Austrian framework for PET quality control

    International Nuclear Information System (INIS)

    Nicoletti, R.; Dobrozemsky, G.; Minear, G.; Bergmann, H.

    2002-01-01

    Full text: The European patient protection directive (97/43 EURATOM) requires regular routine quality control (QC) of PET imaging devices. Since no standards were available covering this area and in order to comply with the directive a joint working party of the Austrian societies of nuclear medicine and of medical physics have developed a set of procedures suitable for both dedicated PET scanners and gamma cameras operating in coincidence mode (GCPET). The routine procedures proposed include both manufacturer recommended procedures and tests for specific parameters and calibration procedures. Wherever possible, procedures adapted or derived from NEMA standards publication NU 2-2001 were used to permit direct comparison with specified parameters of image quality. For dedicated PET scanners the most important procedures are the checking of detector sensitivities and the attenuation calibration scan. With full ring scanners the attenuation calibration scan is a blank scan, with partial ring devices a special attenuation calibration phantom has to be used. Test protocols are specific to manufacturer and scanner type. They are usually performed automatically overnight. In addition, some instruments require special calibrations, e.g. gain adjustments or coincidence timing calibration. GCPET procedures include the frequent assessment in coincidence mode of detector uniformity, energy resolution and system sensitivity. Common to both dedicated PET and GCPET are the regular quarterly assessment of tomographic spatial resolution and the calibration of the system for quantitative measurements. As a total performance test for both systems assessment of image quality following NU 2-2001 was included, to be carried out after major system changes or repairs. The suite of QC procedures was tested on several dedicated PET and GCPET systems including all major manufacturers' systems. Due to missing hardware or software not all tests could be performed on all systems. Some of the

  2. Avian Plasmodium in Eastern Austrian mosquitoes.

    Science.gov (United States)

    Schoener, Ellen; Uebleis, Sarah Susanne; Butter, Julia; Nawratil, Michaela; Cuk, Claudia; Flechl, Eva; Kothmayer, Michael; Obwaller, Adelheid G; Zechmeister, Thomas; Rubel, Franz; Lebl, Karin; Zittra, Carina; Fuehrer, Hans-Peter

    2017-09-29

    Insect vectors, namely mosquitoes (Diptera: Culicidae), are compulsory for malaria parasites (Plasmodium spp.) to complete their life cycle. Despite this, little is known about vector competence of different mosquito species for the transmission of avian malaria parasites. In this study, nested PCR was used to determine Plasmodium spp. occurrence in pools of whole individuals, as well as the diversity of mitochondrial cytochrome b gene sequences in wild-caught mosquitoes sampled across Eastern Austria in 2013-2015. A total of 45,749 mosquitoes in 2628 pools were collected, of which 169 pools (6.43%) comprising 9 mosquito species were positive for avian Plasmodium, with the majority of positives in mosquitoes of Culex pipiens s.l./Culex torrentium. Six different avian Plasmodium lineages were found, the most common were Plasmodium vaughani SYAT05, Plasmodium sp. Linn1 and Plasmodium relictum SGS1. In 2014, mosquitoes of the Culex pipiens complex were genetically identified and Culex pipiens f. pipiens presented with the highest number of avian Plasmodium positives (n = 37; 16.74%). Despite this, the minimum infection rate (MIR) was highest in Culex torrentium (5.36%) and Culex pipiens f. pipiens/f. molestus hybrids (5.26%). During 2014 and 2015, seasonal and annual changes in Plasmodium lineage distribution were also observed. In both years P. vaughani SYAT05 dominated at the beginning of the sampling period to be replaced later in the year by P. relictum SGS1 (2014) and Plasmodium sp. Linn1 (2015). This is the first large-scale study of avian Plasmodium parasites in Austrian mosquitoes. These results are of special interest, because molecular identification of the taxa of the Cx. pipiens complex and Cx. torrentium enabled the determination of Plasmodium prevalence in the different mosquito taxa and hybrids of this complex. Since pools of whole insects were used, it is not possible to assert any vector competence in any of the examined mosquitoes, but the results

  3. THE HUNGARIAN CRISIS: AN AUSTRIAN SCHOOL EXPLANATION

    Directory of Open Access Journals (Sweden)

    Andras Toth

    2013-07-01

    Full Text Available The Hungarian model was heralded as one of the most successful post-socialist way of integration into the globalised world economy and European economic area in the nineties. Currently, Hungary is suffering from a full-blown crisis 1996 onwards. Increasingly large number of Hungarians is losing their faith in political parties, institutions, democracy and in market economy. The government, elected in 2010 by supermajority and still enjoying a broad support despite the deepening recession, condemns the development path taken after 1989 and openly rejects the wrong model of the last 20 years. The government intends to build a new economic model following a model, which one can call a model of economic nationalism as the only way out of the crisis. The paper intends to portray, through the case of Hungary, how economy and politics is interconnected, and why political elites are choosing a credit fuelled development path. The paper intends to portray how a credit fuelled growth was induced by politics and ended up in tears. Moreover, the paper describes the consequences of pro-etatist shift in the public sentiment due to the alleged “market-failure”, which was in reality a crisis, at first place, created for political purposes by political means. This article, based on the Austrian business cycle theory, argues that the tragedy of Hungary was that it went through a government inspired spending binge in the first half of the 2000s. The deficit spending of the government was accompanied by the expansion of credit by the commercial banks, mostly denominated in Swiss francs. The combined effect of deficit spending and credit expansion was the build-up of debt and loss of cost competitiveness. The 2008 crisis ended the credit fuelled development path and has started the long and painful period of deleveraging crisis. On the other hand, the Hungarian crisis is a post-Keynesian crisis. It had broken out when the state was already heavily indebted and

  4. 47. annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    Kutschera, W.

    1997-01-01

    This volume contains lectures (short communications) of the 47. symposium of the Austrian Physical Society which had been held at the University of Vienna (Austria) in 1997. The following topics are included: atomic physics, molecular physics, plasma physics, solid state physics, nuclear and particle physics, biophysics, environmental physics, quantum electronics and quantum optics. (Suda)

  5. 45. Annual Convention of the Austrian Physical Society

    International Nuclear Information System (INIS)

    1995-01-01

    This volume contains lectures of the 45 th symposium of the Austrian Physical Society which had been held in Leoben, Austria in 1995. The following topics are included: Atomic physics, molecular physics, plasma physics, solid state physics, nuclear and particle physics, biophysics, environmental physics, quantum electronics and quantum optics. (Suda)

  6. 50. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    Lippitsch, M.E.

    2000-01-01

    The conference held from 25. - 29. 9. 2000 at the University of Graz was elaborated by the Austrian society of physics in the fields of solid state physics, polymers physics, quantum electronics, electrodynamics, optics, nuclear and particle physics, atomic, molecules and plasma physics, acoustics, physics - industry - energy and physics teaching. (botek)

  7. 49. annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    Blatt, R.; Maerk, T.

    1999-01-01

    This volume contains short communications of lectures and poster sessions of the 49th symposium of the Austrian Physical Society which has been held at the University of Innsbruck (Austria) in 1999. The following topics are included: atomic physics, molecular physics, plasma physics, solid state physics, nuclear and particle physics, polymer physics, biophysics, environmental physics, quantum electronics and quantum optics. (Suda)

  8. 40. annual convention 1990 of the Austrian physical society

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Titles and abstracts of the 1990 Convention of the Austrian Physical Society, 17-21 September 1990 at Salzburg, Austria, are given. The topical sections are: 1. Atomic, Molecular- and Plasma Physics; 2. Solid State Physics; 3. Polymer Physics; 4. Nuclear- and Particle Physics; 5. Medical Physics and Biophysics. There are alltogether 193 contributions, 61 thereof of INIS interest

  9. Annual convention 1986 of the Austrian Physical Society

    International Nuclear Information System (INIS)

    1986-01-01

    There are 152 contributions, 58 thereof of INIS interest. The subject matters are indicated by the grouping of contributions into topical sessions on 1) nuclear and particle physics 2) physics of high polymers 3) atomic and plasma physics. There is additionally a session for teachers contimation training and one page informations on the Austrian Physical Society. (G.Q.)

  10. Acidification and Nitrogen Eutrophication of Austrian Forest Soils

    Directory of Open Access Journals (Sweden)

    Robert Jandl

    2012-01-01

    Full Text Available We evaluated the effect of acidic deposition and nitrogen on Austrian forests soils. Until thirty years ago air pollution had led to soil acidification, and concerns on the future productivity of forests were raised. Elevated rates of nitrogen deposition were believed to cause nitrate leaching and imbalanced forest nutrition. We used data from a soil monitoring network to evaluate the trends and current status of the pH and the C : N ratio of Austrian forest soils. Deposition measurements and nitrogen contents of Norway spruce needles and mosses were used to assess the nitrogen supply. The pH values of soils have increased because of decreasing proton depositions caused by reduction of emissions. The C : N ratio of Austrian forest soils is widening. Despite high nitrogen deposition rates the increase in forest stand density and productivity has increased the nitrogen demand. The Austrian Bioindicator Grid shows that forest ecosystems are still deficient in nitrogen. Soils retain nitrogen efficiently, and nitrate leaching into the groundwater is presently not a large-scale problem. The decline of soil acidity and the deposition of nitrogen together with climate change effects will further increase the productivity of the forests until a limiting factor such as water scarcity becomes effective.

  11. 48. annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    Netzer, F.P.

    1998-01-01

    This volume contains short communications of lectures and posters of the 48 th Symposium of the Austrian Physical Society which had been held at the University of Graz (Austria) in 1998. The following topics are included: atomic physics, molecular physics, plasma physics, solid state physics, nuclear and particle physics, polymer physics, biophysics, environmental physics, quantum electronics and quantum optics. (Suda)

  12. Holocaust Studies in Austrian Elementary and Secondary Schools

    Science.gov (United States)

    Mittnik, Philipp

    2016-01-01

    This article presents arguments in support of teaching about the Holocaust and Nazism in Austria at an early age. To accomplish this, Austrian and German elementary school textbooks were analyzed for the amount of content dealing with the Holocaust and Jews; the results showed that since 1980 the amount of content on the Holocaust increased in…

  13. Report 1985 of the Austrian Research Centre Seibersdorf. Abridged version

    International Nuclear Information System (INIS)

    Schwach, G.W.

    1987-01-01

    The report gives a short survey of the work carried out by the Austrian Research Centre Seibersdorf in 1985. The working programme comprises five main areas: Energy and safety; Materials research, isotope and radiation techniques; Measuring techniques and information processing; Environmental protection, health and food; Industrial consulting. (Author)

  14. English, French, Spanish, Italian, Portuguese? Code Choice and Austrian Export

    Science.gov (United States)

    Lavric, Eva; Back, Bernhard

    2009-01-01

    This article deals with how "export oriented Austrian companies effect code choice in their business relationships with customers from Romance language speaking countries". The focus lies on the most widespread Romance languages, therefore on French, Spanish, Italian and Portuguese speaking customers.The question of code choice in export…

  15. Hospital admissions for traumatic brain injury of Austrian residents vs. of visitors to Austria.

    Science.gov (United States)

    Mauritz, Walter; Brazinova, Alexandra; Majdan, Marek; Leitgeb, Johannes

    2014-01-01

    The goal was to compare epidemiology of hospital admissions for traumatic brain injury (TBI) in Austrian residents vs. visitors to Austria. Data on all hospital admissions due to TBI (ICD-10 codes S06.0-S06.9; years 2009-2011) was provided by the Austrian Statistical Office. Data on Austrian population and on tourism (visitor numbers, nights spent) was retrieved from www.statistik.at . Age, sex, mechanism of injury, season and mortality was analysed for Austrian residents vs. visitors. Visitors contributed 3.9% to the total population and 9.2% of all TBI cases. Incidence of hospital admissions was 292/100,000/year in Austrian residents and was 727/100,000/year in visitors. Male:female ratio was 1.39:1 in Austrian residents and 1.55:1 in visitors. Austrian cases were older than visitors' cases (mean age 41 vs. 28 years). Austrian cases were distributed evenly over the seasons, while 75% of the visitors' cases happened during winter and spring. The most frequently observed causes of TBI in Austrian residents were private accidents, while sports caused almost half of the visitors' cases. Hospital mortality was lower in visitors than in Austrian residents (0.8 vs. 2.1%). Sports-related TBI of visitors causes a significant workload for Austrian hospitals. Better prevention is warranted.

  16. Gazing behavior reactions of Vietnamese and Austrian consumers to Austrian wafers and their relations to wanting, expected and tasted liking.

    Science.gov (United States)

    Vu, Thi Minh Hang; Tu, Viet Phu; Duerrschmid, Klaus

    2018-05-01

    Predictability of consumers' food choice based on their gazing behavior using eye-tracking has been shown and discussed in recent research. By applying this observational technique and conventional methods on a specific food product, this study aims at investigating consumers' reactions associated with gazing behavior, wanting, building up expectations, and the experience of tasting. The tested food products were wafers from Austria with hazelnut, whole wheat, lemon and vanilla flavors, which are very well known in Austria and not known in Vietnam. 114 Vietnamese and 128 Austrian participants took part in three sections: The results indicate that: i) the gazing behavior parameters are highly correlated in a positive way with the wanting-to-try choice; ii) wanting to try is in compliance with the expected liking for the Austrian consumer panel only, which is very familiar with the products; iii) the expected and tasted liking of the products are highly country and product dependent. The expected liking is strongly correlated with the tasted liking for the Austrian panel only. Differences between the reactions of the Vietnamese and Austrian consumers are discussed in detail. The results, which reflect the complex process from gazing for "wanting to try" to the expected and tasted liking, are discussed in the context of the cognitive theory and food choice habits of the consumers. Copyright © 2018. Published by Elsevier Ltd.

  17. [Pain care in Austrian health care centers: Questionnaire study on the current status of Austrian pain clinics].

    Science.gov (United States)

    Szilagyi, I-S; Bornemann-Cimenti, H; Messerer, B; Vittinghoff, M; Sandner-Kiesling, A

    2015-12-01

    Pain clinics provide interdisciplinary therapy to treat chronic pain patients and to increase the return-to-work rate. In recent years and due to increased economic pressure in health care, a change in the management of pain in Austrian health care centers has been observed. For the analysis of the current situation, two surveys addressing all Austrian pain clinics were performed. In total, 133 heads of Austrian Anesthesia Departments were interviewed online and personally. The data from the first interview were confirmed by an additional telephone survey that was performed by one anesthetist per Austrian state (n = 9). Currently, 44 Austrian pain clinics are active. During the last 5 years, 9 pain clinics closed. Adding the current active pain clinics together, they represent a total of 17.5 full-time-operated clinics. The most common reasons for closing the pain clinics were lack of personnel (47%), lack of time resources (26%), lack of space resources (11%), and financial difficulties (11%). A reduction of >50% of operating hours during the last 3 years was reported by 9 hospitals. The reasons for not running a pain clinic were lack of personnel (36%), lack of time (25%) and department too small (16%). Estimates between actual and required clinics indicate that 49.5 full-time-operating pain clinics are lacking in Austria, resulting in 74% of the Austrian chronic pain patients not receiving interdisciplinary pain management. Our survey confirmed the closure of 9 pain clinics during the last 5 years due to lack of personnel and time. Pain clinics appear to provide the simplest economic saving potential. This development is a major concern. Although running a pain clinic seems to be expensive at the first sight, it reduces pain, sick leave, complications, and potential legal issues against health care centers, while simultaneously increasing the hospital's competitiveness. Our results show that 74% of Austrian chronic pain patients do not have access to an

  18. Post-irradiation examination of HTR-fuel at the Austrian Research Centre Seibersdorf Ltd

    International Nuclear Information System (INIS)

    Reitsamer, G.; Proksch, E.; Stolba, G.; Strigl, A.; Falta, G.; Zeger, J.

    1985-01-01

    Austrian R and D activities in the HTR-field reach back almost to the beginning of this advanced reactor line. For more than 20 years post-irradiation examination (PIE) of HTR-fuel has been performed at the laboratories of the Austrian Research Centre Seibersdorf Ltd. (OEFZS) (formerly OESGAE) and a high degree of qualification has been achieved in the course of that time. Most of the PIE-work has been carried out by international cooperation on contract basis with the OECD-DRAGON-project and with KFA-Juelich (FRG). There has also been some collaboration with GA (USA), Belgonucleaire and others in the past. HTR-fuel elements contain the fissile and fertile materials in form of coated particles (CPs) which are embedded in a graphite matrix. Because of this special design it has been necessary from the very beginning of the PIE work up to now to develop new methods (i.e. fuel element disintegration methods, chlorine gas leach, single particle examination techniques...) as well as to adapt and improve already existing methods (i.e. gamma spectrometry, mass-spectrometry, optical methods...). The main interests on PIE-work at Seibersdorf are concentrated on particle performance, fission product distribution and the 'free' Uranium content (contamination and broken particles) of the fuel elements (fuel spheres or cylindrical compacts). A short compilation of the applied methods and of available instrumental facilities is given as follows: deconsolidation of fuel elements; equipment for electrochemical deconsolidation; examinations and measurements of graphite and electrolyte samples; examination of coated particles; single particle examinations

  19. Post-irradiation examination of HTR-fuel at the Austrian Research Centre Seibersdorf Ltd

    Energy Technology Data Exchange (ETDEWEB)

    Reitsamer, G; Proksch, E; Stolba, G; Strigl, A; Falta, G; Zeger, J [Department of Chemistry, Austrian Research Centre Seibersdorf Ltd., Seibersdorf (Austria)

    1985-07-01

    Austrian R and D activities in the HTR-field reach back almost to the beginning of this advanced reactor line. For more than 20 years post-irradiation examination (PIE) of HTR-fuel has been performed at the laboratories of the Austrian Research Centre Seibersdorf Ltd. (OEFZS) (formerly OESGAE) and a high degree of qualification has been achieved in the course of that time. Most of the PIE-work has been carried out by international cooperation on contract basis with the OECD-DRAGON-project and with KFA-Juelich (FRG). There has also been some collaboration with GA (USA), Belgonucleaire and others in the past. HTR-fuel elements contain the fissile and fertile materials in form of coated particles (CPs) which are embedded in a graphite matrix. Because of this special design it has been necessary from the very beginning of the PIE work up to now to develop new methods (i.e., fuel element disintegration methods, chlorine gas leach, single particle examination techniques...) as well as to adapt and improve already existing methods (i.e. gamma spectrometry, mass-spectrometry, optical methods...). The main interests on PIE-work at Seibersdorf are concentrated on particle performance, fission product distribution and the 'free' Uranium content (contamination and broken particles) of the fuel elements (fuel spheres or cylindrical compacts). A short compilation of the applied methods and of available instrumental facilities is given as follows: deconsolidation of fuel elements; equipment for electrochemical deconsolidation; examinations and measurements of graphite and electrolyte samples; examination of coated particles; single particle examinations.

  20. Asymmetric Mutual Social Perception of Austrians and Germans: A Social Identity Approach Assessing Implicit and Explicit Attitudes

    Directory of Open Access Journals (Sweden)

    Walter Renner

    2014-07-01

    Full Text Available Whereas Austrians tend to perceive Germans as "competent but cold", Germans tend to see Austrians as "incompetent but nice" in the sense of Fiske's Stereotype Content Model. With respect to the unequal distribution of power between Austria and Germany, which outnumbers Austria by approximately the tenfold population, Social Identity Theory (SIT predicts that Austrians will tend to devalue Germans, attempting to preserve their self-esteem and cultural identity, whereas Germans will perceive Austrians more positively. We tested this expectation with N = 31 Austrian and N = 49 German students at an Austrian university. Our hypotheses of asymmetrical mutual attitudes and massive devaluation of Germans by Austrians were confirmed by the Implicit Association Test, whereas on adjective lists as an explicit measure, Austrians described Germans more favourably, obviously out of a desire not to appear prejudiced. The results support SIT and have important implications for the development of Austrian academic education.

  1. Austrian Transition to Open Access“ 2017–2020

    Directory of Open Access Journals (Sweden)

    Bauer, Bruno

    2017-12-01

    Full Text Available In December the higher education structural funds project (Hochschulraumstrukturmittelprojekt “Austrian Transition to Open Access (AT2OA“ was authorised by the Austrian Federal Ministry of Science, Research and Economy. The 21 public universities cooperate on this project running from 2017 to 2020 in order to promote open access through concerted measures. Constitutive on OANA’s “suggestions for the implementation of Open Access in Austria” published in 2015 four subprojects have been developed. These subprojects’ main focuses are drafting an expert’s report about the financial impact of a total adjustment to open access on a national and institutional basis, the extension of existing consortium licences with an open access component, establishment of an open access publishing fund as well as the promotion of open access monographs and suitable open access infrastructures.

  2. Austrian Security Strategy: Need For Reformulation Due To Security Developments

    Science.gov (United States)

    2016-02-14

    accession to the North Atlantic Treaty Organization (NATO) as an option. Under the Austrian Constitution , the federal government wanted to maintain the...the Middle East and Africa completely overwhelmed the police at the border crossing between Austria and Hungary and Slovenia . On 14 September 2015...Hungary, Croatia, and Slovenia .33, 34, 35 At the end of October 2015 refugees broke through the barriers several times at the border crossing point

  3. Seasonality in the Austrian Economy: Common Seasonals and Forecasting

    OpenAIRE

    Kunst, Robert M.

    1992-01-01

    Abstract: Seasonal cointegration generalizes the idea of cointegration to processes with unit roots at frequencies different from 0. Here, also the dual notion of common trends, "common seasonals", is adopted for the seasonal case. Using a five-variable macroeconomic core system of the Austrian economy, it is demonstrated how common seasonals and seasonal cointegrating vectors look in practice. Statistical tests provide clear evidence on seasonal cointegration in the system. However, it is sh...

  4. Austrian Economics - The Ultimate Achievement of an Intellectual Journey

    Directory of Open Access Journals (Sweden)

    Pascal Salin

    2009-01-01

    Full Text Available In this lecture delivered November 2008 on the occasion of the presentation of the Mises Institute’s Gary G. Schlarbaum Prize for lifetime achievement in the cause of liberty, Professor Salin discusses his discovery of Austrian economics and his involvement in “the world of individual liberty,” and draws various lessons from his intellectual journey. The coherence of Austrian economics appealed to Salin—it is not a patchwork of partial theories, but a logical process of thought founded on realistic assumptions about individual action. Salin also discusses differences between the Chicago and Austrian approaches, and his views about monetary systems.The financial crisis beginning in late 2008 is not a crisis of capitalism, but of state intervention, caused by the expansionary monetary policy of the Fed. Capitalism is the solution, not the cause. There is no need to create money. There is never any balance of payments problem. What is required is tax systems more friendly to capital accumulation, a decrease in the role of the state, the end of monetary policy and, if possible, the disappearing of central banks and the IMF.

  5. Current status of radioactive waste management from nuclear applications in Korea

    International Nuclear Information System (INIS)

    Kwan Sik Chun

    1997-01-01

    Korea has been in operation of nuclear research reactor(s) since the first research reactor, TRIGA MARK-II type, started to operate in 1965. The third research reactor, HANARO, has begun to operate since 1995 while other research reactors have been shut down for their decommissioning and will be dismantled in near future. The RI application wastes have been collected and stored at the Nuclear Environment Technology Institute (NETEC) separately from the operational wastes of nuclear power plant (NPP) which are being stored at on-site storage of each NPP. 10 refs, 2 figs, 4 tabs

  6. State aid in the Austrian electricity industry law

    International Nuclear Information System (INIS)

    Rehulka, J.

    2009-01-01

    The present work deals with the existence of State aid in the Austrian electricity industry and focuses on three selected areas of the Austrian legal system, which are examined for their compatibility with Community law. Subject of the first part of this work is a representation of the article 87 ff Treaty of Rome and its impact on Austrian provisions on the promotion of electricity from renewable energies or on the promotion of cogeneration energy. In this context, the first principles of the European state aid law and in particular the European Court are presented regarding the existence of State aid. Here, the Rsp of the Court in connection with the use of State resources in the Rs PreussenElektra Stardust Marine and Pearle is paid in connection with para-fiscal levies special attention. The evaluation of the Austrian support model is based on PreussenElektra, Stardust Marine and Pearle. Then the system of green electricity production in Austria represented. In addition to the Community law principles (green power directive, frameworks and guidelines for environmental aid) is here in particular the 'Oekostromgesetz' and treated it's novellas. It is an intensive discussion with the Commission's decisions on the compatibility of the green power and CHP funding and the funding of the countries with state aid rules. As part of this analysis is to attempt a classification of the Commission's practice in the Community legal system. The second part of the work deals with the determination of absorbed. System utilization rates and their distribution to the network operator. After a presentation of the Community legislation (EC regulations, the internal electricity market directives) and Rsp of the European Court of Justice (Case ADBHu, Ferring, Altmark Trans) to services of general economic interest is first attempted to determine the presence of these services in the 216 Austrian legislation. Here, the question will be, entrusted with services of general economic

  7. Overview on neutron beam industry-focused strategic research in Malaysia

    International Nuclear Information System (INIS)

    Abdul Aziz Mohamed; Razali Kassim; Abdul Jalil Abdul Hamid; Azali Muhammad; Muhammad Rawi Mohd Zain; Azhar Azmi

    2002-01-01

    The TRIGA MARK II research reactor (RTP) at the Malaysian Institute for Nuclear Technology Research (MINT) was commissioned in July 1982. RTP is a 1 MW steady state reactor which being used for reactor training and research related to neutron. Since then various works have been performed to utilise the neutrons produced from this steady state reactor. Projects undertaken are the development and utilization of the neutron radiography (myNR) and small angle neutron scattering (mySANS) facilities. This poster highlights the recent status the above neutron beam facilities and their application in materials science and technology research and education. (Author)

  8. Nuclear analytical techniques with neutron beams at the Univ. of Texas at Austin

    International Nuclear Information System (INIS)

    Uenlue, K.; Wehring, B.W.

    1996-01-01

    Neutron beams produced by nuclear research reactors can be used for analytical chemical analysis by measuring nuclear radiation produced by neutron capture. Prompt gamma activation analysis (PGAA) and neutron depth profiling (NDP) are two such analytical techniques. For the last three decades, these techniques have been applied at a number of research reactors around the world. Within the last 4 yr, we have developed NDP and PGAA facilities at The University of Texas at Austin research reactor, a 1-MW TRIGA Mark II reactor. Brief descriptions of the facilities and summaries of activities for these analytical techniques at the University of Texas at Austin are provided in this paper

  9. Some remarks on the Austrian radiation protection legislation

    International Nuclear Information System (INIS)

    Vetter, H.

    1979-01-01

    Some of the provisions of the Austrian Radiation Protection Law and Radiation Protection Ordinance differ from those recommended by ICRP and IAEO. This is particularly true for the definition of working conditions, the categorization of radiation areas and the classification of radiation workers. It is suggested that the responsible authorities when considering a revision of the legislation in the light of ICRP 26 and the revised IAEA Basic Safety Standards, also study the desirability of adapting the currently applicable provisions to the universally accepted international norms. (Auth.)

  10. Emission factors of Austrian industry production and international comparison. Final report

    International Nuclear Information System (INIS)

    Turi, K.

    1997-05-01

    During the last few years a number of measures have been implemented in the Austrian industries to reduce air pollution and energy use. Therefore specific emissions in the various sectors were changed considerably during this period. The aim of this research project was to better characterize air pollutant emissions of the Austrian industry. Emission data as measured by the Austrian industry was compared with published emission factors from international literature. The results show that the emission factors of the Austrian industry are generally lower than literature emission factors. This is because on the one hand many older data from the literature do not reflect current state of the knowledge, and on the other hand because emission reduction measures and new technologies were introduced in the Austrian industry. (author)

  11. 4th February 2011 - Austrian Academy of Sciences President H. Denk visiting CMS underground area with Collaboration Spokesperson G. Tonelli, Austrian Academy of Sciences Secretary General A. Suppan, CERN Head of International Relations F. Pauss and Director, High Energy Physics Laboratory, Austrian Academy of Sciences C Fabjan.

    CERN Multimedia

    Maximilien Brice

    2011-01-01

    4th February 2011 - Austrian Academy of Sciences President H. Denk visiting CMS underground area with Collaboration Spokesperson G. Tonelli, Austrian Academy of Sciences Secretary General A. Suppan, CERN Head of International Relations F. Pauss and Director, High Energy Physics Laboratory, Austrian Academy of Sciences C Fabjan.

  12. Measurement of neutron diffusion length in heavy concrete

    International Nuclear Information System (INIS)

    Krejci, D.

    2007-04-01

    Using an aluminium sampler filled with heavy concrete the neutron diffusion length was determined, measuring thermal and fast neutrons over the whole beam hole with various threshold detectors using gold samples. These calculations should describe the neutron distribution in the whole concrete shield of the reactor and contribute to the investigation of the activation of the concrete shield using reactor parameters like operating time, power and neutron flux. Instrumentation, activation and positioning of the samples in the beam hole of the TRIGA Mark II reactor are described. (nevyjel)

  13. Two dimensional burn-up calculation of TRIGA core

    International Nuclear Information System (INIS)

    Persic, A.; Ravnik, M.; Slavic, S.

    1996-01-01

    TRIGLAV is a new computer program for burn-up calculation of mixed core of research reactors. The code is based on diffusion model in two dimensions and iterative procedure is applied for its solution. The material data used in the model are calculated with the transport program WIMS. In regard to fission density distribution and energy produced by the reactor the burn-up increment of fuel elements is determined. In this paper the calculation model of diffusion constants and burn-up calculation are described and some results of calculations for TRIGA MARK II reactor are presented. (author)

  14. 69 The Multicultural Education in Bucovina during the Austrian Domination

    Directory of Open Access Journals (Sweden)

    Vasile Baltag

    2014-12-01

    Full Text Available In 1775, the territory of Bucovina became part of the Habsburg monarchy and it stayed like that for 143 years. All throughout this period when the Romanians lived here next to Ukrainians, Germans, Jews and other nationalities, the Austrian government took into consideration their need for culture, which resulted in the development of a multicultural teaching system. This implied that the languages of teaching in the Bukovinian schools were: Latin, Greek, Romanian, Ukrainian and, more often than not, German. Although the weighty presence of the German language in the academic institutions limited the number of young Romanians in schools, the teaching in German enabled the access of the Bukovinian students to the great European universities from Vienna, Salzburg, Lemberg, Kraków or Prague, before the founding of the Chernivtsi University (1875. Thus, beyond the negative aspects of the separation of this territory from Romania, the Austrian occupation represented an effervescent period from a cultural viewpoint, which lent a specific identity to the teaching system in Bukovina.

  15. Radiation dosimetry and standards at the austrian dosimetry laboratory

    International Nuclear Information System (INIS)

    Leitner, A.

    1984-10-01

    The Austrian Dosimetry Laboratory, established and operated in cooperation between the Austrian Research Center Seibersdorf and the Federal Office of Metrology and Surveying (Bundesamt and Eich- und Vermessungswesen) maintains the national primary standards for radiation dosimetry. Furthermore its tasks include routine calibration of dosemeters and dosimetric research. The irradiation facilities of the laboratory comprise three X-ray machines covering the voltage range from 5 kV to 420 kV constant potential, a 60 Co teletherapy unit, a circular exposure system for routine batch calibration of personnel dosemeters with four gamma ray sources ( 60 Co and 137 Cs) and a reference source system with six gamma ray sources ( 60 Co and 137 Cs). In addition a set of calibrated beta ray sources are provided ( 147 Pm, 204 Tl and 90 Sr). The dosimetric equipment consists of three free-air parallelplate ionization chambers serving as primary standards of exposure for the X-ray energy region, graphite cavity chambers with measured volume as primary standards for the gamma radiation of 137 Cs and 60 Co as well as different secondary standard ionization chambers covering the dose rate range from the natural background level up to the level of modern therapy accelerators. In addition for high energy photon and electron radiation a graphite calorimeter is provided as primary standard of absorbed dose. The principle experimental set-ups for the practical use of the standards are presented and the procedures for the calibration of the different types of dosemeters are described. (Author)

  16. Information systems for administration, clinical documentation and quality assurance in an Austrian disease management programme.

    Science.gov (United States)

    Beck, Peter; Truskaller, Thomas; Rakovac, Ivo; Bruner, Fritz; Zanettin, Dominik; Pieber, Thomas R

    2009-01-01

    5.9% of the Austrian population is affected by diabetes mellitus. Disease Management is a structured treatment approach that is suitable for application to the diabetes mellitus area and often is supported by information technology. This article describes the information systems developed and implemented in the Austrian disease management programme for type 2 diabetes. Several workflows for administration as well as for clinical documentation have been implemented utilizing the Austrian e-Health infrastructure. De-identified clinical data is available for creating feedback reports for providers and programme evaluation.

  17. A sidelight on the history Korea nuclear energy

    International Nuclear Information System (INIS)

    Park, Ik Su

    1999-12-01

    It deals with a sidelight on the history of Korea nuclear energy through debate. It includes a lot of debates, which are about opinions on agreement of nuclear energy, three people's debates on agreement of nuclear energy between Korea and U.S.A development of nuclear energy and revolution of technology, introduction of reactor for generation of electricity, discuss over business of Korea nuclear power, the system of nuclear power plants, the issues on administration for nuclear power and radiation safety, the important things of Korea nuclear power business and Let's keep the first reactor; TRIGA-MARK-II and III.

  18. Investigations on fiberoptic behaviour during gamma irradiation

    International Nuclear Information System (INIS)

    Siehs, J.

    1980-12-01

    Investigations on the behaviour of bulk glasses and fiber optics under gamma irradiation and two types of annealing processes (thermal and optical) have been investigated. The samples were irradiated in the thermal column of the TRIGA Mark II Reactor, Vienna. The irradiation induced losses of transmission were measured in a dual beam spectrophotometer. The transmission was measured one hour after reactor shut-down. Thermal annealing was done at 300, 400 and 500 0 C. Photo bleaching was investigated with a quartz-lamp, an arc-lamp and an UV-laser light. (author)

  19. Actualization and enlargement of the Upper Austrian emission inventory

    International Nuclear Information System (INIS)

    Winiwarter, W.; Schimak, G.; Raup, N.

    2001-06-01

    The functionality of the Upper Austrian emission inventory has been increased by simplifying the evaluation routines. Thus access to existing data will be simplified. This version 2.0 not only improves evaluation procedures already in place, but also allows to retrieve annual information on point sources, as routinely reported by the individual industrial facilities on an annual basis. In the same way as for such point source information, also statistical information is used to derive annual emission changes. This is currently limited to the sector of domestic heating, where emissions are directly influenced by climate parameters that can be easily obtained. Trend analysis currently is not possible due to the limited number of sectors included. First conclusions on the temporal behavior of emissions are still possible and are discussed here. Likewise, additional plausibility checks are facilitated by using temporal emission changes, which will help improve data quality. (author)

  20. A Thought Experiment Comparing Austrian and Keynesian Stimulus Packages

    Directory of Open Access Journals (Sweden)

    Wladimir Kraus

    Full Text Available Essentially, there are two competing views of how to overcome an economy-wide recession/depression. The Austrian view understands the free-play of competition as the most potent means to overcome the short-run mismatch between an excessive boom-level of nominal wages/prices and depressed crisis-level volume of aggregate spending. In the Keynesian view, the disastrous mismatch between desired saving and planned investment inherent in capitalist economies requires the government to step in and take up the burden of spending to infuse the lacking demand for products and labor.The thought experiment presented in the paper is designed to provide the reader with a direct comparison of major analytical claims of the two competing approaches to assess the ability of each of the two to affect, positively or negatively, employment, capital accumulation, and the general standard of living/real wages.

  1. Lay theories of suicide among Austrian psychology undergraduates.

    Science.gov (United States)

    Voracek, Martin; Loibl, Lisa Mariella; Lester, David

    2007-01-01

    Lester and Bean's (1992) Attribution of Causes to Suicide Scale gauges lay theories of suicide including intrapsychic problems, interpersonal conflicts, and societal forces as causes. Results obtained with its German form (n=165 Austrian psychology undergraduates) showed no sex differences and no social-desirability effects. Intriguingly, all three subscales were moderately intercorrelated, thereby indicating respondents' general agreement (or disagreement) with all three theories. Thus, the critical dimension of lay theories of suicide appears to be the belief that suicide has definite causes (regardless of type) versus that it is without causes (unpredictable). In addition, religiosity was positively associated (and overall knowledge about suicide negatively associated) with belief in intrapsychic causes, whereas liberal political views were negatively associated with belief in interpersonal causes.

  2. Austrian WBC intercomparison by means of a BOMAB phantom

    Energy Technology Data Exchange (ETDEWEB)

    Castellani, C.M.; Battisti, P.; Tarroni [ENEA, Centro Ricerche Ezio Clementel, Bologna (Italy). Dipt. Ambiente; Edelmeier, R. [Bundesamt fuer Eich- und Vermessungswesen, Wien (Austria)

    1998-07-01

    The paper discusses the results obtained in the intercomparison between the Austrian Institute for Legal Metrology and the ENEA (National Agency for New Technology, Energy and the Environment) Institute for Radiation Protection, which gave a BOMAB phantom. Values related to potassium content and MBA (minimum detectable activity) for each identified nuclide are also discussed. [Italian] L'Istituto Austriaco di Metrologia Legale ha organizzato l'interconfronto usando un fantoccio gelificato di tipo BOMAB fornito dall'Istituto di Radioprotezione dell'ENEA nel periodo marzo-giugno 1996. Vengono riportati i risultati ottenuti relativi al contenuto di potassio e all'attivita' minima rilevabile (MDA) per ogni nuclide identificato.

  3. 51. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    Oberhummer, H.

    2001-01-01

    The 51th Symposium of the Austrian Physical Society was held from 17-21 September 2001 at the Technical University of Vienna (Austria). The topics covered deal with: energy (greenhouse effect, climatic change, environment protection, energy system transformation, innovative energy technologies), neutrons and synchrotron radiation, quantum mechanics, microscopy, accelerator-driven systems, physics aspects of radiotherapy, nano world, micro cosmos, modern physics, life in the universe, x-ray fluorescence, heavy-ion accelerator mass spectrometry, acoustics, atomic-, molecular- and plasma physics, solid-state physics, nuclear and particle physics, medical-, bio-and environmental physics, quantum electronics, electrodynamics and optics. Those contributions which are in the INIS subject scope are indexed separately. (nevyjel)

  4. 64th Annual Meeting of the Austrian Physical Society

    International Nuclear Information System (INIS)

    2014-01-01

    The 64th Annual Meeting of the Austrian physical society, including a special topical Energy Day. was held at the Echophysics – European Centre for the History of Physics, Schloss Pöllau 1, 8225 Pöllau, Austria. The plenary sessions gave an overview of the present status of research in quantum mechanics, particle physics and solid state physics.The topical sessions were dedicated to: nuclear and particle physics; atoms, molecules, quantum optics and plasmas; solid state physics and research with neutron and synchrotron radiation; history of physics; surfaces, interfaces and thin films; nanostructures; fundamental interactions; gravity, quantum chromodynamics; particle theory and collider physics; detectors and methods. Those contributions which are in the INIS subject scope are indexed individually

  5. [CGM-Continuous Glucose Monitoring--Statement of the Austrian Diabetes Association].

    Science.gov (United States)

    Schütz-Fuhrmann, Ingrid; Rami-Merhar, Birgit; Hofer, Sabine; Stadler, Marietta; Bischof, Martin; Zlamal-Fortunat, Sandra; Laimer, Markus; Weitgasser, Raimund; Prager, Rudolf

    2016-04-01

    This position statement represents the recommendations of the Austrian Diabetes Association regarding the clinical diagnostic and therapeutic application, safety and benefits of continuous subcutaneous glucose monitoring systems in patients with diabetes mellitus, based on current evidence.

  6. [CGM-continuous glucose monitoring - statement of the Austrian Diabetes Association].

    Science.gov (United States)

    Schütz-Fuhrmann, Ingrid; Schober, Edith; Rami, Birgit; Stadler, Marietta; Bischof, Martin; Fortunat, Sandra; Laimer, Markus; Weitgasser, Raimund; Prager, Rudolf

    2012-12-01

    This position statement represents the recommendations of the Austrian Diabetes Association regarding the clinical diagnostic and therapeutic application, safety and benefits of continuous subcutaneous glucose monitoring systems in patients with diabetes mellitus, based on current evidence.

  7. The Remembrance of World War One and the Austrian Federation of Jewish War Veterans

    Directory of Open Access Journals (Sweden)

    Gerald Lamprecht

    2016-10-01

    Full Text Available This paper discusses discourses and activities of memory of the Austrian “Federation of Jewish War Veterans” (Bund jüdischer Frontsoldaten/BJF, based primarily on the analysis of the journal “Jewish Front” (Jüdische Front as well as on archival sources. A remarkable increase in anti-Semitic activities as well as acts of violence committed by the National Socialists led former Jewish soldiers of the Austrian army to found the BJF in 1932. The aim of the BJF was to defend the Austrian Jewry against anti-Semitic accusations as well as to strengthen their Jewish self-consciousness by focusing on the remembrance of the Jewish military service during the Great War and an idealized and exaggerated war experience. To reach their objectives, the BJF was organized hierarchically and militarily. The members wore uniforms, and the BJF organized military inspections, spread propaganda via the journal “Jewish Front” and initiated the erection of Jewish war memorials in several Austrian cities. Due to the fact that the BJF wanted to unify the Austrian Jewry under its leadership, it claimed to be above all party lines and propagandized a common Austrian Jewish identity.

  8. Occupational radiation exposure in upper Austrian water supplies and Spas

    International Nuclear Information System (INIS)

    Ringer, W.; Simader, M.; Bernreiter, M.; Aspek, W.; Kaineder, H.

    2006-01-01

    The Council Directive 96/29/EURATOM lays down the basic safety standards for the protection of the workers and the general public against the dangers arising from ionising radiation, including natural radiation. Based on the directive and on the corresponding Austrian legislation a comprehensive study was conducted to determine the occupational radiation exposure in Upper Austrian water supplies and spas. The study comprises 45 water supplies and 3 spas, one of them being a radon spa. Most measurements taken were to determine the radon concentration in air at different workplaces (n = 184), but also measurements of the dose rate at dehumidifiers (n = 7) and gamma spectrometric measurements of back washing water (n = 4) were conducted. To determine the maximum occupational radon exposure in a water supply measurements were carried out in all water purification buildings and in at least half o f the drinking water reservoirs of the water supply. The results were combined with the respective working times in these locations (these data having been collected by means of a questionnaire). Where the calculated exposure was greater than 1 MBq h/m then all drinking water reservoirs of the concerned water suppl y were measured for their radon concentration to ensure a reliable assessment of the exposure. The results show that the radon concentrations in the water supplies were lower as expected, being in 55% of all measurement sites below 1000 Bq/m in 91% below 5000 Bq/m and with a maximum value of 38700 Bq/m.This leads to exposures that are below 2 MBq h/m (corresponding to approx. 6 mSv/a) in 42 water supplies. However, for the remaining three water supplies maximal occupational exposures due to radon of 2.8 MBq h/m (∼ 10 mSv/a), 15 MBq h/m (∼ 50 mSv/a), and 17 MBq h/m ( ∼ 56 mSv/a), respectively, were determined. In these water supplies remediation measures were proposed, based mainly on improved ventilation of and/or reduction of working time in the building

  9. Potentials to mitigate climate change using biochar - the Austrian perspective

    Science.gov (United States)

    Bruckman, Viktor J.; Klinglmüller, Michaela; Liu, Jay; Uzun, Basak B.; Varol, Esin A.

    2015-04-01

    Biomass utilization is seen as one of various promising strategies to reduce additional carbon emissions. A recent project on potentials of biochar to mitigate climate change (FOREBIOM) goes even a step further towards bioenergy in combination of CCS or "BECS" and tries to assess the current potentials, from sustainable biomass availability to biochar amendment in soils, including the identification of potential disadvantages and current research needs. The current report represents an outcome of the 1st FOREBIOM Workshop held in Vienna in April, 2013 and tries to characterize the Austrian perspective of biochar for climate change mitigation. The survey shows that for a widespread utilization of biochar in climate change mitigation strategies, still a number of obstacles have to be overcome. There are concerns regarding production and application costs, contamination and health issues for both producers and customers besides a fragmentary knowledge about biochar-soil interactions specifically in terms of long-term behavior, biochar stability and the effects on nutrient cycles. However, there are a number of positive examples showing that biochar indeed has the potential to sequester large amounts of carbon while improving soil properties and subsequently leading to a secondary carbon sink via rising soil productivity. Diversification, cascadic utilization and purpose designed biochar production are key strategies overcoming initial concerns, especially regarding economic aspects. A theoretical scenario calculation showed that relatively small amounts of biomass that is currently utilized for energy can reduce the gap between Austria's current GHG emissions and the Kyoto target by about 30% if biomass residues are pyrolized and biochar subsequently used as soil amendment. However, by using a more conservative approach that is representing the aims of the underlying FOREBIOM project (assuming that 10% of the annual biomass increment from forests is used for biochar

  10. First experiences with NORM regulations in the Austrian legislation

    International Nuclear Information System (INIS)

    Dauke, Michael; Katzlberger, C.; Haider, W.; Ringer, W.

    2008-01-01

    Full text: This paper gives a brief overview of important aspects of the recently implemented NORM ordinance in the Austrian Radiation Protection Legislation. It describes first experiences from pilot studies and dose assessments in this field. The field of application of this ordinance is defined by a list of work activities which might cause a significant increase in the exposure of workers and of members of the public. This list includes work activities, which potentially increase the exposure due to radon or uranium, thorium and their progenies and work activities, where residues with elevated levels of natural radionuclides may lead to a significant increase in the exposure of workers and the public. The first level of a dose assessment is the determination of activity concentrations in materials. It is assumed that the dose of workers does not exceed 1 mSv per year, if the activity concentrations of natural radionuclides are below 1 Bq/g. A notification of the workplace to the radiation protection authority is sufficient in this case. Otherwise a detailed dose assessment considering all relevant exposure pathways has to be performed as well as radiation protection measures and organisational measures, if needed. If the results of the dose assessment show higher levels than 6 mSv per year, radiation protection measures like personal dosimeters and periodical medical examination and reporting to the radiation protection authority are obligatory. A similar dose assessment procedure has to be applied for residues. The residues are allowed to be disposed as conventional waste, as long as the dose assessment shows a dose lower than 1 mSv per year. Otherwise the residues have to be treated as radioactive waste. Only accredited or certified institutions may perform authorised dose assessments. The Austrian Agency for Food and Health Safety performed pilot studies in this field for getting more experience in the field of dose assessment and to get an overview of the

  11. CFD Simulation on Cooling Down of Beryllium Filters for Neutron Conditioning for Small Angle Neutron Scattering

    International Nuclear Information System (INIS)

    Azraf Azman; Shahrir Abdullah; Mohd Rizal Mamat

    2011-01-01

    The cryogenic system for cooling Beryllium filter utilizing liquid nitrogen was designed, fabricated, tested and installed at SANS instrument of TRIGA MARK II PUSPATI research reactor. A computational fluid dynamics (CFD) modeling was used to predict the cooling performance of the beryllium for optimization of neutron beam resolution and transmission. This paper presents the transient CFD results of temperature distributions via the thermal link to the beryllium and simulation of heat flux. The simulation data are also compared with the experimental results for the cooling time and distribution to the beryllium. (author)

  12. Search for free neutron-antineutron oscillations

    International Nuclear Information System (INIS)

    Bressi, G.; Calligarich, E.; Cambiaghi, M.; Dolfini, R.; Genoni, M.; Gigli Berzolari, A.; Lanza, A.; Liguori, G.; Mauri, F.; Piazzoli, A.; Ratti, S.P.; Torre, P.; Bini, C.; Conversi, M.; De Zorzi, G.; Gauzzi, P.; Massa, F.; Zanello, D.; Cardarelli, R.; Santonico, R.; Scannicchio, D.; Terrani, M.

    1989-01-01

    A search for free neutron-antineutron oscillations has been carried out at the Pavia Triga Mark II research reactor. A thin carbon target is crossed by a beam of thermal neutrons propagating in a 18.5 m long channel where the earth magnetic field is attenuated by a factor of 50. The total neutron current through the target is 3.2x10 10 n/s. Possible antineutron annihilations are identified by a large track detector surrounding the target. A lower limit on the oscillation time of 4.7x10 5 s (90% C.L.) has been reached. (orig.)

  13. Malaysia: Overview of activities on Neutron Imaging (NI) and Cultural Heritage (CH) studies

    International Nuclear Information System (INIS)

    Muhammad Rawi Mohamed Zin

    2012-01-01

    Inspection of cultural heritage artifact by neutron imaging becoming interesting and important research area since its able to sees internal structure non-destructively. Therefore advanced neutron imaging capability to conduct this kind of inspection is needed. Associated with this needs, TRIGA MARK II PUSPATI reactor has neutron imaging facility, NUR-2 which capable for radiography and tomography usage. Details parameters of current set up is given. Neutron radiography capability at this facility has been relied on direct method technique by the usage of SR-45 KODAK film technology. Current set-up has been used by university student through-out the country to conduct their research in various levels of educations

  14. Determination of toxic and essential element concentrations in foodstuffs from local market

    International Nuclear Information System (INIS)

    Surtipanti; Suwirma; Yumiarti; June, M.; Syaifudin, S.

    1989-01-01

    Determination of toxic and essential elements concentrations in foodstuffs from local market in Jakarta. Concentration of toxic essential elements, such as, As, Hg, Cr, Pb, Cu, and Zn, in rice, corn bean, small green peas, wheat, vegetables, fruits, tea and coffee, have been determined. As, Hg, Sb, Cr, Se, and Zn, were determined using neutron activation analysis, after being irradiated at TRIGA-MARK II reactor, while Pb and Cu were determined using atomic absorption spectrophotometer. The results obtained were lower than the maximum permissible concentration allowed. (author). 8 refs

  15. Determination of toxic and essential elements in foodstuffs from local market in Jakarta

    International Nuclear Information System (INIS)

    Sadjirun, S.

    1994-01-01

    This report presents data on toxic and essential elements such as As, Cd, Cr, Cu, Hg, Pb, Sb, Se, and Zn in rice, corn, bean, wheat, small green pea, vegetables, fruits, tea, coffee, sea foods, meat, chicken, intestines and associated organs, and eggs as consumed in Jakarta. As, Hg, Sb, Cr, Se, and Zn were determined using instrumental neutron activation analysis (INAA) after being irradiated at TRIGA MARK II reactor, while Cd, Cu, and Pb were determined using atomic absorption spectrometry (AAS). The results obtained were lower than the maximum permissible concentrations allowed. (author). 6 refs, 9 tabs

  16. [Austrian guideline for palliative sedation therapy (long version) : Results of a Delphi process of the Austrian Palliative Society (OPG)].

    Science.gov (United States)

    Weixler, Dietmar; Roider-Schur, Sophie; Likar, Rudolf; Bozzaro, Claudia; Daniczek, Thomas; Feichtner, Angelika; Gabl, Christoph; Hammerl-Ferrari, Bernhard; Kletecka-Pulker, Maria; Körtner, Ulrich H J; Kössler, Hilde; Meran, Johannes G; Miksovsky, Aurelia; Pusswald, Bettina; Wienerroither, Thomas; Watzke, Herbert

    2017-02-01

    Palliative sedation therapy (PST) is an important and ethically accepted therapy in the care of selected palliative care patients with otherwise unbearable suffering from refractory distress. PST is increasingly used in end-of-life care. Austria does not have a standardized ethical guideline for this exceptional practice near end of life, but there is evidence that practice varies throughout the country. The Austrian Palliative Society (OPG) nominated a multidisciplinary working group of 16 palliative care experts and ethicists who established the national guideline on the basis of recent review work with the aim to adhere to the Europeans Association of Palliative Care's (EAPC) framework on palliative sedation therapy respecting Austrians legal, structural and cultural background. Consensus was achieved by a four-step sequential Delphi process. The Delphi-process was strictly orientated to the recently published EUROIMPACT-sedation-study-checklist and to the AGREE-2-tool. Additionally national stakeholders participated in the reflection of the results. As a result of a rigorous consensus process the long version of the Austrian National Palliative Sedation Guideline contains 112 statements within eleven domains and is supplemented by a philosophers excursus on suffering. By establishing a national guideline for palliative sedation therapy using the Delphi technique for consensus and stakeholder involvement the Austrian Palliative Society aims to ensure nationwide good practice of palliative sedation therapy. Screening for the practicability and efficacy of this guideline will be a future task.

  17. Structures and perspectives of the Austrian energy system

    International Nuclear Information System (INIS)

    Wohlgemut, N.

    1992-03-01

    The technical tools for projecting future energy demand can be grouped into two broad categories: Firstly, time series or cross section data based econometric models which contain information about customers' past behavior and thus enable to judge the causal effects of economic factors like incomes and prices on energy demand (passive forecasting). Secondly, structural simulation models which indicate how energy services transform to flows of useful, final and primary energy. These models enable to estimate the technical potential of improving the energy application and energy transformation systems (active scenario approach). Comparison of the two approaches with respect to projections for future energy demand yields that, typically, in the short run of econometric approach will dominate the structural simulation model. In the long run, however, this relation will be reversed. The econometric models suffer lack of technical information necessary to describe the demand for energy. The structural simulation model enables an incorporation of technical factors like efficiencies and fuel shares. An application of the structural model is a simulation run describing a scenario in order to reduce the Austrian CO 2 -emissions according to the recommendations of the conference of Toronto

  18. Holocaust Studies in Austrian Elementary and Secondary Schools

    Directory of Open Access Journals (Sweden)

    Philipp Mittnik

    2016-09-01

    Full Text Available This article presents arguments in support of teaching about the Holocaust and Nazism in Austria at an early age. To accomplish this, Austrian and German elementary school textbooks were analyzed for the amount of content dealing with the Holocaust and Jews; the results showed that since 1980 the amount of content on the Holocaust increased in Germany, and to a lesser extent in Austria. The article reviews some of the criticism in Europe of the term Holocaust Education and explores some of arguments about why that is. The author argues that moral education and teaching of Human Rights are important components of, but ought not be the main goal of teaching about the Holocaust. The role of Austria after World War II, and exploration of the so called victim myth, prevalent until the 1990s are important to understanding history and to how history textbooks were created. After a discussion of how the Holocaust can be taught to elementary and early secondary school aged children, some suggestions are made about approaches to teaching the Holocaust to students in these age groups.

  19. Attitude Towards End of Life Communication of Austrian Medical Students.

    Science.gov (United States)

    Rumpold, Tamara; Lütgendorf-Caucig, Carola; Löffler-Stastka, Henriette; Roider-Schur, Sophie; Pötter, Richard; Kirchheiner, Kathrin

    2018-04-23

    Medical students have to acquire theoretical knowledge, practical skills, and a personal attitude to meet the emerging needs of palliative care. The present study aimed to assess the personal attitude of Austrian medical students towards end of life communication (EOLC), as key part of palliative care. This cross-sectional, mono-institutional assessment invited all medical students at the Medical University of Vienna in 2015. The assessment was conducted web-based via questionnaire about attitudes towards EOLC. Additional socio-demographic and medical education-related parameters were collected. Overall, 743 medical students participated in the present report. Differences regarding the agreement or disagreement to several statements concerning the satisfaction of working with chronically ill patients, palliative care, and health care costs, as well as the extent of information about palliative disease, were found for age, gender, and academic years. The overall attitude towards EOLC in the present sample can be regarded as quite balanced. Nevertheless, a considerable number of medical students are still reluctant to inform patients about their incurable disease. Reservations towards palliative care as part of the health care system seem to exist. The influence of the curriculum as well as practical experiences seems to be important but needs further investigation.

  20. Cornerstones of the Austrian radon risk communication strategy

    International Nuclear Information System (INIS)

    Kunte, A.; Ringer, W.

    2015-01-01

    On behalf of the Federal Ministry of Agriculture, Forestry, Environment and Water Management (BMLFUW), the National Radon Centre of Austria developed the National Radon Risk Communication Strategy. The superior goal is the reduction of the radon exposure of Austrian citizens as well as the reduction of radon-related lung cancer deaths. Austria, like many other countries, follows the approach to raise awareness and to inform the public to achieve this goal. The presented strategy deals with the question of how radon protection issues can be communicated to the public, existing fears can be reduced and affected people can be motivated to take action (perform a radon test, if necessary, mitigate or install preventive measures in new buildings). The cornerstones of the National Radon Risk Communication Strategy can be summarized as follows: - Definition of communication goals - Identification and categorization of target groups - Development of specific key messages for each of the target groups - Determination of communication channels and assessment of their efficiency - Integration of the radon issue in education and training - Cooperation with relevant organizations and platforms. The communication objectives, target groups and communication paths (and their evaluation) will be discussed during the presentation in detail.

  1. A Proposal for an Austrian Nursing Minimum Data Set (NMDS)

    Science.gov (United States)

    Hackl, W.O.; Ammenwerth, E.

    2014-01-01

    Summary Objective Nursing Minimum Data Sets can be used to compare nursing care across clinical populations, settings, geographical areas, and time. NMDS can support nursing research, nursing management, and nursing politics. However, in contrast to other countries, Austria does not have a unified NMDS. The objective of this study is to identify possible data elements for an Austrian NMDS. Methods A two-round Delphi survey was conducted, based on a review of available NMDS, 22 expert interviews, and a focus group discussion. Results After reaching consensus, the experts proposed the following 56 data elements for an NMDS: six data elements concerning patient demographics, four data elements concerning data of the healthcare institution, four data elements concerning patient’s medical condition, 20 data elements concerning patient problems (nursing assessment, nursing diagnoses, risk assessment), eight data elements concerning nursing outcomes, 14 data elements concerning nursing interventions, and no additional data elements concerning nursing intensity. Conclusion The proposed NMDS focuses on the long-term and acute care setting. It must now be implemented and tested in the nursing practice. PMID:25024767

  2. 52. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    Lippitsch, M.

    2002-01-01

    The 52th Symposium of the Austrian Physical Society was held from 23.-26. September 2002 at the Montan University of Leoben (Austria). The papers presented were organized under the following sessions: main session (intermetallic materials, nanostructures as sensors, volcanic products as dating materials); Fritz-Kohlrausch-price 2002 (electronic structure and charge transfer in doped single-walled carbon nanotubes), Max-Auwaerter-price 2002 ( growth phenomena of thin overlayers on semiconductor surfaces), Viktor-Hess-price 2002 (analysis of rare Ke4 - decays), Roman-Ulrich-Sexl-price 2002 (experienced physics); acoustics; atomic-, molecular- and plasma physics (plasma ion mass spectrometers, proton-transfer-reaction-mass-spectrometry, radiation damage, electron-molecule interactions, decay); solid physics (nanoopticcs, nanocrystalline magnetic materials, nanostructure, nanoelectronics); nuclear and particle physics (CP-violations, neutral kaons, quark-antiquark systems, QCD, kaonic atoms spectroscopy, hadronic decay, long-lived radionuclides); medical-, bio-and environmental physics (biological radiation damage, photons therapy, Med-AUSTRON, doses rate, endovascular brachytherapy); physics-industry-energy (ski-simulation, acoustic surface wave); neutrons and synchrotron radiation physics (neutron quantum interferometry, AUSTRON, synchrotron-induced x-ray analysis); polymer physics(micro-Raman spectroscopy, x-ray analysis); quantum electronics, electrodynamics and optics (solid-state lasers, doped lasers, quantum purification and teleportation, Bose-Einstein condensates, quantum optics, Talbot-Lau interferometry, neutron quantum phases) and two poster sessions with topics dealing with the subjects above mentioned. Those contributions which are in the INIS subject scope are indexed separately. (nevyjel)

  3. 55. Annual symposium of the Austrian Physical Society. Abstracts

    International Nuclear Information System (INIS)

    Vogl, G.; Sepiol, B.

    2005-01-01

    Full text: The 55 th Annual Symposium of the Austrian Physical Society was held from 27.-29. September 2005 at the University of Vienna (Austria), it consisted of a plenary session, oral and poster sessions devoted to: acoustics; women and physics; atomic-, molecular- and plasma physics; solid physics; nuclear and particle physics; medical-, bio-and environmental physics; neutrons and synchrotron radiation physics; surface and thin film analysis and quantum electronics, electrodynamics and optics. Topics such as graphs quantization, molecular interferometry, Brownian movement, ion beam diagnostics, electron emission, optical pumping, Bose-Einstein condensates, molecular matter waves, double-wall carbon nanotubes, quantum dots, ferromagnetic nanocomposites, nanowires, transmission electron microscopy analysis of nanostructures, nanocrystals studies, atomic defects in intermetallic compounds, electron energy loss spectroscopy of intermetallic compounds, CHIRALTEM project, covariance data, nuclear astrophysics, kaonic atoms, pionic hydrogen, geometric phase measurements with neutrons, International linear collider project, ATLAS muon spectrometer, ATLAS detector, LHC's protection system, baryon structure, QCD, lattice QCD, coherent tomography, light microscopy, high resolution magnetic resonance imaging, polymer gel dosimetry, radon microdosimetry, traffic air pollutants, BVOC seasonal variations, biogenic VOC emissions, ice dating, synchrotron small angle x-ray diffraction, small angle neutron scattering, stepped surfaces oxidation, grazing incidence synchrotron reflexion studies, magnetic thin films, atoms quantum dynamics, quantum entanglement, BEC and quantum gases experiments were discussed. This book of abstracts contains their summaries and those contributions which are in the INIS subject scope are indexed individually. (nevyjel)

  4. What did we learn from the Austrian radon project?

    International Nuclear Information System (INIS)

    Friedmann, H.

    2004-01-01

    Approximately 40000 measurements of indoor radon concentrations were performed in randomly selected homes during the Austrian Radon Project. These measurements were carried out by using long-term measuring devices (SSNTD and Electret detectors) and short-term charcoal detectors with liquid scintillation counting as the method of analysis. In addition to the equilibrium factor, soil gas measurements and quasi-continuous indoor measurements, parallel-measurements with different detector systems in randomly selected homes were also performed. Very different results were occasionally obtained for one and the same room at the same time. This was so not only when comparing the long-term and short-term measuring devices; actually, different long-term detector systems also often showed significant discrepancies in results, although all detector systems had been carefully calibrated and tested in laboratories. The essential conclusion was that during a longer exposure in randomly selected homes, the detectors may be moved, opened, or handled in other unfavourable ways which introduce additional uncertainties in the measuring results. The aim of the Austrian Radon Project was to estimate the radon risk for geographic areas (municipalities). This task is different from the evaluation of the mean radon concentration in a single home. Generally, while long-term measurements (a year or even longer) are necessary to get reliable results for a particular house, this is not so where only the mean indoor radon concentrations for an area are of interest. Observed indoor radon concentrations give information about the actual radon exposures of the inhabitants but not about the radon risk from the ground. The house type, the way the house is constructed, the storey where people live, and some living patterns (ventilation rate etc.) modify the geological risk significantly, although it is the geological situation that has to be primarily taken into account when planning and constructing

  5. Impacts of Austrian Climate Variability on Honey Bee Mortality

    Science.gov (United States)

    Switanek, Matt; Brodschneider, Robert; Crailsheim, Karl; Truhetz, Heimo

    2015-04-01

    Global food production, as it is today, is not possible without pollinators such as the honey bee. It is therefore alarming that honey bee populations across the world have seen increased mortality rates in the last few decades. The challenges facing the honey bee calls into question the future of our food supply. Beside various infectious diseases, Varroa destructor is one of the main culprits leading to increased rates of honey bee mortality. Varroa destructor is a parasitic mite which strongly depends on honey bee brood for reproduction and can wipe out entire colonies. However, climate variability may also importantly influence honey bee breeding cycles and bee mortality rates. Persistent weather events affects vegetation and hence foraging possibilities for honey bees. This study first defines critical statistical relationships between key climate indicators (e.g., precipitation and temperature) and bee mortality rates across Austria, using 6 consecutive years of data. Next, these leading indicators, as they vary in space and time, are used to build a statistical model to predict bee mortality rates and the respective number of colonies affected. Using leave-one-out cross validation, the model reduces the Root Mean Square Error (RMSE) by 21% with respect to predictions made with the mean mortality rate and the number of colonies. Furthermore, a Monte Carlo test is used to establish that the model's predictions are statistically significant at the 99.9% confidence level. These results highlight the influence of climate variables on honey bee populations, although variability in climate, by itself, cannot fully explain colony losses. This study was funded by the Austrian project 'Zukunft Biene'.

  6. Austrian Painter Leopold Kupelwieser and Bishop Josip Juraj Strossmayer

    Directory of Open Access Journals (Sweden)

    Ljerka Dulibić

    2016-01-01

    Full Text Available All 20th-century chronologies of the collector’s activity of Bishop Josip Juraj Strossmayer (1815-1905 and overviews of the evolution of today’s Strossmayer’s Gallery of Old Masters at the Croatian Academy of Sciences and Arts mention the bishop’s cooperation with the Austrian Nazarene painter Leopold Kupelwieser (1796-1862, father of Paul Kupelwieser, the former owner of the Brijuni islands. This episode from the “prehistory” of Strossmayer’s Gallery has hitherto been known only as a brief notice repeated in almost identical formulations: “In 1857, the bishop sent the first larger group of paintings to Vienna in order to be restored under the supervision of painter Leopold Kupelwieser.” Research of archival documents mentioning the cooperation between Bishop Strossmayer and painter Kupelwieser has now been complemented with an overview of Kupelwieser’s activity in Croatia, with an aim of promoting the preservation and evaluation of this segment of his painting oeuvre. Besides paintings ordered by Strossmayer (presently at the Diocesan Museum of Zagreb, Kupelwieser produced two paintings for Croatian churches independently of his cooperation with the bishop (for the church of St Stephen of Hungary, today’s church of the Immaculate Conception of the Blessed Virgin Mary in Nova Gradiška, and for the chapel of St Peter and Paul in Dvor na Uni. Two more paintings are preserved on the Brijuni islands that do not directly belong to Kupelwieser’s oeuvre yet are closely linked to him.

  7. Quantifying low-value services by using routine data from Austrian primary care.

    Science.gov (United States)

    Sprenger, Martin; Robausch, Martin; Moser, Adrian

    2016-12-01

    Open debates about the reduction of low-value services, unnecessary diagnostic tests and ineffective therapeutic procedures and initiatives like "Choosing Wisely "in the USA and Canada are still absent in Austria. The objectives of this study are: (i) to establish a list of ineffective or low-value services possibly provided in Austrian primary care, (ii) to explore how many of these services are quantifiable using routine data and (iii) to estimate the number of affected beneficiaries and avoidable costs arising from the provision of these services. In May 2014, we identified low-value care services relevant for primary care in Austria. For our analysis we used routine data sets from the Austrian health insurance. All analysis refer to the insured population of the Lower Austrian Sickness Fund (n = 1 168 433) in the year 2013. (i) We found 453 low-value services possibly offered in Austrian primary care. (ii) Only 34 (7.5%) services were quantifiable using routine data. (iii) In the year 2013, these 34 services were provided to at least 246 131 beneficiaries and the estimated avoidable costs arising were at least 11.38 million Euros. This accounts for 1.2% of overall spending of the Lower Austrian Sickness Fund for drugs and services provided by primary care doctors in the year 2013. The absence of a homogeneous, transparent and accessible coding system for diagnosis in Austrian primary care restrained our assessment. However, our study findings illustrate the potential utility and limitations of using claims-based measures to identify low-value care. © The Author 2016. Published by Oxford University Press on behalf of the European Public Health Association. All rights reserved.

  8. Social, psychological and demographic reflections on the Austrian nuclear power question

    International Nuclear Information System (INIS)

    Bretschneider, R.

    1980-01-01

    The political history of an Austrian referendum in 1978, which led to abandonment of a nuclear power station, is reviewed, and an attempt is made to analyse the reasons for the 'No' vote. Surveys are presented which attempt to classify the yes, no and undecided voters in terms of political views. The effects of the Harrisburg accident on Austrian public opinion is examined and the possibility of accentuated differences between 'for' and 'against' groups is stated. It is noted that success in energy saving may reduce the significance of the atomic energy question. (G.M.E.)

  9. Control Of Stepper Motor Movement By DC Voltage

    International Nuclear Information System (INIS)

    Gayani, Didi; Margono; Indasah, Iin; Sugito

    2000-01-01

    Instrumentation for controlling the power of reactor of TRIGA Mark II uses the stepper motor to move the control rod of neutron absorbers. The direction and speed of control rod movement are determined by the polarity and the amplitude of DC voltage as an error signal that is the difference of set point of power and the power of being measured on the control system. The unit of stepper motor controller of reactor instrumentation of TRIGA Mark II uses patent module of trade Mark of Vexta, USA. In this chance, the electronic circuit is made to function as the control of stepper motor movement by using the DC voltage to anticipate the problem may be faced in case of repair and maintenance of reactor instrumentation. As a result of experiment, it is stated that the control of motor movement by using DC voltage is performed into 2 stages. First, by making the oscillator that is proportional to the positive DC voltage. Secondly, by making the translator to translate the oscillator signal to be a logic pattern for controlling the movement of stepper motor. Translator and motor driver are made by using the L297 and L298 as a pair of stepper motor controller of SGS T HOMSON

  10. Post-irradiation examination of HTR-fuel at the Austrian Research Centre Seibersdorf Ltd

    International Nuclear Information System (INIS)

    Reitsamer, G.; Proksch, E.; Stolba, G.; Strigl, A.; Falta, G.; Zeger, J.

    1984-02-01

    This paper describes methods and measurements developed at the Austrian Research Centre Seibersdorf for the evaluation of the irradiation performance of HTR fuel. Main interest is concentrated on particle failure rates, fission product release, burn-up and inventory measurements (solid and gaseous fission products, uranium inventory). (Author) [de

  11. 45. Annual Convention of the Austrian Physical Society; 45. Jahrestagung der Oesterreichischen Physikalischen Gesellschaft

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This volume contains lectures of the 45{sup th} symposium of the Austrian Physical Society which had been held in Leoben, Austria in 1995. The following topics are included: Atomic physics, molecular physics, plasma physics, solid state physics, nuclear and particle physics, biophysics, environmental physics, quantum electronics and quantum optics. (Suda).

  12. Progress Report 1985 of the Austrian Research Centre Seibersdorf. Abridged version

    International Nuclear Information System (INIS)

    Schwach, G.W.

    1986-06-01

    The report gives a short survey of the work carried out by the Austrian Research Centre Seibersdorf in 1985. The working programme comprises five main areas: Energy and safety; Materials research, isotope and radiation techniques; Measuring techniques and information processing; Environmental protection, health and food; Industrial consulting. (Author)

  13. Networking for Education for Sustainable Development in Austria: The Austrian ECOLOG-Schools Programme

    Science.gov (United States)

    Rauch, Franz

    2016-01-01

    This case describes networking for education for sustainable development within the Austrian ECOLOG-schools network. The article presents theoretical concepts of networks in education in general, and the organization of the ECOLOG-network in particular. Based upon these foundations, the concept and results of a participatory evaluation study are…

  14. Psychometric Properties of the Revised Facts on Suicide Quiz in Austrian Medical and Psychology Undergraduates

    Science.gov (United States)

    Voracek, Martin; Tran, Ulrich S.; Sonneck, Gernot

    2008-01-01

    Psychometric properties and demographic correlates of a German form of R. W. Hubbard and J. L. McIntosh's (1992) Revised Facts on Suicide Quiz (RFOS), an inventory for assessing overall knowledge about suicide, were investigated in a sample of 1,093 Austrian medical and psychology students. Internal consistency of the RFOS was weak, as were many…

  15. Coming together but staying apart: continuity and change in the Austrian and Swiss varieties of capitalism

    NARCIS (Netherlands)

    Afonso, A.; Mach, A.; Becker, U.

    2011-01-01

    This paper provides an overview of continuity and change in the Swiss and Austrian political economies over the last 20 years. After outlining the different institutional foundations of economic governance in both countries (fragmented state, constrained executive power and bourgeois dominance in

  16. PCDD/F and PCB levels in Austrian cow's milk

    Energy Technology Data Exchange (ETDEWEB)

    Thanner, G.; Moche, W. [Umweltbundesamt Wien (Austria)

    2004-09-15

    In 2003 the Federal Environment Agency carried out a first Austrian wide milk monitoring study with the objective to get an overview of average PCDD/F levels in cow's milk, additionally dioxinlike PCBs, according to WHO, and indicator PCBs, as listed by national regulations, were analysed.

  17. Heritabilities and genetic correlations for honey yield, gentleness, calmness and swarming behaviour in Austrian honey bees

    NARCIS (Netherlands)

    Brascamp, Evert; Willam, Alfons; Boigenzahn, Christian; Bijma, Piter; Veerkamp, Roel F.

    2016-01-01

    Heritabilities and genetic correlations were estimated for honey yield and behavioural traits in Austrian honey bees using data on nearly 15,000 colonies of the bee breeders association Biene Österreich collected between 1995 and 2014. The statistical models used distinguished between the genetic

  18. Measurement of the 226Ra-concentration in bottled Austrian mineral waters and table beverages

    International Nuclear Information System (INIS)

    Friedmann, H.; Hernegger, F.

    1978-01-01

    226 Ra being regarded nowadays as a toxic trace element, a systementic examination of bottled Austrian mineral waters and table beverages has been carried out. Only in one case was the maximum allowable concentration of 3.3 pCi/l, a value set up by the WHO, clearly exceeded. (orig.) [de

  19. Deaustrification? : the policy-area-specific evolution of Austrian social partnership.

    NARCIS (Netherlands)

    Kittel, B.E.A.

    2000-01-01

    Recently, the functioning of Austrian Social Partnership has been increasingly questioned. If this interpretation of current strains on the relations between the state and the main economic interest organizations would be correct, Austria would become a significant case in favor of disorganization

  20. 46th annual symposium of the Austrian Physical Society. Programme and abstracts

    International Nuclear Information System (INIS)

    Schindler, H.G.

    1996-01-01

    This volume contains lectures (short communications) of the 46 th symposium of the Austrian Physical Society which had been held at the University of Linz (Austria) in 1996. The following topics are included: atomic physics, molecular physics, plasma physics, solid state physics, nuclear and particle physics, biophysics, environmental physics, quantum electronics and quantum optics. (Suda)

  1. Quality of Austrian and Dutch Falls-Prevention Information: A Comparative Descriptive Study

    Science.gov (United States)

    Schoberer, Daniela; Mijnarends, Donja M.; Fliedner, Monica; Halfens, Ruud J. G.; Lohrmann, Christa

    2016-01-01

    Objectives: The aim of this study was to evaluate and compare the quality of written patient information material available in Austrian and Dutch hospitals and nursing homes pertaining to falls prevention. Design: Comparative descriptive study design Setting: Hospitals and nursing homes in Austria and the Netherlands. Method: Written patient…

  2. Evaluation of air pollution-related risks for Austrian mountain forests

    International Nuclear Information System (INIS)

    Smidt, Stefan; Herman, Friedl

    2004-01-01

    The present paper describes air pollution status and evaluation of risks related to effects of phytotoxic pollutants in the Austrian mountain forests. The results are based on Austrian networks (Forest Inventory, Forest Damage Monitoring System, Austrian Bioindicator Grid), the Austrian sample plots of the European networks of the UN-ECE (ICP Forests, Level I and Level II) and interdisciplinary research approaches. Based on the monitoring data and on modelling and mapping of Critical Thresholds, the evaluation of risk factors was possible. Cause-effect relationships between air pollution and tree responses were shown by tree-physiological measurements. Sulfur impact, proton and lead input, concentrations of nitrogen oxides, nitrogen input and ozone were evaluated. The risk was demonstrated at a regional and large-scale national level. Especially the increasing O 3 level and the accumulation of Pb with altitude present most serious risk for mountain forests. - Despite strong reduction of emissions in Europe, pollutants are still a potential stress factor, especially for sensitive mountain forest ecosystems in Austria

  3. Progress Report 1984 of the Austrian Research Centre Seibersdorf. Abridged version

    International Nuclear Information System (INIS)

    Schwach, G.W.

    1986-06-01

    The report gives a short survey of the work carried out by the Austrian Research Centre Seibersdorf in 1984. The working programme comprises five main areas: Energy and safety; Materials research, isotope and radiation techniques; Measuring techniques and information processing; Environmental protection, health and food; Industrial consulting. (Author)

  4. Civic Education under Pressure? A Case Study from an Austrian School

    Science.gov (United States)

    Schild, Isabella; Breitfuss, Judith

    2018-01-01

    When the politician Roman Haider of the party Freiheitliche Partei Österreichs (FPÖ--Freedom Party of Austria) caused the interruption of a lecture about political extremism in an Austrian school in spring 2017, a heated debate erupted over the place of politics in school education. While Haider accused the lecturer of political propaganda,…

  5. 50. Annual symposium of the Austrian Physical Society; 50. Jahrestagung der Oesterreichischen Physikalischen Gesellschaft

    Energy Technology Data Exchange (ETDEWEB)

    Lippitsch, M E [Institut fuer Experimentalphysik, Karl-Franzens-Universitaet Graz, Universitaetsplatz 5, A-8010 Graz (Austria)

    2000-07-01

    The conference held from 25. - 29. 9. 2000 at the University of Graz was elaborated by the Austrian society of physics in the fields of solid state physics, polymers physics, quantum electronics, electrodynamics, optics, nuclear and particle physics, atomic, molecules and plasma physics, acoustics, physics - industry - energy and physics teaching. (botek)

  6. 1983 Annual convention of the Austrian Physical Society, University of Linz, 28 - 30 September 1983

    International Nuclear Information System (INIS)

    1983-01-01

    Proceedings of lectures and poster presentations given at the 1983 convention of the Austrian Physical Society, with (German) abstracts only. The four topical sessions were: 1) electrodynamics and optics 2) solid state physics 3) nuclear and particle physics 4) physics of high polymers Only part of the presentations pertain to the subject scope of INIS. (G.Q.)

  7. Austrian Daily Climate Data Rescue and Quality Control

    Science.gov (United States)

    Jurkovic, A.; Lipa, W.; Adler, S.; Albenberger, J.; Lechner, W.; Swietli, R.; Vossberg, I.; Zehetner, S.

    2010-09-01

    Checked climate datasets are a "conditio sine qua non" for all projects that are relevant for environment and climate. In the framework of climate change studies and analysis it is essential to work with quality controlled and trustful data. Furthermore these datasets are used as input for various simulation models. In regard to investigations of extreme events, like strong precipitation periods, drought periods and similar ones we need climate data in high temporal resolution (at least in daily resolution). Because of the historical background - during Second World War the majority of our climate sheets were sent to Berlin, where the historical sheets were destroyed by a bomb attack and so important information got lost - only several climate sheets, mostly duplicates, before 1939 are available and stored in our climate data archive. In 1970 the Central Institute for Meteorology and Geodynamics in Vienna started a first attempt to digitize climate data by means of punch cards. With the introduction of a routinely climate data quality control in 1984 we can speak of high-class-checked daily data (finally checked data, quality flag 6). Our group is working on the processing of digitization and quality control of the historical data for the period 1872 to 1983 for 18 years. Since 2007 it was possible to intensify the work (processes) in the framework of an internal project, namely Austrian Climate Data Rescue and Quality Control. The aim of this initiative was - and still is - to supply daily data in an outstanding good and uniform quality. So this project is a kind of pre-project for all scientific projects which are working with daily data. In addition to routine quality checks (that are running since 1984) using the commercial Bull Software we are testing our data with additional open source software, namely ProClim.db. By the use of this spatial and statistical test procedure, the elements air temperature and precipitation - for several sites in Carinthia - could

  8. Results of the Czech-Austrian calculations of BDBA radiological consequences

    International Nuclear Information System (INIS)

    Carny, P.; Hohenberg, J.-K.

    2003-01-01

    Full text: Common Czech - Austrian comparisons of codes and calculations of BDBA radiological consequences have been performed. Background of these comparisons is described in the paper presented at this symposium. Results of single steps are summarized and discussed in this poster presentation. From the Czech side calculations have been performed with computer codes PC Cosyma, este, RTARC, HAVAR, HERALD, PTM, RODOS/MATCH and long range code MEDIA used by the Czech meteorological institute (CHMI). Code PC Cosyma is taken as main comparable code in this inter-comparisons as it is used by the Czech and the Austrian side. For every accident scenario and for deterministic as well as probabilistic assessment of accident consequences results of both sides have been practically identical. Computer code 'este' is instrument for projection of release and evaluation of real release under real VVER 440 and WER 1000 emergency conditions. The code can be operated with real radiological, meteorological and technological data from the plant. The code calculates projection of avertable doses and simulates movement of radioactive clouds in the vicinity (up to 40-50 km) of the plant. The code participates in these comparisons as it serves as a support instrument for the staff at the emergency centre of the Czech nuclear regulatory body. Code RTARC (Real Time Accident Release Consequences) serves as an instrument for evaluation of radiation situation in the vicinity of the plant (up to 40 km) during the early phase of an accident. The code participates in these comparisons as it was used in the process of the Czech nuclear power plants protective action planning zone determination. Codes HERALD and HAVAR have been used by Skoda and Energoprojekt for analyses of consequences of design bases accidents in Temelin safety report. They were compared with PC Cosyma in one step of these common calculations by the Czech side. The code HAVAR enables to calculate ingestion doses, too, and

  9. Why Credit Deflation Is More Likely than Mass Inflation: An Austrian Overview of the Inflation Versus Deflation Debate

    Directory of Open Access Journals (Sweden)

    Vijay Boyapati

    2010-12-01

    Full Text Available This article provides an Austrian overview of the inflation versus deflation debate which has captured the attention of the economics profession in the years following the US housing bust. Much of the Austrian analysis of this debate has focused on the massive expansion of the Federal Reserve’s balance sheet and attendant creation of new reserves. Several Austrian economists have predicted that the creation of new reserves will cause a massive increase in inflation. The money multiplier theory, on which these predictions are based, is criticized and an overview of the Austrian business cycle theory is provided to explain why banks are reluctant to issue new credit. Finally, an analysis of the politics of deflation is provided and a class theory is presented to explain why a policy of controlled credit deflation is more likely than a policy that would result in mass inflation or hyperinflation.

  10. Biblical Allusions in Expressionist Poetry in the Context of Austrian, German, and Ukrainian Literature : A Comparative Analysis

    NARCIS (Netherlands)

    Mykhalchuk, T.

    2016-01-01

    With the application of comparative methodology, this article analyzes biblical allusions, reminiscences, paraphrases, direct and indirect quotations, and symbols in the poetry of Austrian, German, and Ukrainian writers (Georg Heym, Mykola Bazhan, Mykola Khvyliovyj Todosii, T. Osmachka, Pavlo

  11. Comparison of amount of physical load in the Czech and Austrian footballers at the same level of performance

    OpenAIRE

    Bujnovský, David

    2011-01-01

    Title: Comparison of the size of the motor load in the Czech and Austrian soccer players at the same performance level Objectives: The aim is to determine the size of the physical load of players during a football match. At the same time the next aim is to determinate the differences of physical load between Czech and Austrian soccer players at the same performance level. Methods: The indirect (mediated) observations was used in this bachelor thesis, because the data were recorded by computer...

  12. Impact of Austrian hydropower plants on the flood control safety of the Hungarian Danube reach

    International Nuclear Information System (INIS)

    Zsuffa, I.

    1999-01-01

    Statistical analysis of daily water level data from four gauging stations along the Hungarian Danube reach has been carried out with the purpose of analysing the impact of the Austrian hydropower plants on the floods of the river. Conditional probability distribution functions of annual flood load maxima and annual number of floods were generated for the periods 1957-1976 and 1977-1996. By comparing these distribution functions, it could be shown that the flood load maxima have decreased, while the number of small and medium floods have increased during the past forty years. These changes indicate a decreased rate of flood superposition resulting from the barrages constructed in this period. The significantly decreased flood load maxima indicate that the Austrian barrage system has positive impact on the flood control safety of the Hungarian Danube reach

  13. Legal aspects of the crimes committed in insolvency proceedings – comparison of Czech and Austrian legislation

    Directory of Open Access Journals (Sweden)

    Marta Uhlířová

    2013-01-01

    Full Text Available The subject of this paper is to compare the Czech and Austrian legislation considering offenses which entrepreneurs and other entities (natural person may commit within the insolvency proceedings or which are related to the insolvency. Emphasis is placed on the comparison of Czech and Austrian legislation with regard cross-border relationships within the business environment and living between the Czech Republic and Austria.Czech entrepreneurs and natural person in Austria can get into a situation where their debtor is located in Austria and finds himself insolvent or vice versa. Also the Czech entrepreneurs and natural person may do their bussines or live in Austria and may get into such a situation when they are close to the situation which can lead to their decline. This paper would be for them a practical recommendation on how to avoid potential criminal liability.

  14. Manmade radionuclide vector in Austrian soil and vegetation near Temelin nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Sinojmeri, M.; Ringer, V. [Oesterreichische Agentur fuer Gesundheit und Ernaehrungssicherheit - AGES (Austria)

    2014-07-01

    Since Chernobyl NPP accident an environmental monitoring program concerning the Upper Austrian region near Czech Republic Nuclear Power Plant, NPP Temelin, is in progress between AGES and BMLFUV, the Austrian Federal Ministry of Agriculture, Forestry, Environment, Water and Food, in Austria. This paper presents the results obtained during the sampling campaign over biennial period of 2010-2011. Soil samples, grass and different cereal species were collected. Beside Cs-134, Cs-137 and Sr-89, Sr-90 isotopes, at this phase the number of isotopes determined was extended with plutonium isotopes Pu-238, Pu-239, Pu-240, Pu-241 and Am-241. A comparison of these results with the existing data so far is presented. New knowledge was obtained related the bio-kinetic parameters of these elements in the environment. Document available in abstract form only. (authors)

  15. Towards a Dynamic Resource-Based View: Insights from Austrian capital and Entrepreneurship Theory

    DEFF Research Database (Denmark)

    Foss, Nicolai Juul; Ishikawa, Ibuki

    The dominant view in the strategic management field is the resource-based view ("RBV"). It has often been observed that the RBV is lacking in the dynamic dimension. For example, processes of building competitive advantages by means of combining existing complementary resources in novel ways...... are not inquired into. We argue that the RBV may profitably draw on Austrian (Misesian) and Knightian insights in entrepreneurship and capital theory, particularly in its Lachmannian manifestation, in order to strengthen its dynamic components. We link the RBV and Austrian ideas in the context of the theory...... of complex systems pioneered by Herbert Simon. We draw a number of implications for strategic management from this synthesis, notably into resource value and sustainability of competitive advantage.JEL Code: B53, D21, L23, M1...

  16. Austrian Capital Theory and the Link Between Entrepreneurship and the Theory of the Firm

    DEFF Research Database (Denmark)

    Foss, Kirsten; Foss, Nicolai Juul; Klein, Peter G.

    2005-01-01

    tangible and intangible,are heterogeneous; arranging these assets to minimize contractual hazards, toprovide efficient investment incentives, or to exploit competitive advantage isconceived as the prime task of economic organization. None of these approaches,however, is based on a systematic theory......Several writers link entrepreneurship to asset ownership, trying to incorporatethe theory of entrepreneurship into the theory of the firm. The critical link, weargue, is capital heterogeneity. Transaction cost, property rights, and resourcebasedapproaches to the firm assume that assets, both...... of capital heterogeneity. Inthis paper we outline the approach to capital developed by the Austrian schoolof economics and integrate it into an entrepreneurial theory of the firm. We refineAustrian capital theory by defining capital heterogeneity in terms of subjectivelyperceived attributes, that is...

  17. Use of boron nitride for neutron spectrum characterization and cross-section validation in the epithermal range through integral activation measurements

    Energy Technology Data Exchange (ETDEWEB)

    Radulović, Vladimir, E-mail: vladimir.radulovic@ijs.si [Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Trkov, Andrej [Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia); IAEA, Vienna International Centre, PO Box 100, A-1400 Vienna (Austria); Jaćimović, Radojko [Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Gregoire, Gilles; Destouches, Christophe [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 St. Paul-Lez-Durance (France)

    2016-12-21

    A recent experimental irradiation and measurement campaign using containers made from boron nitride (BN) at the Jožef Stefan Institute (JSI) TRIGA Mark II reactor in Ljubljana, Slovenia, has shown the applicability of BN for neutron spectrum characterization and cross-section validation in the epithermal range through integral activation measurements. The first part of the paper focuses on the determination of the transmission function of a BN container through Monte Carlo calculations and experimental measurements. The second part presents the process of tayloring the sensitivity of integral activation measurements to specific needs and a selection of suitable radiative capture reactions for neutron spectrum characterization in the epithermal range. A BN container used in our experiments and its qualitative effect on the neutron spectrum in the irradiation position employed is displayed in the Graphical abstract. - Graphical abstract: Neutron spectra inside the JSI TRIGA Mark II PT irradiation position, obtained with a Monte Carlo calculation: blue: unperturbed, green inside a BN container, of wall thickness 4 mm, 13 mm in diameter and 14 mm in height.

  18. Use of boron nitride for neutron spectrum characterization and cross-section validation in the epithermal range through integral activation measurements

    International Nuclear Information System (INIS)

    Radulović, Vladimir; Trkov, Andrej; Jaćimović, Radojko; Gregoire, Gilles; Destouches, Christophe

    2016-01-01

    A recent experimental irradiation and measurement campaign using containers made from boron nitride (BN) at the Jožef Stefan Institute (JSI) TRIGA Mark II reactor in Ljubljana, Slovenia, has shown the applicability of BN for neutron spectrum characterization and cross-section validation in the epithermal range through integral activation measurements. The first part of the paper focuses on the determination of the transmission function of a BN container through Monte Carlo calculations and experimental measurements. The second part presents the process of tayloring the sensitivity of integral activation measurements to specific needs and a selection of suitable radiative capture reactions for neutron spectrum characterization in the epithermal range. A BN container used in our experiments and its qualitative effect on the neutron spectrum in the irradiation position employed is displayed in the Graphical abstract. - Graphical abstract: Neutron spectra inside the JSI TRIGA Mark II PT irradiation position, obtained with a Monte Carlo calculation: blue: unperturbed, green inside a BN container, of wall thickness 4 mm, 13 mm in diameter and 14 mm in height.

  19. Phylogenetic analysis of Austrian canine distemper virus strains from clinical samples from dogs and wild carnivores.

    Science.gov (United States)

    Benetka, V; Leschnik, M; Affenzeller, N; Möstl, K

    2011-04-09

    Austrian field cases of canine distemper (14 dogs, one badger [Meles meles] and one stone marten [Martes foina]) from 2002 to 2007 were investigated and the case histories were summarised briefly. Phylogenetic analysis of fusion (F) and haemagglutinin (H) gene sequences revealed different canine distemper virus (CDV) lineages circulating in Austria. The majority of CDV strains detected from 2002 to 2004 were well embedded in the European lineage. One Austrian canine sample detected in 2003, with a high similarity to Hungarian sequences from 2005 to 2006, could be assigned to the Arctic group (phocine distemper virus type 2-like). The two canine sequences from 2007 formed a clearly distinct group flanked by sequences detected previously in China and the USA on an intermediate position between the European wildlife and the Asia-1 cluster. The Austrian wildlife strains (2006 and 2007) could be assigned to the European wildlife group and were most closely related to, yet clearly different from, the 2007 canine samples. To elucidate the epidemiological role of Austrian wildlife in the transmission of the disease to dogs and vice versa, H protein residues related to receptor and host specificity (residues 530 and 549) were analysed. All samples showed the amino acids expected for their host of origin, with the exception of a canine sequence from 2007, which had an intermediate position between wildlife and canine viral strains. In the period investigated, canine strains circulating in Austria could be assigned to four different lineages reflecting both a high diversity and probably different origins of virus introduction to Austria in different years.

  20. Segregated integration : recent trends in the Austrian gender division of labor

    OpenAIRE

    Kreimer, Margareta; Mora, Ricardo

    2013-01-01

    Using micro data from the Austrian Labor Force Survey, this paper explores how decreases in the gender differential in participation rates together with increasing differentials in the incidence of part-time jobs and stable or rising levels of occupational segregation by gender affect the gender division of labor. To so so, we propose an index for the gender division of labor based on the Mutual Information index. Our main results show that the gender division of labor is very sta...

  1. Authority Relationship From a Societal Perspective: Social Representations of Obedience and Disobedience in Austrian Young Adults

    OpenAIRE

    Fattori, Francesco; Curly, Simone; J?rchel, Amrei C.; Pozzi, Maura; Mihalits, Dominik; Alfieri, Sara

    2015-01-01

    Obedience and disobedience have always been salient issues for both civil society and social psychologists. Since Milgram’s first studies on destructive obedience there has not been a bottom-up definition of what obedience and disobedience mean. The current study aimed at investigating the social representations young adults use to define and to co-construct knowledge about obedience and disobedience in Austria. One hundred fifty four (106 females, 68.8%) Austrian young adults (Mean age = 22....

  2. European parliament in Strasbourg more courageous against 'atomic neighbours' than Austrian politicians

    International Nuclear Information System (INIS)

    Stockinger, H.

    1987-01-01

    The author is refering to a notice in the german journal VDI-Nachrichten that the European Parliament claims that nuclear power stations should be put into operation upon agreement of the neighbouring member state up to a distance of 100 km from the border. The presently accepted distance is 30 km only. The author gives a list of claims the Austrian authorities should insist on when negotiating with neighbours operating nuclear power plants, primarily West Germany and Czechoslovakia. 1 fig. (qui)

  3. Longer Working Hours? More Flexible Work Schedules? Do Austrian Economic Policymakers Need to Act?

    OpenAIRE

    Alfred Stiglbauer

    2004-01-01

    On September 23, 2004, the Oesterreichische Nationalbank (OeNB) hosted a workshop to discuss extending working hours and increasing working time flexibility. After Peter Mooslechner (OeNB) outlined the development of the present discussion in the media and presented some facts, the participants delivered their statements. Erhard Fu‹rst (Federation of Austrian Industry and Austria perspektiv) called for more flexibility rather than for an extension of working hours. He supported this view by p...

  4. Open Access Policies of Research Funders: The Case Study of the Austrian Science Fund (FWF)

    OpenAIRE

    Tonto, Yaşar; Doğan, Güleda; Al, Umut; Madran, Orçun

    2015-01-01

    The Austrian Science Fund (FWF) is the main funder for basic research in Austria. FWF has been instrumental in promoting Open Access in Austria and elsewhere and possesses a strong Open Access policy for the research it funds. This case study presents FWF as a good practice of an effective funder policy on account of its comprehensive strategy and multi-faceted approach for implementing and supporting it.

  5. Joint Annual Meeting of the Austrian Physical Society and the Swiss Physical Society together with the Austrian and Swiss Societies for Astronomy and Astrophysics

    International Nuclear Information System (INIS)

    2013-01-01

    The Joint Annual Meeting of the Austrian Physical Society and the Swiss Physical Society was organized together with both national societies of Astronomy and Astrophysics (SSAA and ÖGAA) at the Johannes Kepler University Linz, Altenberger Straße 69, 4040 Linz, Austria. The plenary sessions gave an overview of the present status of research in quantum mechanics, particle, atomic and molecular physics. The topical sessions were dedicated to: nuclear, particle- and astro particle physics; physics teachers; acoustics; atoms, molecules, quantum optics and plasmas; solid state physics and research with neutron and synchrotron radiation; history of physics; medical, bio and environmental physics; surfaces, interfaces and thin films; careers in physics. There were special sessions on thermoelectrics and photovoltaics. In addition to the regular program, an Energy Day (Energietag) with several parallel sessions on recent topics of energy generation, -transport and -storage was jointly organized by the Energy and Industry Subdivisions of the Austrian Physical Society and by the Johannes Kepler Universität Linz. Those contributions which are in the INIS subject scope are indexed individually

  6. [Comparison between the Austrian and German DRG systems in hand surgery].

    Science.gov (United States)

    Lotter, O; Jaminet, P; Schwarzach, S; Schaller, H E

    2013-02-01

    Diagnosis-Related Groups (DRG) are a patient classification system grouping related types of patients treated to the resources they consumed. In this analysis, we compared the Austrian and the German DRG systems. The 15 most common hand surgical diagnoses and their corresponding operative treatment were transferred into the Austrian system. Thus, the length of stay and the reimbursement of both countries could be obtained and compared. The mean values and the median values of the upper and lower thresholds of length of stay as well as the average length of stay were all lower in Austria compared to Germany. Reimbursement in Germany was higher in 13 of 19 cases. Total proceeds amounted to 1.67 million in the German and 1.70 million in the Austrian health care system. Considering the purchasing power applying consumer prize parities, the difference of reimbursement between the countries rose to 130,000 which equals a difference of almost 8%. Reimbursement of the top 15 diagnoses in hand surgery in Austria is 8% higher than in Germany. Except for one case, mean values as well as upper and lower thresholds of length of stay are considerably shorter in Austria. Comparison of international data to refine a national compensation system is advocated.

  7. Österreichs Wirtschaftsbeziehungen in Südostasien [Austrian Economic Relations to South-East Asia

    Directory of Open Access Journals (Sweden)

    Reinhart Zimmermann

    2008-01-01

    Full Text Available Der süd- und südostasiatische Raum befindet sich im Aufholprozess. Der anhaltende Wachstumstrend geht einher mit der steigenden Nachfrage aus den Industriestaaten sowie dem Binnenmarkt und führt auch zu erhöhtem Bedarf an Infrastruktur. Auch die österreichische Wirtschaft profitiert vom Asien-Boom. Dies zeigt das stete Wachstum österreichischer Warenexporte in die Region, der Anstieg heimischer Direktinvestitionen sowie die wachsende Präsenz österreichischer Firmen. Ziel der österreichischen WirtschaftsvertreterInnen ist es, die Tigerstaaten Südostasiens mehr aus dem Schatten der aufstrebenden Wirtschaftssupermacht China zu holen und die österreichische Wirtschaftsverflechtung mit diesen Ländern zu intensivieren.The South and South East Asian Area has been catching up with the developed world. The sustained economic growth trend goes hand in hand with a higher demand from industrialized nations and a stronger internal demand, pushing for better infrastructure. The Austrian economy is also benefiting from booming Asia, underscored by the steady increase of Austrian exports to this region, the rise of foreign direct investment and companies doing business in these countries. The Austrian business community would like to see the South East Asian tiger states more out of the shadow of the new super power China. The overall objective is to intensify the economic integration with South and South East Asia.

  8. 54. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    Lippitsch, M.

    2004-01-01

    The papers presented were organized under the following sessions: main session (from attoseconds to RGB to telecom, density functional calculations, magnetic anisotropy of nanostructures, quantum cascade laser, bose-einstein condensates, DNA molecular force sensor); Fritz-Kohlrausch-price 2004 (nanoscale building blocks), Max-Auwaerter-price 2004 (electron emission and nano defects, magnetic rings), AT + S price 2004 (conducting atomic-force microscopy for nanoscale studies), Viktor-Hess-price 2004 (entanglement for meson-antimeson systems), Roman-Ulrich-Sexl-price 2004 (teaching physics ); acoustics; atomic-, molecular- and plasma physics (kinetic electron emission, accelerated-mass spectrometry of molecules, dissociative electron attachment, voc measurements); solid physics (spin relaxation, nano clean room reactor, proton transport through nanotubes); nuclear and particle physics (color reconnection, supersymmetry at Large Hadron Collider, pionic hydrogen, kaonic hydrogen, quantum chaos, quantum dwell time, trigger system simulation, ATLAS initial detector layout, QCD); medical-, bio-and environmental physics (PTR-MS, validation Monte Carlo FLUKA codes, Gamma camera- positron emission tomography); neutrons and synchrotron radiation physics (3D synchrotron micro on human bones); surface and thin film analysis; quantum electronics, electrodynamics and optics (teleportation, optic induced changes in interaction in BEC, electronic feed back cooling single ions) and poster sessions with topics dealing with the subjects above mentioned. This book of abstracts contains their summaries and those contributions which are in the INIS subject scope are indexed individually. (nevyjel)

  9. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

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

  10. Attitudes among the general Austrian population towards neonatal euthanasia: a survey.

    Science.gov (United States)

    Goldnagl, Lena; Freidl, Wolfgang; Stronegger, Willibald J

    2014-10-07

    The Groningen Protocol aims at providing guidance in end-of-life decision-making for severely impaired newborns. Since its publication in 2005 many bioethicists and health care professionals have written articles in response. However, only very little is known about the opinion among the general population on this subject. The aim of this study was to present the general attitude towards neonatal euthanasia (NE) among the Austrian population and the factors associated with the respondents' opinion. A cross-sectional study was conducted among the general Austrian population. Computer-assisted telephone interviews were performed with 1,000 interviewees aged 16 years and older. Binary logistic regression was performed in order to determine factors that are independently associated with the respondents' opinion about neonatal euthanasia. While 63.6% of the participants rejected the idea of neonatal euthanasia for severely impaired newborns, 36.4% opted either in favor or were undecided. Regression analysis has shown the respondents' educational level (p = 0.005) and experience in the care of terminally ill persons (p = 0.001) to be factors that are positively associated with the rejection of neonatal euthanasia, whereas a higher age was associated with a lower degree of rejection (p = 0.021). We found that the majority of the Austrian population rejects the idea of neonatal euthanasia for severely impaired newborns. However, given the increasing levels of rejection of NE among the younger generations and among people with a higher educational level, it cannot be precluded that the rejection rate might in future increase even further, rather than decrease.

  11. THE AUSTRIAN CONSTITUTIONAL CONVENTION: CONTINUING THE PATH TO REFORM THE FEDERAL STATE?

    Directory of Open Access Journals (Sweden)

    Anna Gamper

    2006-04-01

    Full Text Available This article discusses the different debates and attempts to reform the Austrianfederal system over the last fifteen years. The article is based on a historicalperspective that describes the most relevant developments of Austrianfederalism during the 20th century, highlighting the importance of thecentralisation process through the constant transfer of powers from the Länderto the Federal Government, as well as various debates in this regard.According to the author, since 1995, the year of Austrian adhesion to theEuropean Union, two opportunities have been missed to carry out a generalreform of the federal system which could contribute to compensating thecentralisation process.The first missed opportunity is directly related to the Austrian adhesion tothe European Union. The Länder agreed to the adhesion under the conditionthat the Federal Constitution would include their participation in Europeandecision-making processes. By focussing on this point, the Länder set aside the opportunity to take advantage of the debate and, as a consequence,press for structural reform of the federal system. The second missed opportunitywas related to the dispersion of proposals resulting from the work ofthe Austrian Constitutional Convention. The Convention, created in 2003,had the mission of discussing those aspects of the reform of the Constitutionthat regulated the federal structure of the country and, as a consequence,of making a first draft reform. The incapability of establishing and definingcommon ground for reform, together with the lack of flexibility and ofseeking political commitment, weakened the role of the Convention and,thus, any possibility to carry on with the reform.

  12. H Reactor

    Data.gov (United States)

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

  13. The effectiveness of psychotherapy with refugees and asylum seekers: preliminary results from an Austrian study.

    Science.gov (United States)

    Renner, Walter

    2009-02-01

    An Austrian Non-Governmental Organization (NGO) offered psychotherapy to 37 asylum seekers and refugees (21 of them female) with a mean age of 36.1 years (s = 7.5), with the majority of them from Chechnya or Afghanistan. Comparative data between the start of therapy and the time of evaluation revealed a highly significant positive effect (d = 0.77), while most therapies were still going on. By a retrospective measure of perceived change, 85% of the participants reported significant improvements. The results show that even under difficult conditions, when working with asylum seekers and refugees, psychotherapy can be effective.

  14. Progress report 1980/81 of the Austrian Academy of Sciences

    International Nuclear Information System (INIS)

    1982-01-01

    From the numerous institutes and divisions of the Austrian Academy of Sciences presented in this report the Commission for Arteriosclerosis and Thrombosis Research (application of radioimmunoassay) and the Institute for X-ray Microstructure Research (investigation of biological substances by X-ray and neutron small angle scattering) are partly within the scope of INIS. Fully in scope are short project discriptions of the Institute for Radium Research and Nulear Physics: the Commission for the SIN-project and the Institute for High Energy Physics, completed by publication lists. (G.Q.)

  15. Annoying vacation souvenir: Fish tapeworm (Diphyllobothrium sp.) infestation in an Austrian fisherman.

    Science.gov (United States)

    Stadlbauer, Vanessa; Haberl, Renate; Langner, Cord; Krejs, Günter J; Eherer, Andreas

    2005-11-01

    Diphyllobothriosis is infestation with the fish tapeworm. Although the worldwide incidence has decreased in recent decades, increased travel and the new popularity of dishes involving raw fish (e.g. sushi) may provide a higher risk of infestation in formerly low-risk areas. We report an Austrian fisherman who passed a 75 cm tapeworm segment in his stool. Infestation presumably occurred 14 months earlier during a fishing tour in Alaska. At presentation, the patient was asymptomatic, reported no weight loss and showed neither anaemia nor eosinophilia. He was cured with a single dose of 10 mg/kg body weight praziquantel.

  16. Feasibility and acceptance of biofeedback-assisted mental training in an Austrian elementary school: a pilot study.

    Science.gov (United States)

    Crevenna, Richard; Krammer, Christine; Keilani, Mohammad

    2016-04-01

    This pilot study aimed to investigate feasibility, acceptance, and effects of biofeedback-assisted mental training in a population of fifteen 10-year-old pupils in an Austrian elementary school. Participants were instructed in relaxation techniques by using biofeedback. Before intervention, after 6 weeks with active mental training and with regular instructions by the teacher, and after a further time period of 6 weeks without instructions, attention and concentration improved. The results indicate feasibility, good acceptance, and beneficial effects of biofeedback-assisted mental techniques in Austrian elementary school pupils.

  17. Validation of a new design of tellurium dioide-irradiated target

    Energy Technology Data Exchange (ETDEWEB)

    Fllaoui, Aziz; Ghamad, Younes; Zoubir, Brahim; Ayaz, Zinel Abidine; El Morabiti, Aissam; Amayoud, Hafid [Centre National de l' Energie des Sciences et des Techniques Nucleaires, Rabat (Morocco); Chakir, El Mahjoub [Nuclear Physics Department, University Ibn Toufail, Kenitra (Morocco)

    2016-10-15

    Production of iodine-131 by neutron activation of tellurium in tellurium dioxide (TeO{sub 2}) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gas welding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ≤ 10 - 4 mbr.L/s, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to 600 .deg. C with the appearance of deformations on lids beyond 450 .deg. C. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes-convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from 4 hours of irradiation at a power level of 0.5 MW up to 35 hours (7 h/d for 5 days a week) at 1.5 MW. The results show that the irradiated targets are

  18. Validation of a New Design of Tellurium Dioxide-Irradiated Target

    Directory of Open Access Journals (Sweden)

    Aziz Fllaoui

    2016-10-01

    Full Text Available Production of iodine-131 by neutron activation of tellurium in tellurium dioxide (TeO2 material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gas welding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ≤ 10−4 mbr.L/s, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics. To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to 600°C with the appearance of deformations on lids beyond 450°C. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes—convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from 4 hours of irradiation at a power level of 0.5 MW up to 35 hours (7 h/d for 5 days a week at 1.5 MW. The results show that the irradiated targets are

  19. Why Context Matters: Social Inclusion and Multilingualism in an Austrian School Setting

    Directory of Open Access Journals (Sweden)

    Ulrike Jessner

    2017-12-01

    Full Text Available This article draws attention to language choice and language use of Austrian bi- and multilingual school children. We explore some implications of their linguistic practices with regard to social inclusion in an Austrian educational school setting. Pursuing a Dynamic Systems and Complexity Theory approach, we hypothesise that before language users actually use a language within a certain context, they have to evaluate the respective communicative situation by taking multiple contextual factors into consideration, meaning language users choose to use, or not to use, a language based on the socio-contextual information at hand. We consider these contextual factors to be most relevant as they provide the basis on which speakers can actually make use of a certain language within a given context. By drawing on examples of empirical data obtained through a language background survey, we examine some of the complex and dynamic interactions of contextual parameters influencing language choice and language use in the formal educational setting of classroom instruction. Based on the results of this study, we display a selection of the dynamic and complex interactions of pupils’ language use in one specific context as well as their language preferences and how these relate to social inclusion.

  20. Characterization of Streptococcus pneumoniae isolates from Austrian companion animals and horses.

    Science.gov (United States)

    Ginders, Maximilian; Leschnik, Michael; Künzel, Frank; Kampner, Doris; Mikula, Claudia; Steindl, Georg; Eichhorn, Inga; Feßler, Andrea T; Schwarz, Stefan; Spergser, Joachim; Loncaric, Igor

    2017-11-14

    The aim of the present study was to investigate the genetic relatedness and the antimicrobial resistance profiles of a collection of Austrian Streptococcus pneumoniae isolates from companion animals and horses. A total of 12 non-repetitive isolates presumptively identified as S. pneumoniae were obtained during routinely diagnostic activities between March 2009 and January 2017. Isolates were confirmed as S. pneumoniae by bile solubility and optochin susceptibility testing, matrix-assisted laser desorption-ionization-time of flight (MALDI-TOF) mass spectrometry and sequence analysis of a part recA and the 16S rRNA genes. Isolates were further characterized by pneumolysin polymerase chain reaction (PCR) and genotyped by multilocus sequence typing (MLST). Antimicrobial susceptibility testing was performed and resistance genes were detected by specific PCR assays. All isolates were serotyped. Four sequence types (ST) (ST36, ST3546, ST6934 and ST6937) and four serotypes (3, 19A, 19F and 23F) were detected. Two isolates from twelve displayed a multidrug-resistance pheno- and genotype. This study represents the first comprehensive investigation on characteristics of S. pneumoniae isolates recovered from Austrian companion animals and horses. The obtained results indicate that common human sero- (23F) and sequence type (ST36) implicated in causing invasive pneumococcal disease (IPD) may circulate in dogs. Isolates obtained from other examined animals seem to be host-adapted.

  1. Augmenting Austrian flood management practices through geospatial predictive analytics: a study in Carinthia

    Science.gov (United States)

    Ward, S. M.; Paulus, G.

    2013-06-01

    The Danube River basin has long been the location of significant flooding problems across central Europe. The last decade has seen a sharp increase in the frequency, duration and intensity of these flood events, unveiling a dire need for enhanced flood management policy and tools in the region. Located in the southern portion of Austria, the state of Carinthia has experienced a significant volume of intense flood impacts over the last decade. Although the Austrian government has acknowledged these issues, their remedial actions have been primarily structural to date. Continued focus on controlling the natural environment through infrastructure while disregarding the need to consider alternative forms of assessing flood exposure will only act as a provisional solution to this inescapable risk. In an attempt to remedy this flaw, this paper highlights the application of geospatial predictive analytics and spatial recovery index as a proxy for community resilience, as well as the cultural challenges associated with the application of foreign models within an Austrian environment.

  2. [Counselling customers with psychotropic vs. cardiovascular prescriptions: a survey among Austrian community pharmacists].

    Science.gov (United States)

    Hagmair, Gisela; Amering, Michaela; Kaiser, Gerda; Katschnig, Heinz

    2014-01-01

    Prescriptions for psychotropic drugs in general and their share of all prescriptions have substantially risen over the last decades. Thus, also counselling by pharmacists becomes more important in this area. This study focuses on how community pharmacists see their own role when counselling persons with prescriptions for psychotropic medication and how this differs from counselling persons with other types of prescriptions. Based on the Toronto Community Pharmacists' Questionnaire an online questionnaire was developed with the assistance of the Austrian Pharmacists Association. This instrument elicits pharmacists' attitudes toward and professional interactions with users of psychotropic drugs on the one hand and of cardiovascular medication on the other. After a pilot study the questionnaire - which was to be filled in anonymously - was put on a web portal for six months and Austrian community pharmacists were invited to answer it. 125 pharmacists completed the questionnaire. Overall it was reported, that new customers with psychotropic prescriptions were less often counselled than those with prescriptions for cardiovascular medication. The main reasons for this difference seem to be the lack of privacy in public pharmacies, the fear of stigmatising customers with psychotropic medication and a perceived lack of training concerning the treatment of mental disorders. In addition to improving such training, it was suggested that seminars and workshops for communication skills should be organised. The reduced frequency in counselling new customers with psychotropic medication is related to a lack of privacy in public pharmacies, fear of stigmatising customers and a perceived need for improving the training on the treatment of mental disorders.

  3. Augmenting Austrian flood management practices through geospatial predictive analytics: a study in Carinthia

    Directory of Open Access Journals (Sweden)

    S. M. Ward

    2013-06-01

    Full Text Available The Danube River basin has long been the location of significant flooding problems across central Europe. The last decade has seen a sharp increase in the frequency, duration and intensity of these flood events, unveiling a dire need for enhanced flood management policy and tools in the region. Located in the southern portion of Austria, the state of Carinthia has experienced a significant volume of intense flood impacts over the last decade. Although the Austrian government has acknowledged these issues, their remedial actions have been primarily structural to date. Continued focus on controlling the natural environment through infrastructure while disregarding the need to consider alternative forms of assessing flood exposure will only act as a provisional solution to this inescapable risk. In an attempt to remedy this flaw, this paper highlights the application of geospatial predictive analytics and spatial recovery index as a proxy for community resilience, as well as the cultural challenges associated with the application of foreign models within an Austrian environment.

  4. Integrated environmental protection obligations under European law, survey analysis of Austrian legislation

    International Nuclear Information System (INIS)

    Berthaler, W.

    2001-05-01

    This work focuses on legal instruments serving integrated environmental protection, especially with respect to administrative procedures concerning plant permits, and their inhorent limits. Initially, the legal and scientific approach pursued under the notion of 'integrated environmental protection' and 'environmental impact assessment' is examined and clarified in chapter A. Based thereon, chapter B deals with the obligations resulting from the EIA-Directive and - compared therewith - from the IPPC-Directive with regard to procedures for plant permits. Further, Austria's delay in fully transposing these directives is examined. When dealing with the constitutional basis for transposing the EIA- and IPPC-D into Austrian administrative law (chapter C), the inherent limits of some competence of legislation are discovered to be too narrow to ensure full compliance with EC law; only with regard to EIA, legistation is based on sound constitutional ground. The second part of the work is devoted to three areas of discussion on EIA- and IPPC-procedures under Austrian law: the scope of their applicability (chapter D), the problems of integrated evaluation and the limits of ecological expertise (chapter E) and aspects of public participation (chapter F). The study is concluded by a summary of the main results (chapter G). (author)

  5. Recent Developments Concerning Pellet Combustion Technologies - A Review of Austrian Developments

    International Nuclear Information System (INIS)

    Obernberger, I.; Thek, G.

    2006-01-01

    This paper gives an overview of recent developments concerning pellet combustion technologies in Austria. It covers basic information about the Austrian pellet market and market developments in recent years as well as about national framework conditions in Austria with regard to standards for Pellets, pellet furnaces and emission limits. A detailed overview is given of the state-of-the-art of Austrian pellet boiler technology, which is - from a technological point of view - probably the best developed market world-wide. Innovations, which have recently been developed and introduced into the market, are described. The most important innovations are new furnace developments based on CFD (Computational Fluid Dynamics) simulations, flue gas condensation systems for small-scale pellet boilers and multi-fuel concepts, where e.g. firewood and Pellets can be utilised in one boiler. Moreover, emissions from pellet furnaces are discussed and evaluated based on test stand and field measurements. In this respect, a focus is put on fine particulate emissions from pellet boilers. Finally, future developments based on ongoing research projects are described and discussed. The ongoing R and D activities focus on the further reduction of fine particulate emissions by primary and secondary measures, the utilisation of herbaceous biomass fuels and small or micro-scale CHP systems

  6. Speaking up behaviors and safety climate in an Austrian university hospital.

    Science.gov (United States)

    Schwappach, David; Sendlhofer, Gerald; Häsler, Lynn; Gombotz, Veronika; Leitgeb, Karina; Hoffmann, Magdalena; Jantscher, Lydia; Brunner, Gernot

    2018-04-26

    To analyze speaking up behavior and safety climate with a validated questionnaire for the first time in an Austrian university hospital. Survey amongst healthcare workers (HCW). Data were analyzed using descriptive statistics, Cronbach's alpha was calculated as a measure of internal consistencies of scales. Analysis of variance and t-tests were used. The survey was conducted in 2017. About 2.149 HCW from three departments were asked to participate. To measure speaking up behavior and safety climate. To explore psychological safety, encouraging environment and resignation towards speaking up. About 859 evaluable questionnaires were returned (response rate: 40%). More than 50% of responders perceived specific concerns about patient safety within the last 4 weeks and observed a potential error or noticed rule violations. For the different items, between 16% and 42% of HCW reported that they remained silent though concerns for safety. In contrast, between 96% and 98% answered that they did speak up in certain situations. The psychological safety for speaking up was lower for HCW with a managerial function (P speak up (P speaking up behaviors for the first time in an Austrian university hospital. Only moderately frequent concerns were in conflict with frequent speaking up behaviors. These results clearly show that a paradigm shift is needed to increase speaking up culture.

  7. Strategic capacity withholding through failures in the German-Austrian electricity market

    International Nuclear Information System (INIS)

    Bergler, Julian; Heim, Sven; Hüschelrath, Kai

    2017-01-01

    In electricity day-ahead markets organized as uniform price auction, a small reduction in supply in times of high demand can cause substantial increases in price. We use a unique data set of failures of generation capacity in the German-Austrian electricity market to investigate the relationship between electricity spot prices and generation failures. Differentiating between strategic and non-strategic failures, we find a positive impact of prices on non-usable marginal generation capacity for strategic failures only. Our empirical analysis therefore provides evidence for the existence of strategic capacity withholding through failures suggesting further monitoring efforts by public authorities to effectively reduce the likelihood of such abuses of a dominant position. - Highlights: • We investigate the relationship between electricity spot prices and generation failures. • Announced (non-strategic) failures are found to decrease with increasing price. • Unannounced (strategic) failures of marginal technologies increase with increasing price. • Our evidence is consistent with the presence of capacity withholding strategies in the German-Austrian electricity market.

  8. The relevance and legibility of radio/TV weather reports to the Austrian public

    Science.gov (United States)

    Keul, A. G.; Holzer, A. M.

    2013-03-01

    The communicative quality of media weather reports, especially warnings, can be evaluated by user research. It is an interdisciplinary field, still uncoordinated after 35 years. The authors suggest to shift from a cognitive learning model to news processing, qualitative discourse and usability models as the media audience is in an edutainment situation where it acts highly selective. A series of field surveys 2008-2011 tested the relevance and legibility of Austrian radio and television weather reports on fair weather and in warning situations. 247 laypeople heard/saw original, mostly up-to-date radio/TV weather reports and recalled personally relevant data. Also, a questionnaire on weather knowledge was answered by 237 Austrians. Several research hypotheses were tested. The main results were (a) a relatively high level of meteorological knowledge of the general population, with interest and participation of German-speaking migrants, (b) a pluralistic media usage with TV, radio and internet as the leading media, (c) higher interest and attention (also for local weather) after warnings, but a risk of more false recalls after long warnings, (d) more recall problems with radio messages and a wish that the weather elements should always appear in the same order to faciliate processing for the audience. In their narrow time windows, radio/TV weather reports should concentrate on main features (synoptic situation, tomorrow's temperature and precipitation, possible warnings), keep a verbal “speed limit” and restrict show elements to serve the active, selective, multioptional, multicultural audience.

  9. Preliminary survey on the information campaign on nuclear energy of the Austrian Government

    International Nuclear Information System (INIS)

    Hirsch, H.

    1977-01-01

    To provide adequate, unbiased information to the public as well as basic material for future decisions concerning nuclear energy to parliament, the Austrian Government began the Information Campaign on Nuclear Energy in October 1976 and it will continue to June 1977. In the first phase of this campaign, teams of experts consisting of promoters and critics of nuclear energy discussed the various aspects of this topic in public as well as in internal debates, finally producing exhaustive reports. In the second phase, scheduled to take place in May and June 1977, these reports will be discussed in a series of symposia by representatives of the different viewpoints of the Austrian public on nuclear energy. They will then be submitted to parliament together with a summary provided by the Government. The motivation of the campaign, the preparation and execution of the first phase, as well as the first steps in the preparation of the second pahse, are described. Preliminary analyses concern: a) the interaction between the authorities, the experts and the public; b) the interaction among the experts; c) the character of the protest movement and its activities and the public activities of the promoters of nuclear energy; d) the role of the mass media and the information flow in society; and, very cursorily; e) the international echo. Preliminary conclusions are drawn on the organisation of the process of optimal transfer of information to the public, consensus-finding in society and decision-making; a comparison with experiences in other countries is attempted

  10. Water demand for ski resort development in the Austrian Alps: an Overview

    Science.gov (United States)

    Breiling, M.; Sokratov, S.

    2012-04-01

    Austria has the highest national added value from winter tourism in Europe, as well as worldwide. 15.7 million arrivals were counted in Austrian accommodation establishments in the 2010/11 winter season. There were more than 62 million overnight stays and 51.2 million skier-days were consumed. 588 million transports were carried out by more than 3000 lifts (cable cars, chair lifts and T-bars). Including indirect and induced effects, this resulted in more than 10 billion euros in added value being generated. The lack of snow in many Austrian skiing areas during the 2006/2007 winter season demonstrated the extent to which meteorological conditions influence operations. Declines in the number of skiers transported and total skier days were the result. The cable-car operators also had to struggle with little snow in the 2010/2011 winter. The Austrian Cable Car Operators' Association stated that the opening of 70-80% of all skiing areas outside of the peak season could only be assured through the use of snowmaking equipment. The central criterion for winter sports enthusiasts to make a trip is the guarantee that they will find snow at their destination and Austria's cable-car operators invest more than 100 million euros in the erection and improvement of snowmaking complexes every year to satisfy this deand. In the 2010/2011 season, this provided for 17,800 jobs. Cable car operators set up snowmaking equipment to become independent from meteorological conditions and improve the capacity utilisation of their expensive investments in transport systems in the early winter. Austria has a skiing area of around 25,400 hectares - around 17,000 hectares at altitudes between 600m and 3200m are currently suitable for snowmaking. As much as 70% of the snow is produced immediately before the start of the season. This recent trend is responsible that the irrigation pattern of Austrian land use changed significantly in the last decade. Previously maize fields and low lands in summer

  11. 25 October 2017- Austrian, German and Swiss Science Foundations signing the guest book in the Globe of Science and Innovation

    CERN Multimedia

    Ordan, Julien Marius

    2017-01-01

    Austrian, German and Swiss Science Foundations in Globe: Professor Klement Tockner, Präsident, Fonds zur Förderung der wissenschaftlichen Forschung, Austria; Professor Peter, Strohschneider, Präsident, Deutsche Forschungsgemeinschaft Germany; Professor Matthias Egger, Präsident, Schweizerischer Nationalfonds zur Förderung der Wissenschaftlichen Forschung, Switzerland

  12. ["Maintaining a Common Culture"--the German Research Foundation and the Austrian-German scientific aid in the interbellum].

    Science.gov (United States)

    Fengler, Silke; Luxbacher, Günther

    2011-12-01

    After the end of the Great War, private as well as public research funding in Austria was anaemic and slow to develop. Whereas the German state-funded Deutsche Forschungsgemeinschaft (DFG) was established as early as 1920, first steps in that direction were only taken in Austria in the late 1920s. In 1929, the Osterreichisch-deutsche Wissenschaftshilfe (ODW) was founded under the auspices of the Austrian Academy of Sciences and the DFG. Although prima facie on an equal footing, the new research funding organisation was in fact highly dependent on its German cooperation partner. The article explores for the first time ODW's position within the German and Austrian science and foreign policies, which aimed to promote the idea of unification of both states within the German Reich. A quantitative analysis of the subsidies policy in the first five years of existence shows that the ODW gave financial aid primarily to conservative research fields, affecting the intellectual balance of power in the First Austrian Republic. Policy continuities and discontinuities of the organisation in the course of the national-socialist rise to power in Germany after 1933 are examined in the second part of the article. The article thus both increases our knowledge about the most important German research funding organisation DFG, and identifies some of the fundamental structural features of Austrian science policy in the interwar years.

  13. Combining IPPC and emission trading: An assessment of energy efficiency and CO2 reduction potentials in the Austrian paper industry

    International Nuclear Information System (INIS)

    Starzer, Otto; Dworak, Oliver

    2005-01-01

    In the frame of an innovative project partnership E.V.A. - the Austrian Energy Agency accompanied the Austrian paper industry for the last 2.5 years in developing a branch specific climate change strategy. Within the scope of this project an assessment of the energy efficiency status of the branch was carried out as well as an evaluation of still realisable energy savings and CO 2 reduction potentials. The paper presents the methodology applied, which combines a top down approach (benchmarking and best practice) with a bottom up approach (on-site interviews and energy audits), supported by a huge data collection process. Within the benchmarking process all Austrian paper industry installations affected by the EU emission trading directive were benchmarked against their respective IPPC/BAT values. Furthermore an extensive list of best practice examples derived from existing or ongoing studies was compared with the energy efficiency measures already carried out by the companies ('early actions'). These theory-oriented findings were complemented by several on-site interviews with the respective energy managers as well as by detailed energy audits carried out by a consulting company, covering in total more than 80% of the Austrian paper industry's CO 2 emissions. The paper concludes with the main results of the project, presenting the pros and cons of working with IPPC documents and BAT values in terms of energy efficiency assessments. Recommendations are presented on how to improve the allocation exercise for the next emission trading period from 2008 to 2012

  14. What Does It Take to Be an Adult in Austria? Views of Adulthood in Austrian Adolescents, Emerging Adults, and Adults

    Science.gov (United States)

    Sirsch, Ulrike; Dreher, Eva; Mayr, Eva; Willinger, Ulrike

    2009-01-01

    The present study examined the defining features of emerging adulthood, subjects' conceptions of the transition to adulthood, and the perceived adult status in Austria. The sample consisted of 775 subjects (226 adolescents, 317 emerging adults, 232 adults). Results showed that most Austrian emerging adults feel themselves to be between adolescence…

  15. The regulation of social housing outcomes : A micro examination of Dutch and Austrian social landlords since financing reforms

    NARCIS (Netherlands)

    Lawson, J.M.; Nieboer, N.

    2009-01-01

    Since the 1990s, significant changes affecting financial arrangements have permeated both the Dutch and Austrian system of social housing provision. Potentially, these changes could have influenced the role and performance of social landlords in both countries. This paper explores the actual impact

  16. Austrian Lives

    OpenAIRE

    Bischof, Günter; Plasser, Fritz; Maltschnig, Eva

    2012-01-01

    Writing biographies for a long time had been a male hegemonic project. Ever since Plutarch and Sueton composed their vitae of the greats of classical antiquity, to the medieval obsession with the hagiographies of holy men (and a few women) and saints, Vasari's lives of great Renaissance artists, down to the French encyclopedists, Dr. Johnson and Lytton Strachey, as well as Ranke and Droysen the genre of biographical writing has become increasingly more refined. In the twentieth century male p...

  17. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

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

  18. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

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

  19. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

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

  20. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

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

  1. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

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

  2. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

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

  3. Strengthening of Organizational Infrastructure for Meeting IAEA Nuclear Safeguards Obligations: Bangladesh Perspective

    International Nuclear Information System (INIS)

    Mollah, A.S.

    2010-01-01

    Safeguards are arrangements to account for and control the use of nuclear materials. This verification is a key element in the international system which ensures that uranium in particular is used only for peaceful purposes. The only nuclear reactor in Bangladesh achieved critically on September 14, 1986. Reactor Operation and Maintenance Unit routinely carries out certain international obligations which need to undertake as signatory of different treaties, agreements and protocols in the international safeguards regime. Pursuant to the relevant articles of these agreements/protocols, the reactor and associated facilities of Bangladesh (Facility code: BDA- and BDZ-) are physically inspected by the designated IAEA safeguards inspectors. The Bangladesh Atomic Energy Commission (BAEC) has recently created a new division called 'Nuclear Safeguards and Security Division' for enhancing the safeguards activities as per international obligations. This division plays a leading role in the planning, implementation, and evaluation of the BAEC's nuclear safeguards and nuclear security activities. This division is actively working with USDOE, IAEA and EU to enhance the nuclear safeguards and security activities in the following areas: - Analysis of nuclear safeguards related reports of 3 MW TRIGA Mark-II research reactor; - Upgrading of physical protection system of 3 MW TRIGA Mark-II research reactor, gamma irradiation facilities, central radioactive storage and processing facility and different radiation oncology facilities of Bangladesh under GTRI programme; - Supervision for installation of radiation monitoring system of the Chittagong port under USDOE Megaports Initiative Programmes for detection of illicit trafficking of nuclear and radioactive materials; - Development of laboratory capabilities for analysis of nuclear safeguards related samples; - Planning for development of organizational infrastructure to carry out safeguards related activities under IAEA different

  4. Design and safety aspects of the Cornell cold neutron source

    International Nuclear Information System (INIS)

    Ouellet, Carol G.; Clark, David D.

    1992-01-01

    The cold neutron beam facility at the Cornell University TRIGA Mark II reactor will begin operational testing in early 1993. It is designed to provide a low background subthermal neutron beam that is as free as possible of fast neutrons and gamma rays for applied research and graduate-level instruction. The Cornell cold neutron source differs from the more conventional types of cold sources in that it is inherently safer because it uses a safe handling material (mesitylene) as the moderator instead of hydrogen or methane, avoids the circulation of cryogenic fluids by removing heat from the system by conduction through a 99.99% pure copper rod attached to a cryogenic refrigerator, and is much smaller in its size and loads. The design details and potential hazards are described, where it is concluded that no credible accident involving the cold source could cause damage to the reactor or personnel, or cause release of radioactivity. (author)

  5. FIR 1 TRIGA activity inventories for decommissioning planning

    International Nuclear Information System (INIS)

    Raety, Antti; Kotiluoto, Petri

    2016-01-01

    The objective of the study has been to estimate the residual activity in the decommissioning waste of TRIGA Mark II type research reactor FiR 1 in Finland. Neutron flux distributions were calculated with Monte Carlo code MCNP. These were used in ORIGEN-S point-depletion code to calculate the neutron induced activity of materials at different time points by modelling the irradiation history and radioactive decay. The knowledge of radioactive inventory of irradiated materials is important in the planning of the decommissioning activities and is essential for predicting the radiological impact to personnel and environment. Decommissioning waste consists mainly of ordinary concrete, aluminium, steel and graphite parts. Results include uncertainties due to assumptions on material compositions and possible diffusion of gaseous nuclides. Comparison to activity inventory estimates of two other decommissioned research reactors is also presented. (authors)

  6. About the study of irradiation effects on in-core instrumentation

    International Nuclear Information System (INIS)

    Angelino, G.

    1972-01-01

    The knowledge of in-core instrumentation performances is a very important item when irradiations of technological interest are concerned. When measurement of small changes in mechanical or thermal properties is of major importance, the effect of neutron and gamma irradiation on various transducers must be thoroughly evaluated. A rig mock-up was irradiated in the Triga Mark II Reactor of the Pavia University to assess the possibility of carrying out a study on irradiation effects on in-core instrumentation. Data on neutron flux distribution and γ-heating effect were collected from this preliminary experiment; at the same time a complete check was performed on rig assembling procedure, on the behaviour under operating conditions, and on the reactor loading and unloading operations. (author)

  7. Electrochemical corrosion characteristics of aluminium alloy 6061 T6 in demineralized water containing 0.1 % chloride ion

    International Nuclear Information System (INIS)

    Zaifol Samsu; Muhammad Daud; Siti Radiah Mohd Kamarudin; Mohd Saari Ripin; Rusni Rejab; Mohd Shariff Sattar

    2012-01-01

    Direct current electrochemical method is one of the techniques has been used to study the corrosion behaviour of metal/alloy in its environment. This paper attempts to investigate the corrosion behaviour of Al 6061 T6 immersed in Reactor TRIGA Mark II pool water containing about 0.1% NaCl content. The result shown that the corrosion rate value of the aluminium 6061 T6 increased with the presence of 0.1 % Ion Chloride content in the demineralized water reactor pool as compared to normal demineralized water. This is due to aggressiveness of chloride ion attack to metal surface. Beside corrosion rate analysis, the further tests such as corrosion behaviour diagram, cyclic polarization have been carried and the results have been reported. (author)

  8. Hanaro operation

    International Nuclear Information System (INIS)

    Lee, Ji Bok; Jeon, Byung Jin; Kwack, Byung Ho

    1997-01-01

    HANARO was configurated its first operating core in 1995. Long term operation test was conducted up to 3-1 cycle during 1996, in order to investigate the reactor characteristics due to fuel depletion and additional fuel loading. Now HANARO has accumulated 168.4 days of total operation time and 2,687.5 MWD of total thermal output. Reactor analysis, producing operation datum and its validation with test, periodic inspection and maintenance of the facility are continuously conducted for safe operation of the HANARO. Conducted the verification tests for installed utilization facilities, and successfully performed the radiation emergency drill. The shutdown report of TRIGA Mark II and III was submitted to MOST, and decommissioning will be started from 1997. (author). 70 tabs., 50 figs., 27 refs

  9. Utilization of the HANARO

    International Nuclear Information System (INIS)

    Park, Kyung Bae; Yoon, Byung Mok; Chung, Yong Sam; Han, Hyun Soo; Bang, Hong Sik; Shin, Byung Chul; Cho, Woon Gap; Kim, Young Mi; Park, Ul Jae; Moon, Jong Hwa; Kim, Joo Young; Park, Choon Deuk; Seo, Choon Ha; Lee, Young Koo; Shin, Hun Young; Han, Kwang Hee; Chung, Young Joo; Park, Woong Woo; Kim, Dong Soo; Jun, Sang Soo; Hong, Soon Buk; Min, Eun Sook; Jin, Joon Ha; Kim, Ki Yup; Nho, YOung Chang; Lee, Young Keun; Jung, Sung Hee; Park, Soon Cheol; Na, Bong Joo; Kim, Jae Ho; Paik, Sam Tae; Park, Sang Jun; Suh, Doo Whan; Lee, Jae Poong; Oh, Sam Yong; Youm, Kee Hong; Kim, Jong Kook; Gu, Jung Min; Sin, Ho Chul.

    1997-01-01

    Radioisotope facilities were operated to support research, development and production of radioisotopes. Irradiation facilities were operated to offer irradiation service to the clients. Even though intensive periodical checks and some essential maintenance had been carried out the results of RI facility maintenance seemed to be not much satisfactory due mainly to the shortage of skilled manpower and maintenance expenses. High intensity γ irradiator was normally operated 165 times for overall 2,670 hrs, and the low intensity γ irradiator was operated 89 times for overall 367 hrs, respectively. The reactor shutdown report of TRIGA Mark-II and Mark-III were submitted to MOST and the spent fuels from the core were transferred to storage racks in reactor pool for decommissioning which will be started in 1997. (author). 5 tabs., 3 figs

  10. Instrumentation for Position Sensitive Detector-Powder diffractometer at CENM-Maamora

    International Nuclear Information System (INIS)

    Messous, M.-Y.; Belhorma, B.; Labrim, H.; El-Bakkari, B.; Jabri, H.

    2013-06-01

    Linear position sensitive detectors are widely used to configure neutron diffractometer and other instruments. Necessary front-end electronics and data acquisition system was developed to fulfil such instruments built around the research reactor. In this paper, the front-end electronics dedicated to the neutron powder diffractometer which will be installed in the axial beam port of the Triga Mark II research reactor (Center of Nuclear Studies of Maamora) is described. It consists of High voltage power supply, a Position-decoder and a Multichannel analyzer and data acquisition software. The 3 He-PSD detector response exposed to the neutron flow emitted by 252 Cf source held in paraffin spheres with distinct thicknesses for moderation effect, is shown. Monte-Carlo N Particles code (MCNP) simulations were also performed to study both the detector performance and the paraffin efficiency. (authors)

  11. Austrian Business Cycle Theory: Are 100 Percent Reserves Sufficient to Prevent a Business Cycle?

    Directory of Open Access Journals (Sweden)

    Philipp Bagus

    2010-02-01

    Full Text Available Authors in the Austrian tradition have made the credit expansion of a fractional reserve banking system as the prime cause of business cycles. Authors such as Selgin (1988 and White (1999 have argued that a solution to this problem would be a free banking system. They maintain that the competition between banks would limit the credit expansion effectively. Other authors such as Rothbard (1991 and Huerta de Soto (2006 have gone further and advocated a 100 percent reserve banking system ruling out credit expansion altogether. In this article it is argued that a 100 percent reserve system can still bring about business cycles through excessive maturity mismatching between deposits and loans.

  12. Modelling the impact of changes in the interest rates on the economy: An Austrian perspective

    Directory of Open Access Journals (Sweden)

    P Le Roux

    2004-07-01

    Full Text Available Even though econometric models and yield curve analysis are useful in assessing the impact of interest rate changes on the economic structure, their power to predict the magnitude and direction of swings in the business cycle is often restricted to the use of short-term interest rates. From an Austrian school perspective on interest rates, empirical evidence suggests that the profitability of heavy industries further downstream outperforms that of light industries in the initial stages of monetary easing, due to a rising demand for investment goods and a rise in capacity utilisation levels. This paper assesses the impact of interest rates changes on the productive structure of the economy by taking into account the effect thereof on sector earnings and ultimately share prices.

  13. The Austrian school of economics in Russia: From criticism and rejection to absorption and adoption

    Directory of Open Access Journals (Sweden)

    Vladimir Avtonomov

    2018-04-01

    Full Text Available Dissemination and adoption of Western economic ideas in Russia have never been a simple process, always bearing marks of the socio-political and ideological circumstances of the country and inner processes in economics, as well as marks of the national intellectual tradition in general. It is not surprising that the history of Austrian economics in Russia was akin to a long road with many windings and turns. We can distinguish three different periods, or waves, each of them rather complex: from the 1890s until the late 1920s (introduction and, to a certain degree, adoption and criticism, from the beginning of the 1930s until the mid-1980s (hostile attitude and ignorance, and from the mid-1980s onwards (rediscovery, dissemination, and adoption.

  14. Total-reflection X-ray fluorescence analysis of Austrian wine

    Energy Technology Data Exchange (ETDEWEB)

    Gruber, X. [Atominstitut der Osterreichischen Universitaeten, 1020 Vienna (Austria); Kregsamer, P. [Atominstitut der Osterreichischen Universitaeten, 1020 Vienna (Austria); Wobrauschek, P. [Atominstitut der Osterreichischen Universitaeten, 1020 Vienna (Austria); Streli, C. [Atominstitut der Osterreichischen Universitaeten, 1020 Vienna (Austria)]. E-mail: streli@ati.ac.at

    2006-11-15

    The concentration of major, minor and trace elements in Austrian wine was determined by total-reflection X-ray fluorescence using gallium as internal standard. A multi-elemental analysis was possible by pipetting 6 {mu}l of wine directly on the reflector and drying. Total-reflection X-ray fluorescence analysis was performed with Atomika EXTRA II A (Cameca) X-rays from a Mo tube with a high-energy cut-off at 20 keV in total-reflection geometry. The results showed that it was possible to identify only by the elemental analysis as fingerprint the vineyards and year of vintage among 11 different wines.

  15. The Austrian social festival Keep the Ball Rolling in a peripheral region of Upper Styria

    Directory of Open Access Journals (Sweden)

    Gstach Isabell

    2014-03-01

    Full Text Available The “Steirische Eisenstraße” is a region located in the province of Styria in Austria, which has been struggling with a massive shift in population and age structure for some time. In 2012/13 the Austrian social festival Keep the Ball Rolling is taking place in this region. Over a period of 18 months, the social festival is providing opportunities to think of their own environment. Consequently, they can develop and implement ideas for good cohabitation and put these into practice. The main focus of this article is the demographic presentation of the “Steirische Eisenstraße” region, according to population, employment and age structure. The introduction of the social festival is fundamental in initiating successful change processes.

  16. SOCIETAL CULTURE: A COMPARISON OF ROMANIAN, AUSTRIAN AND GERMAN STUDENTS PERSPECTIVE

    Directory of Open Access Journals (Sweden)

    CATANA DOINA

    2012-07-01

    Full Text Available Our study compares the students’ view on the existing cultural practices with their ideal societal value system in compared societies. For the purpose of this investigation, Austria and Germany were selected to represent Central European values since they are seen as a ‘bridge’ between Eastern and Western European societal values. The research findings are helpful in identifying signs of cultural convergence of Romanian societal culture with Central European values. In doing so, our study will hopefully broaden the body of knowledge about the cultural harmonization between newer and older members of European Union. As seen in the literature review section, such studies started only a few years ago. Comparison of Romanian, Austrian and German students’ perspective on societal culture is performed for the first time by the authors of this study. \\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\r\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\

  17. Eight- and twelve-hour shifts in Austrian rail traffic controllers: a psychophysiological comparison

    Directory of Open Access Journals (Sweden)

    K. WOLFGANG KALLUS

    2009-09-01

    Full Text Available The present study compared a 12-hour and an 8-hour shift system in 18 Austrian rail traffic controllers. To gain objective indicators for arousal and fatigue induced by the whole workrest sequence, we recorded heart rate during the last night shift, in addition to subjective measures that included physical symptoms. A higher increase of monotony, fatigue and saturation emerged during the 8-hour compared to the 12-hour regime, together with a heart rate decrease during the last 8-hour night shift. In line with other researchers, we conclude that flexible working conditions in specific occupational groups may compensate for disadvantages of prolonged working periods, giving way to advantages of longer shifts such as longer pauses and extra days off for social and other personal activities.

  18. Total-reflection X-ray fluorescence analysis of Austrian wine

    International Nuclear Information System (INIS)

    Gruber, X.; Kregsamer, P.; Wobrauschek, P.; Streli, C.

    2006-01-01

    The concentration of major, minor and trace elements in Austrian wine was determined by total-reflection X-ray fluorescence using gallium as internal standard. A multi-elemental analysis was possible by pipetting 6 μl of wine directly on the reflector and drying. Total-reflection X-ray fluorescence analysis was performed with Atomika EXTRA II A (Cameca) X-rays from a Mo tube with a high-energy cut-off at 20 keV in total-reflection geometry. The results showed that it was possible to identify only by the elemental analysis as fingerprint the vineyards and year of vintage among 11 different wines

  19. Building positive nature awareness in pupils using the "Rainforest of the Austrians" in Costa Rica.

    Science.gov (United States)

    Aubrecht, Margit; Hölzl, Irmgard; Huber, Werner; Weissenhofer, Anton

    2013-04-01

    20 years ago, Michael Schnitzler founded the NGO "Rainforest of the Austrians" to help save one of the most diverse rainforests in Central America, the Esquinas rainforest on the Pacific coast of SW Costa Rica, from being destroyed through logging. In this abstract we present an interdisciplinary upper Austrian school project aiming at building positive awareness in pupils towards rainforest conservation by fund-raising to help purchase endangered forest areas. The acquired rainforest was donated to the Costa Rican government and became part of the National Park "Piedras Blancas". In the following, we present a chronology of events and actions of the school project. We started our rainforest project by face-to-face encounters, letting involved persons speak directly to the pupils. Dr. Huber, coordinator of the tropical rainforest station La Gamba in Costa Rica (www.lagamba.at), together with Dr. Weissenhofer, presented an introductory slide show about the "Rainforest of the Austrians". With rainforest images and sounds in their mind the pupils wrote "trips of a lifetime" stories, thus creating idyllic images of rainforest habitats. Following up on that, we visited the exhibition "Heliconia and Hummingbirds" at the Biology Center in Linz. Reports about the slide show and the exhibition followed. Tropical sites were compared by producing climate graphs of La Gamba, Costa Rica, and Manaus in Brazil. The global distribution and the decrease of rainforests were also analyzed. In biology lessons the symbiosis between plants and animals of the rainforest were worked out by searching the Internet. Flyers with profiles of rainforest animals were produced. We also discussed the ecotourism project "RICANCIE" in Ecuador using fact sheets. "RICANCIE" is a Spanish acronym standing for "Indigenous Community Network of the Upper Napo for Intercultural Exchange and Ecotourism". It was founded in 1993 aiming to improve the quality of life for some 200 indigenous Kichwa families

  20. Development of soil taxation and soil classification as furthered by the Austrian Soil Science Society

    Science.gov (United States)

    Baumgarten, Andreas

    2013-04-01

    Soil taxation and soil classification are important drivers of soil science in Austria. However, the tasks are quite different: whereas soil taxation aims at the evaluation of the productivity potential of the soil, soil classification focusses on the natural development and - especially nowadays - on functionality of the soil. Since the foundation of the Austrian Soil Science Society (ASSS), representatives both directions of the description of the soil have been involved in the common actions of the society. In the first years it was a main target to improve and standardize field descriptions of the soil. Although both systems differ in the general layout, the experts should comply with identical approaches. According to this work, a lot of effort has been put into the standardization of the soil classification system, thus ensuring a common basis. The development, state of the art and further development of both classification and taxation systems initiated and carried out by the ASSS will be shown.

  1. Scientific support, soil information and education provided by the Austrian Soil Science Society

    Science.gov (United States)

    Huber, Sigbert; Baumgarten, Andreas; Birli, Barbara; Englisch, Michael; Tulipan, Monika; Zechmeister-Boltenstern, Sophie

    2015-04-01

    The Austrian Soil Science Society (ASSS), founded in 1954, is a non-profit organisation aiming at furthering all branches of soil science in Austria. The ASSS provides information on the current state of soil research in Austria and abroad. It organizes annual conferences for scientists from soil and related sciences to exchange their recent studies and offers a journal for scientific publications. Annually, ASSS awards the Kubiena Research Prize for excellent scientific studies provided by young scientists. In order to conserve and improve soil science in the field, excursions are organized, also in cooperation with other scientific organisations. Due to well-established contacts with soil scientists and soil science societies in many countries, the ASSS is able to provide its members with information about the most recent developments in the field of soil science. This contributes to a broadening of the current scientific knowledge on soils. The ASSS also co-operates in the organisation of excursions and meetings with neighbouring countries. Several members of the ASSS teach soil science at various Austrian universities. More detail on said conferences, excursions, publications and awards will be given in the presentation. Beside its own scientific journal, published once or twice a year, and special editions such as guidebooks for soil classification, the ASSS runs a website providing information on the Society, its activities, meetings, publications, awards and projects. Together with the Environment Agency Austria the ASSS runs a soil platform on the internet. It is accessible for the public and thus informs society about soil issues. This platform offers a calendar with national and international soil events, contacts of soil related organisations and networks, information on national projects and publications. The society has access to products, information material and information on educational courses. Last but not least information on specific soil

  2. Present and future situation of Austrian petroleum supply in consideration of energy economy aspects

    Energy Technology Data Exchange (ETDEWEB)

    Filip, G

    1982-02-02

    The author attempts to show the present situation (as of 1979/80) of the Austrian petroleum industry. Section two of the study is, to a certain extent, pointing out the range of activities of the OeMV-AG, which is the most important national petroleum company. Furthermore, the most important data and figures documenting the importance of petroleum and its processing products are mentioned in that section. In many countries the energy source petroleum contributes more than 50% to the total energy supply. Especially for this reason, it is necessary to attribute a certain weight to this energy source in making forecasts. This is considered in detail mainly in the third section, and apart from imports problems and environmental protection also the recent technologies in the field of petroleum production are described. The dissertation ends with a short view to the future energy situation and its problems.

  3. Survey to identify depth of penetration of critical incident reporting systems in Austrian healthcare facilities.

    Science.gov (United States)

    Sendlhofer, Gerald; Eder, Harald; Leitgeb, Karina; Gorges, Roland; Jakse, Heidelinde; Raiger, Marianne; Türk, Silvia; Petschnig, Walter; Pregartner, Gudrun; Kamolz, Lars-Peter; Brunner, Gernot

    2018-01-01

    Incident reporting systems or so-called critical incident reporting systems (CIRS) were first recommended for use in health care more than 15 years ago. The uses of these CIRS are highly variable among countries, ranging from being used to report critical incidents, falls, or sentinel events resulting in death. In Austria, CIRS have only been introduced to the health care sector relatively recently. The goal of this work, therefore, was to determine whether and specifically how CIRS are used in Austria. A working group from the Austrian Society for Quality and Safety in Healthcare (ASQS) developed a survey on the topic of CIRS to collect information on penetration of CIRS in general and on how CIRS reports are used to increase patient safety. Three hundred seventy-one health care professionals from 274 health care facilities were contacted via e-mail. Seventy-eight respondents (21.0%) completed the online survey, thereof 66 from hospitals and 12 from other facilities (outpatient clinics, nursing homes). In all, 64.1% of the respondents indicated that CIRS were used in the entire health care facility; 20.6% had not yet introduced CIRS and 15.4% used CIRS only in particular areas. Most often, critical incidents without any harm to patients were reported (76.9%); however, some health care facilities also use their CIRS to report patient falls (16.7%), needle stick injuries (17.9%), technical problems (51.3%), or critical incidents involving health care professionals. CIRS are not yet extensively or homogeneously used in Austria. Inconsistencies exist with respect to which events are reported as well as how they are followed up and reported to health care professionals. Further recommendations for general use are needed to support the dissemination in Austrian health care environments.

  4. Lymphedema and employability - Review and results of a survey of Austrian experts.

    Science.gov (United States)

    Neubauer, Markus; Schoberwalter, Dieter; Cenik, Fadime; Keilani, Mohammad; Crevenna, Richard

    2017-03-01

    Literature about lymphedema and its influence on the ability to work and employability is limited. The aim of the present study was to investigate the opinion of Austrian experts on factors influencing the ability to work and employability in patients suffering from lymphedema. A self-administered questionnaire consisting of 6 questions was sent to 12 Austrian lymphedema experts with 6 different specializations from May to August 2016. These experts were asked about suitable and unsuitable professions, the possible influence of lymphedema on the ability to work and employability as well as about existing and additional measures to improve the return to work. The reply rate was 100% (12 out of 12). All experts agreed that lymphedema can restrict the ability to work and employability. The leading reason for limited ability to work and employability was restricted mobility or function of the affected limb along with time-consuming therapeutic modalities, pain and psychological stress. The most suitable job named was teacher and the most unsuitable job named was cook. As easements for return to work, early rehabilitation, self-management, coping strategies, patient education, employer's goodwill and employer's cooperation were reported. Furthermore, experts stressed the need for an adjustment of the legal framework as well as low-barrier and more therapy offers. Adjusted work demands seem to be of greater importance to support the ability to work and employability than recommendations for specific job profiles alone. Experts suggest an adjustment of the legal framework for affected patients, claiming a right for early rehabilitation as well as for life-long therapy. Even though some clinically useful conclusions may be drawn from this article, further research in the field is warranted.

  5. Individual-based assessment of population structure and admixture in Austrian, Croatian and German draught horses.

    Science.gov (United States)

    Druml, T; Curik, I; Baumung, R; Aberle, K; Distl, O; Sölkner, J

    2007-02-01

    All over Europe, the number of draught horses has decreased drastically during the last 50 years. As a prerequisite for efficient management decisions, we analysed the conservation status in Austrian (Noriker Carinthia - NC, Noriker Salzburg - NS), Croatian (Croatian Coldblood - C, Posavina horse - P) and German (Altmaerkisch Coldblood - A, Black Forest horse - BF, Mecklenburg Coldblood - M, Rhenish German Draught horse - R, Saxon Thuringa Coldblood - ST, Schleswig Draught horse - Sch, South German Coldblood - SG) draught horses (434) using multilocus genotypic information from 30 (effectively 27) microsatellite loci. Populations located in areas with less intensive agricultural production (C, NC, NS, P and SG) had greater diversity within the population and estimated effective population size than A, BF, Sch, M, R and ST populations. The PCA plots revealed that populations form five separate groups. The 'Noriker' group (NC, NS and SG) and the 'Rhenish' group (A, M, R and ST) were the most distinctive (pairwise F(ST) values ranged from 0.078 to 0.094). The 'Croatian' group (C and P) was in the centre, while the BF and Sch populations formed two out-groups. A posterior Bayesian analysis detected further differentiation, mainly caused by political and geographical factors. Thus, it was possible to separate the South German Coldblood from the Austrian Noriker population where no subpopulation structure was detected. The admixture analysis revealed imprecise classification between C and P populations. A small but notable separation of R from A, M and ST populations was detected, while Sch and BF populations remained as out-groups. The information obtained should aid in making efficient conservation decisions.

  6. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

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

  7. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

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

  8. The Core Conversion of the TRIGA Reactor Vienna

    International Nuclear Information System (INIS)

    Villa, M.; Bergmann, R.; Musilek, A.; Sterba, J.H.; Böck, H.; Messick, C.

    2016-01-01

    The TRIGA Reactor Vienna has operated for many years with a mixed core using Al-clad and stainless-steel (SST) clad low enriched uranium (LEU) fuel and a few SST high enriched uranium (HEU) fuel elements. In view of the US spent fuel return program, the average age of these fuel elements and the Austrian position not to store any spent nuclear fuel on its territory, negotiation started in April 2011 with the US Department of Energy (DOE) and the International Atomic Energy Agency (IAEA). The sensitive subject was to return the old TRIGA fuel and to find a solution for a possible continuation of reactor operation for the next decades. As the TRIGA Vienna is the closest nuclear facility to the IAEA headquarters, high interest existed at the IAEA to have an operating research reactor nearby, as historically close cooperation exists between the IAEA and the Atominstitut. Negotiation started before summer 2011 between the involved Austrian ministries, the IAEA and the US DOE leading to the following solution: Austria will return 91 spent fuel elements to the Idaho National Laboratory (INL) while INL offers 77 very low burnt SST clad LEU elements for further reactor operation of the TRIGA reactor Vienna. The titles of these 77 new fuel elements will be transferred to Euratom in accordance with Article 86 of the Euratom-US Treaty. The fuel exchange with the old core returned to the INL, and the new core transferred to Vienna was carried out in one shipment in late 2012 through the ports of Koper/Slovenia and Trieste/Italy. This paper describes the administrative, logistic and technical preparations of the fuel exchange being unique world-wide and first of its kind between Austria and the USA performed successfully in early November 2012. (author)

  9. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

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

  10. Multiregion reactors

    International Nuclear Information System (INIS)

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

    1979-08-01

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

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

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

  12. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

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

  13. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

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

  14. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

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

  15. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

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

  16. Teaching in Bukovina at the time of the Austrian domination. The Foundation of the University of Tchernivtsi

    Directory of Open Access Journals (Sweden)

    Vasile Baltag

    2014-07-01

    Full Text Available Teaching is a mirror that reveals how a nation defines and limits its identity in history, taking its landmarks at cultural level. The situation of education in Bukovina during the Austrian occupation was precarious, especially in the presence of the Romanian language in schools. In that sense, the Romanians of Bukovina fought against the preponderance of German language, imposed by the Austrian occupation and against the pressure exerted by the Ukrainians to impose their mother tongue in educational institutions. If the quality of the teaching of the first schools remained at a fairly low level, the time has come when, following the Western model, Bukovina raised the level of its institutions. The Theological Institute which turns into the Faculty of Theology so that the University of Tchernivtsi allowed students to complete their studies in Bukovina, without having to study in the academic centers of Liov or Vienna.

  17. Connectedness to nature and public (skin) health perspectives: results of a representative, population-based survey among Austrian residents.

    Science.gov (United States)

    Haluza, Daniela; Simic, Stana; Höltge, Jan; Cervinka, Renate; Moshammer, Hanns

    2014-01-20

    Connectedness to nature (CN) influences motivation to have contact with outdoor natural environments. Spending leisure time in natural environments is beneficial for human health and well-being. Besides these positive effects, health risks of open-air activities are mainly related to unprotected sun light exposure-associated acute and chronic skin hazards. Thus, we conducted a cross-sectional, representative telephone survey among Austrian residents to study the association of perceived CN level with sun-exposure knowledge, tanning habits, and sun protective behaviour. In total, 1,500 study subjects (50.5% females) participated in this questionnaire survey. Although knowledge about tanning and motives to tan were similar among genders, females performed more photoprotective measures and were more connected to nature (all p nature connectedness and skin health-relevant recreational habits of Austrian residents. The findings suggest to integrate hitherto neglected gender-specific Public (Skin) Health promotion when counselling on the manifold health advantages of outdoor activities.

  18. Modelling technical snow production for skiing areas in the Austrian Alps with the physically based snow model AMUNDSEN

    Science.gov (United States)

    Hanzer, F.; Marke, T.; Steiger, R.; Strasser, U.

    2012-04-01

    Tourism and particularly winter tourism is a key factor for the Austrian economy. Judging from currently available climate simulations, the Austrian Alps show a particularly high vulnerability to climatic changes. To reduce the exposure of ski areas towards changes in natural snow conditions as well as to generally enhance snow conditions at skiing sites, technical snowmaking is widely utilized across Austrian ski areas. While such measures result in better snow conditions at the skiing sites and are important for the local skiing industry, its economic efficiency has also to be taken into account. The current work emerges from the project CC-Snow II, where improved future climate scenario simulations are used to determine future natural and artificial snow conditions and their effects on tourism and economy in the Austrian Alps. In a first step, a simple technical snowmaking approach is incorporated into the process based snow model AMUNDSEN, which operates at a spatial resolution of 10-50 m and a temporal resolution of 1-3 hours. Locations of skiing slopes within a ski area in Styria, Austria, were digitized and imported into the model environment. During a predefined time frame in the beginning of the ski season, the model produces a maximum possible amount of technical snow and distributes the associated snow on the slopes, whereas afterwards, until to the end of the ski season, the model tries to maintain a certain snow depth threshold value on the slopes. Due to only few required input parameters, this approach is easily transferable to other ski areas. In our poster contribution, we present first results of this snowmaking approach and give an overview of the data and methodology applied. In a further step in CC-Snow, this simple bulk approach will be extended to consider actual snow cannon locations and technical specifications, which will allow a more detailed description of technical snow production as well as cannon-based recordings of water and energy

  19. Interaction with customers: The Application of Social Media within the Austrian Supply Chain for Food and Beverages

    OpenAIRE

    Oliver Meixner; Rainer Haas; Helmut Moosbrugger; Philipp Magdits

    2013-01-01

    Social media marketing has become a powerful tool of interaction with stakeholders. An increasing number of companies are using social media platforms to initiate active interaction and communication with current and prospective customers. Within this study, certain content and contact features, as well as social media activities of companies of the Austrian food and beverage industry were evaluated. Empirical findings concerning the threats, risks, and opportunities connected with the applic...

  20. Attitudes of Austrian veterinarians towards euthanasia in small animal practice: impacts of age and gender on views on euthanasia

    OpenAIRE

    Hartnack, Sonja; Springer, Svenja; Pittavino, Marta; Grimm, Herwig

    2016-01-01

    Background Euthanasia of pets has been described by veterinarians as ?the best and the worst? of the profession. The most commonly mentioned ethical dilemmas veterinarians face in small animal practice are: limited treatment options due to financial constraints, euthanizing of healthy animals and owners wishing to continue treatment of terminally ill animals. The aim of the study was to gain insight into the attitudes of Austrian veterinarians towards euthanasia of small animals. This include...

  1. Evaluation of selective boron absorption in liver tumors

    International Nuclear Information System (INIS)

    Chiaraviglio, D.; Grazia, F. De; Zonta, A.; Altieri, S.; Pedroni, P.; Braghieri, B.; Fossati, F.; Pinelli, T.; Perotti, A.; Specchiarello, S.; Perlini, G.; Rief, H.

    1988-01-01

    The first step was a pharmacokinetic study to identify substances which are good boron transporters and are therefore able to provide a high concentration of the nuclide with respect to the healthy hepatic tissue in the MHN. For this purpose the tumor M5076/73 (M5), which matastasizes spontaneously in liver, was inoculated subcutaneously in a group of C57B1/6 mice. Thirty days after the inoculation, when 90% of the liver was invaded by metastases, a boric acid 0.3 M solution enriched to 96% 10 B was injected into the caudal vein. The mice were sacrificed and the liver was frozen for measurements. Boron concentration in the various samples was achieved by measuring the energy distribution of α particles produced in the nuclear reaction 10 B(n, α) 7 Li induced by a thermal neutron beam extracted from the Triga Mark II reactor,

  2. Magnetic materials research with polarized neutrons

    International Nuclear Information System (INIS)

    Hammer, J.; Rauch, H.; Badurek, G.

    1980-01-01

    In order to study the mechanisms of time dependent effects in magnetic materials with superparamagnetic or spinglass behaviour as well as in ferromagnetic materials a 'dynamic neutron depolarization' system has been developed as a beam hole experiment at the TRIGA Mark II Reactor in Vienna. In the course of this experiment an increasing or decreasing polarization can be observed as a consequence of the interaction between spins of the polarized neutron beam and the magnetic structure if the magnetic clusters in the sample are stimulated by a short magnetic pulse, lasting up to a few seconds. In accordance with numerical calculations and theoretical considerations we can draw conclusions from dynamics in the range of 10 ms to 1 h within magnetic materials which give us additional information that cannot be obtained from experiments used so far

  3. Evaluation of Safety Culture Implementation and Socialization Results

    International Nuclear Information System (INIS)

    Situmorang, Johnny

    2003-01-01

    Evaluation of safety culture implementation and socialization results has been perform. Evaluation is carried out with specifying safety culture indicators, namely: Meeting between management and employee, system for incidents analysis, training activities related to improving safety, meeting with regulator, contractors, surveys on behavioural attitudes, and resources allocated to promote safety culture. Evaluation is based on observation and visiting the facilities to show the compliance indicator in term of good practices in the frame of safety culture implementation. For three facilities of research reactors, Kartini Yogyakarta, TRIGA Mark II Bandung and MPR-GAS Serpong, implementation of safety culture is considered good enough and progressive. Furthermore some indicator should be considered more intensive, for example the allocated resources, self assesment based on own questionnaire in the frame of improving the safety culture implementation. (author)

  4. Elemental analysis in bed sediment samples of Karnafuli estuarine zone in the Bay of Bengal by instrumental neutron activation analysis

    International Nuclear Information System (INIS)

    Molla, N.I.; Hossain, S.M.; Basunia, S.; Miah, R.U.; Rahman, M.; Sikder, D.H.; Chowdhury, M.I.

    1997-01-01

    The concentration of rare earths and other elements have been determined in the bed sediment samples of Karnafuli estuarine zone in the Bay of Bengal by instrumental neutron activation analysis (INAA). The samples and the standards soil-5, soil-7, coal fly ash and pond sediment were prepared and simultaneously irradiated for short and long time at the TRIGA Mark-II research reactor facility of Atomic Energy Research Establishment, Savar, Dhaka. The maximum thermal neutron flux was of the order of 10 13 n x cm -2 x s -1 . After irradiation the radioactivity of the product nuclides was measured by using a high resolution high purity germanium detector system. Analysis of γ-ray spectra and quantitative analysis of the elemental concentration were done via the software GANAAS. It has been possible to determine the concentration level of 27 elements including the rare earths La, Ce, Sm, Eu, Tb, Dy and Yb and uranium and thorium. (author)

  5. Determination of uranium and thorium in rock samples from Harargaj Anticline by instrumental neutron activation analysis

    International Nuclear Information System (INIS)

    Rahman, M.; Molla, N.I.; Sharif, A.K.M.; Basunia, S.; Islam, S.; Miah, R.U.; Hossain, S.M.; Chowdhury, M.I.; Bhuiyan, A.D.; Stegnar, P.

    1993-01-01

    Uranium and thorium were determined in geological materials such as radioactive rock samples collected from the Harargaj Anticline in Moulavi Bazar. The pure instrumental neutron activation analysis (INAA) technique was used in qualitative and quantitative analysis of the rock samples for U and Th. The samples were properly prepared together with their standards and simultaneously irradiated in a neutron flux of the order of 10 12 n*cm -2 *s -1 using the TRIGA MARK II research reactor facility at the AERE, Savar, Dhaka. After activation the samples were subjected to γ-ray spectrometry using a high purity germanium detection system. As a result of the analysis, U and Th could be determined. The data are consistent with the values reported by the ground radiometric survey group for some of the samples. (author) 7 refs.; 1 fig.; 2 tabs

  6. Personal Dosemeter of Thermal Neutron Using A Cr-39 Detector with Filter Natural LiF

    International Nuclear Information System (INIS)

    Sofyan, Hasnel; Thamrin, M.Thoyib

    1996-01-01

    The research of personal dosemeter for thermal neutron using Cr-39 detector with different thicknesses of natural LiF filter was carried out. The irradiation of Cr-39 detector with neutron source from reactor research TRIGA mark II of Rikkyo University Tokyo, Japan. Nuclear track was counted by automatic method with ASPECT ver.4.22 Series A4T124 software and manual method for correction. The result of research, the maximum of nuclear tracks was obtained at 8 mm of LiF filter was 10 mm with 11,630x10E-5 track/neutron for air radiation. And on phantom radiation, the thickness of filter was 10 mm with 11,630x10E-5 track/neutron. Its values were 3.6 and 7.5 bigger than the response of Cr-39 non filter in air and on phantom radiation, respectively

  7. TRIGA out of core gamma irradiation facility

    International Nuclear Information System (INIS)

    Rant, J.; Pregl, G.

    1988-01-01

    A possibility to irradiate extended objects in a gamma field inside the shielding water tank and above the core of operating TRIGA Mark II Reactor has been investigated. The irradiation cask is shielded with Cd cover to filter out thermal neutrons. The dose rate of the gamma field strongly depends on the distance of the irradiation position above the core. At 25 cm above the core, the gamma dose rate is 2.2 Gy/s and epithermal neutron flux is ∼ 8.10 6 ncm -2 s -1 ∼ 3 as measured by TLD (CaF 2 : Mn) dosimeters and Au foils respectively. Tentative applications of the gamma irradiation facility are in the studies of radiation induced accelerated aging and within the Nuclear Power Plant Equipment Qualification Program (EQP). A complete characterization of the neutron spectrum and optimization of the 7 radiation field within the cask has still to be performed. (author)

  8. Analysis of 125Xe electron-photon coincidence decay

    International Nuclear Information System (INIS)

    Klingberg, F.J.; Biegalski, S.R.

    2016-01-01

    As part of the verification component of the Comprehensive Nuclear-Test-Ban Treaty (CTBT), environmental gas samples originating from nuclear fission are analyzed for the presence of 131m Xe, 133m Xe, 133 Xe, and 135 Xe. In this work, the non-traditional radioxenon isotope 125 Xe was investigated. The isotope was produced as an isotopically pure sample via neutron activation of 124 Xe at the University of Texas at Austin Nuclear Engineering Teaching Lab's TRIGA MARK II Reactor. The sample was then measured using a HPGe detector as well as an ARSA-style b-c coincidence detector. Potential sources and sensitivities for production of 125 Xe are also considered for relevance to the CTBT verification mission. (author)

  9. Approach to neutronography at the LENA plant

    International Nuclear Information System (INIS)

    Altieri, S.; Pelizza, M.L.; Sturini, M.C.

    1986-01-01

    Preliminary results of neutron radiography experiments carried out with a thermal neutron beam outside the biological shielding of the University of Pavia Triga Mark II Reactor, are reported. The neutron beam is characterized by: D = 2.5 cm L/D = 50 Φ th = 7 x 10 6 n cm -2 s -1 R cd = 2. Cellulose nitrate Kodak films such as CN 85, with and without converter (BN1), were used as track detectors. CN 85 Film contrast was improved, during printing, by lighting the films up with an orthogonally incident parallel light beam. The technique was applied to monitoring of steel weldings, glass fiber composites glued with epoxydic resin as used in aerospace industries, and rubber-steel wire adhesion in rubber vulcanization. (author)

  10. Investigation of the agglomeration and amorphous transformation effects of neutron irradiation on the nanocrystalline silicon carbide (3C-SiC) using TEM and SEM methods

    Energy Technology Data Exchange (ETDEWEB)

    Huseynov, Elchin M., E-mail: elchin.h@yahoo.com [Department of Nanotechnology and Radiation Material Science, National Nuclear Research Center, Inshaatchilar pr. 4, AZ 1073 Baku (Azerbaijan); Institute of Radiation Problems of Azerbaijan National Academy of Sciences, B.Vahabzade 9, AZ 1143 Baku (Azerbaijan)

    2017-04-01

    Nanocrystalline 3C-SiC particles irradiated by neutron flux during 20 h in TRIGA Mark II light water pool type research reactor. Silicon carbide nanoparticles were analyzed by Scanning Electron Microscope (SEM) and Transmission Electron Microscopy (TEM) devices before and after neutron irradiation. The agglomeration of nanoparticles was studied comparatively before and after neutron irradiation. After neutron irradiation the amorphous layer surrounding the nanoparticles was analyzed in TEM device. Neutron irradiation defects in the 3C-SiC nanoparticles and other effects investigated by TEM device. The effect of irradiation on the crystal structure of the nanomaterial was studied by selected area electron diffraction (SAED) and electron diffraction patterns (EDP) analysis.

  11. Epiphytic lichens as quantitative biomonitors for atmospheric element deposition

    International Nuclear Information System (INIS)

    Jeran, Z.; Jacimovic, J.; Smodis, B.; Batic, F.

    2000-01-01

    Epiphytic lichens are being used as passive and active biomonitors of trace elements in Slovenia. The lichen Hypogymnia physodes (L.) Nyl. was exposed at three locations (two in the vicinity of a coal fired-power plant, and one at a reference location) for 8 months. At the same locations air particulate matter and total deposition were collected on a monthly basis. The k 0 -method of neutron activation analysis, using the TRIGA Mark II reactor at the 'Jozef Stefan' Institute, was employed for multielemental nondestructive analysis of all samples. The influence of the power plant on the concentration levels of some elements in the transplanted lichens, air particulates and total deposition is discussed and their correlation presented. (author)

  12. Preliminary study on zinc-carbon battery performance by using neutron tomography

    International Nuclear Information System (INIS)

    Abdul Aziz Mohamed; Nor Abidin Ashari; Mohd Zaid Abdullah; Junita Mohamad Saleh; Azraf Azman; Megat Harun AlRashid Megat Ahmad; Rafhayudi Jamro

    2008-08-01

    This paper describes on the discharging characteristic of zinc-carbon batteries (dry cells) by using a neutron imaging technique called a monochromatic neutron tomography. Experiment was conducted on the Nuclear Malaysia neutron tomography prototype instrument which based on 1-dimensional position sensitive neutron detector. The instrument is constructed at the small angle neutron scattering (SANS) beam line built at the one of the beam ports of TRIGA MARK II Research reactor, Malaysian Nuclear Agency, Bangi, Selangor. The main aim of this preliminary experiment was to test the instrument capability on a real industrial component. It was also aimed to understand structural and chemical changes of these battery particles after experiencing a discharging process. In this preliminary work, new and used batteries used were the products of Eveready company. (Author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, G. [Institut fuer Kernchemie, Johannes Gutenberg-Universitaet Mainz, Fritz-Strassmann-Weg 2, D-55128 Mainz (Germany)], E-mail: gabriele.hample@uni-mainz.de; Wortmann, B. [Evonik Energy Services GmbH Essen, Ruettenscheider Str. 1-3, D-45128 Essen (Germany); Blaickner, M. [Austrian Research Centers, 2444 Seibersdorf (Austria); Knorr, J. [TU Dresden, Institut fuer Energietechnik, D-01062 Dresden (Germany); Kratz, J.V. [Institut fuer Kernchemie, Johannes Gutenberg-Universitaet Mainz, Fritz-Strassmann-Weg 2, D-55128 Mainz (Germany); Lizon Aguilar, A. [Evonik Energy Services GmbH Essen, Ruettenscheider Str. 1-3, D-45128 Essen (Germany); Minouchehr, S. [Transplantationschirurgie, Universitaetsklinikum Mainz, D-55131 Mainz (Germany); Nagels, S. [Forschungszentrum Karlsruhe GmbH, Institut fuer Strahlenforschung (ISF), Postfach 3640, D-76021 Karlsruhe (Germany); Otto, G. [Transplantationschirurgie, Universitaetsklinikum Mainz, D-55131 Mainz (Germany); Schmidberger, H. [Klinik und Poliklinik fuer Radioonkologie und Strahlentherapie, Universitaetsklinikum Mainz, D-55131 Mainz (Germany); Schuetz, C.; Vogtlaender, L. [Institut fuer Kernchemie, Johannes Gutenberg-Universitaet Mainz, Fritz-Strassmann-Weg 2, D-55128 Mainz (Germany)

    2009-07-15

    The TRIGA Mark II reactor at 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.

  14. Boron absorption imaging in rat lung colon adenocarcinoma metastases

    Energy Technology Data Exchange (ETDEWEB)

    Altieri, S [Dipartimento di Fisica Nucleare e Teorica Universita degli Studi di Pavia (Italy); Bortolussi, S [Dipartimento di Fisica Nucleare e Teorica Universita degli Studi di Pavia (Italy); Bruschi, P [Dipartimento di Fisica Nucleare e Teorica Universita degli Studi di Pavia (Italy); Fossati, F [Dipartimento di Fisica Nucleare e Teorica Universita degli Studi di Pavia (Italy); Vittor, K [Dipartimento di Fisica Nucleare e Teorica Universita degli Studi di Pavia (Italy); Nano, R [Dipartimento di Biologia Animale Universita degli Studi di Pavia (Italy); Facoetti, A [Dipartimento di Biologia Animale Universita degli Studi di Pavia (Italy); Chiari, P [Dipartimento di Fisica Nucleare e Teorica Universita degli Studi di Pavia (Italy); Bakeine, J [Dipartimento di Scienze Biomediche e Biotecnologie Universita degli Studi di Brescia (Italy); Clerici, A [Dipartimento di Chirurgia Universita degli Studi di Pavia (Italy); Ferrari, C [Dipartimento di Chirurgia Universita degli Studi di Pavia (Italy); Salvucci, O [Dipartimento di Scienze Biomediche e Biotecnologie Universita degli Studi di Brescia (Italy)

    2006-05-15

    Given the encouraging results from our previous work on the clinical application of BNCT on non-resectable, chemotherapy resistant liver metastases, we explore the possibility to extend our technique to lung metastases. A fundamental requirement for BNCT is achieving higher {sup 10}B concentrations in the metastases compared to those in healthy tissue. For this reason we developed a rat model with lung metastases in order to study the temporal distribution of {sup 10}B concentration in tissues and tumoral cells. Rats with induced lung metastases from colon adenocarcinoma were sacrificed two hours after intraperitoneal Boronphenylalanine infusion. The lungs were harvested, frozen in liquid nitrogen and subsequently histological sections underwent neutron autoradiography in the nuclear reactor Triga Mark II, University of Pavia. Our findings demonstrate higher Boron uptake in tumoral nodules compared to healthy lung parenchyma 2 hours after Boronphenylalanine infusion.

  15. Use of boron nitride for neutron spectrum characterization and cross-section validation in the epithermal range through integral activation measurements

    Science.gov (United States)

    Radulović, Vladimir; Trkov, Andrej; Jaćimović, Radojko; Gregoire, Gilles; Destouches, Christophe

    2016-12-01

    A recent experimental irradiation and measurement campaign using containers made from boron nitride (BN) at the Jožef Stefan Institute (JSI) TRIGA Mark II reactor in Ljubljana, Slovenia, has shown the applicability of BN for neutron spectrum characterization and cross-section validation in the epithermal range through integral activation measurements. The first part of the paper focuses on the determination of the transmission function of a BN container through Monte Carlo calculations and experimental measurements. The second part presents the process of tayloring the sensitivity of integral activation measurements to specific needs and a selection of suitable radiative capture reactions for neutron spectrum characterization in the epithermal range. A BN container used in our experiments and its qualitative effect on the neutron spectrum in the irradiation position employed is displayed in the Graphical abstract.

  16. Experimental cross section for the {sup 152}Sm(n, γ){sup 153}Sm reaction at 0.0334 eV

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M. Shuza; Datta, Tapash Kumar; Hossain, Syed Mohammod; Zakaria, A.K.M.; Islam, Mohammad Amirul; Naher, Kamrun; Shariff, M. Asad; Yunus, S.M. [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology; Afroze, Nasmin [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology; Jahangirnagar Univ., Dhaka (Bangladesh). Dept. of Physics; Islam, S.M. Ajharul [Jahangirnagar Univ., Dhaka (Bangladesh). Dept. of Physics

    2014-10-01

    The neutron capture cross section for the {sup 152}Sm(n, γ){sup 153}Sm reaction at an energy of 0.0334 eV was measured for the first time using monochromatic neutrons of a powder diffractometer at the TRIGA Mark II nuclear reactor at Dhaka, Bangladesh. The {sup 197}Au(n, γ){sup 198}Au reaction was used to monitor the neutron beam intensity. The radioactivity of the products was determined via high resolution γ-ray spectrometry. The obtained cross section value is 184 ± 22b, which is consistent with both the ENDF/B-VII and TENDL-2012 data libraries. The measured value at 0.0334 eV and the previous data at 0.0536 eV confirm the reliability of the data in the above libraries. (orig.)

  17. Small angle neutron scattering using a triple axis spectrometer

    International Nuclear Information System (INIS)

    Ahmed, F.U.; Goyal, P.S.; Kamal, L.; Yunus, S.M.; Datta, T.K.; Rahman, M.O.; Azad, A.K.; Begum, S.; Zakaria, A.K.

    1994-01-01

    SANS techniques has been developed on a triple axis neutron spectrometer at TRIGA Mark II (3 MW) research reactor, AERE, Savar, Dhaka, Bangladesh. Double crystal (with very small mosaic spread ∼ 1 min.) diffraction known as Bonse and Hart's method has been employed. Such a device is a useful tool for small angle scattering in the Q range between 10 -5 and 10 -1 Angstroms -1 and for real time experiments at short time scales. Therefore, large objects and large distance interparticle correlations can be easily investigated. The results of SANS' measurements using alumina (A1 2 0 3 ) sample are presented. The radius of gyration has been determined and the data has been fitted to the scattering function of a sphere. 9 refs., 6 figs.,

  18. Determination of trace elements in metallic materials by neutron activation analysis

    International Nuclear Information System (INIS)

    Grassi, B; La Vecchia, G M; Manera, S; Salvini, A; Zenoni, A

    2006-01-01

    The aim of the present paper is to verify the applicability of neutron activation analysis to a metallurgic problem as a possible alternative technique to the standard investigation methodologies. A first series of measurements was performed in order to check the feasibility of irradiation and counting over metallic samples. Some of the feared problems concerned an excessive activation of the matrix and the consequent difficulties in the spectrum interpretation, as well as the removal of the radioactive waste created by the irradiation. Afterwards, a second series of measurements was performed to collect results aimed at the solution of a specific metallurgic case. The tests were performed at the TRIGA MARK II reactor facility of the LENA (Laboratorio Energia Nucleare Applicata) Institute of the Pavia University

  19. Electrical characterization of commercial NPN bipolar junction transistors under neutron and gamma irradiation

    Directory of Open Access Journals (Sweden)

    OO Myo Min

    2014-01-01

    Full Text Available Electronics components such as bipolar junction transistors, diodes, etc. which are used in deep space mission are required to be tolerant to extensive exposure to energetic neutrons and ionizing radiation. This paper examines neutron radiation with pneumatic transfer system of TRIGA Mark-II reactor at the Malaysian Nuclear Agency. The effects of the gamma radiation from Co-60 on silicon NPN bipolar junction transistors is also be examined. Analyses on irradiated transistors were performed in terms of the electrical characteristics such as current gain, collector current and base current. Experimental results showed that the current gain on the devices degraded significantly after neutron and gamma radiations. Neutron radiation can cause displacement damage in the bulk layer of the transistor structure and gamma radiation can induce ionizing damage in the oxide layer of emitter-base depletion layer. The current gain degradation is believed to be governed by the increasing recombination current in the base-emitter depletion region.

  20. Determination of microdistribution of boron in metals

    Energy Technology Data Exchange (ETDEWEB)

    Illic, R; Najzer, M; Rant, J [J. Stefan Institute, Ljubljana (Yugoslavia)

    1976-07-01

    A neutron induced autoradiographic technique was used for the determination of the boron microdistribution in metals. The specimens, which were in close contact with a LR 115 SSTD, were irradiated in the exposure room of the TRIGA Mark II reactor in Ljubljana. The spatial resolution of the autoradiographic image recorded by the LR 115 detector was found to be influenced mainly by the size of the reaction product tracks. The track diameter of a normally etched detector was about 7 {mu}m. An appreciable reduction of track size was achieved by pre-etching the detector foil before neutron irradiation. By this procedure it was possible to obtain a track diameter as small as 1 {mu}m and correspondingly to improve the spatial resolution of the autoradiographs of type EC 80 steel and Al Mg 3 alloy which contain 30 and 2 ppm of boron respectively. (author)