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Sample records for austrian triga-mark-ii reactor

  1. Experience in the operation and maintenance of the Austrian TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    The Austrian TRIGA Mark II reactor ia in operation since March 1962. The reactor instrumentation, core design and irradiation facilities and operation are described. Besides steady state power and pulse operation, square wave operation has been installed 1968, allowing power squares up to 750 kW. A Survey of reactor operation and experiments is given

  2. Decommissioning of TRIGA Mark II type reactor

    International Nuclear Information System (INIS)

    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

  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. TRIGA Mark-II, III reactor operation

    International Nuclear Information System (INIS)

    TRIGA Mark-II reactor has been primarily utilized as usual for the fundamental reactor experiments for university students. The annual operating time is 1,100 hours and the gross thermal output is 17,159 KWH, having consumed 0.88g of U-235. The reconstuction work for the control console of this reactor is now in progress and will be completed in early part of 1982. TRIGA Mark-III reactor has been operated mainly for radioisotope production, test pin irradiation and activation analysis, etc., as well as solid state physics experiments using the beamports. The annual operatino. time is amounted to 3,530 hours being the longest since the beginning of its criticality, and the gross thermal output is 4,113,013 KWH, whereas the U-235 consumption is estimated at 212.82 g. 462 samples were irradiated to produce 9 kinds of radioisotopes. In order to carry out the test pin irradiation experiment, the core configuration of TRIGA Mark-III was changed by loadinq 6 fresh fuels at G-ring as of July 1981 and a new irradiation facility consisting of 14 tubes was manufactured in place of Rotary Specimen Rack. Then 7 kinds of physics experiments were performed over a two week period to scrutinize the chanaed core characteristics. In addition, the present TRIGA Mark-III reactor fuel storage tank was enlarged and the distilled water production facility was renewed to improve its production efficiency. (Author)

  5. Evaluation of TRIGA Mark II reactor in Turkey

    International Nuclear Information System (INIS)

    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.)

  6. Component and operation experience of reactor TRIGA MARK II

    International Nuclear Information System (INIS)

    Reactor TRIGA MARK II is Jozef Stefan Institute's research reactor. It has been operating since 1966. A probabilistic approach of reactor safety estimation was used first in 1989 when a Probabilistic Safety Analysis (PSA) of the reactor was performed. A lack of reactor component data was found as the major problem in probabilistic assessment. It was decided to continue the work with specific data base development. The project has been divided in two phases. In the first phase specific data from year 1985 to 1990 were collected. In the second phase the collected data were treated. The comparison of generic and specific data showed significant difference between the generic and specific data and leads to a conclusion that a generic data based PSA has a limited credibility indicating that there is a need to build a specific data base for research reactors. The TRIGA MARK II research reactor has three major purposes: operator training, research involving neutrons and isotope production. The paper represents specific data base formation for TRIGA MARK II research reactor in Podgorica. Specific data on reactor scrams, components operation and human errors were collected. The data of fifteen components were estimated by classical and Bayesian method. The results of both methods are very different. Because of good specific data the results of classical methods were preferred. The comparison of specific and generic data showed that there is a great need to build a specific data base for research reactors. It is expected to use the specific data for existing PSA of TRIGA MARK II reactor reevaluation and optimisation of its operation. (authors)

  7. Power stabilization in CREN-K TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    In order to eliminate power oscillations in the TRIGA MARK II reactor at the 'Centre Regional d'Etudes Nucleaires de Kinshasa' (CREN-K), Zaire, specially made adapters were put around the control rods in the top grid plate. The paper briefly describes how investigations were made to find out the basic reason of the power oscillations and the way these adapters were conceived and installed. (author)

  8. The current status of Bandung Triga Mark II reactor, Indonesia

    International Nuclear Information System (INIS)

    Full text: The Bandung TRIGA Mark II Reactor - Indonesia was started-up on October 10, 1964 and it has been operated at power level of 250 kw. The facility has been, operated for research, production of radioisotopes and training. In 1971, the reactor has been upgraded from 250 kw to 1000 kw. Since that time the facility has been safely operating at various power levels of a maximum 1000 kw until February 1996, even though the reactor tank is kept unchanged. For a highly reliable reactor that can back-up the Ga Siwabessy Multipurpose Reactor - Jakarta, Indonesia, in producing sufficient radioisotopes, a higher power reactor is needed. This can be accomplished by increasing the thermal power of current TRIGA Mark II Bandung Reactor to 2000 kw as well as by enhancing the inherent and engineered safety features of the current reactor. The upgrading of reactor power shall ensure the increasing of neutron flux in the beam ports; hence the experiments such as neutron radiography, time of flight spectrometry and other nuclear physic experiments can be conducted better. For that the reactor tank, the number and configuration of fuel element, instrumentation and control rod, primary cooling system, secondary cooling system, water treatment system, shielding, etc. have been changed, and an Emergency Core Cooling System (ECCS) was added. One additional control rod, core configuration modification and enhancement of reactor shielding, shall increase the safety margin so that the reactor could be operated at a maximum power of 2000 kw. At the middle of May 2000 cold test (non-nuclear commissioning) was done, and continued to hot test (nuclear commissioning). Since June 24, 2000 the TRIGA Mark II Bandung has been operated at 2000 kw

  9. Thermal - hydraulic analysis of the ITU TRIGA Mark - II reactor

    International Nuclear Information System (INIS)

    Experimental and analytical studies have been performed to find out the temperature distribution, as a function of reactor power, in the TRIGA Mark-II reactor at Istanbul Technical University. A two-dimensional computer code was written in FORTRAN-77 language numerically solves heat conduction equation using finite difference method at the steady state. The calculated results for fuel temperature and coolant temperature distribution in the reactor core for different reactor power were compared with the experimental data. Agreements between experiment and results from the computer program are fairly good

  10. Operational experience data base of TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Two kinds of operational data available from operator logs: component failure-event data and abnormal event scenario information can be effectively used in PSA. Most operating data collection systems are aimed at improving the safety and availability of research reactors or commercial plants. This paper describes our failure-event data collection scheme, suitable for reliability and safety evaluations. Following the proposed data collection scheme the last five years operational experience was analysed and computerized data base for Triga Mark II reactor was developed. (orig.)

  11. The optimal control of ITU TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    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)

  12. Accident scenarios of the TRIGA Mark II reactor in Vienna

    Energy Technology Data Exchange (ETDEWEB)

    Villa, Mario, E-mail: mvilla@ati.ac.a [Vienna University of Technology, Atominstitut, Stadionallee 2, 1020 Wien (Austria); Haydn, Markus [Vienna University of Technology, Atominstitut, Stadionallee 2, 1020 Wien (Austria); Steinhauser, Georg, E-mail: georg.steinhauser@ati.ac.a [Vienna University of Technology, Atominstitut, Stadionallee 2, 1020 Wien (Austria); Boeck, Helmuth [Vienna University of Technology, Atominstitut, Stadionallee 2, 1020 Wien (Austria)

    2010-12-15

    The safety report of the TRIGA Mark II reactor in Vienna includes three accident scenarios and their deterministic dose consequences to the environment. The destruction of the cladding of the most activated fuel element, the destruction of all fuel elements and a plane crash were considered scenarios in that report. The calculations were made in 1978 with the software program named STRISK. In this paper, the program package PC Cosyma was applied on the TRIGA Mark II reactor in Vienna and the deterministic consequences of the scenarios to the environment were updated. The fission product inventories of all fuel elements were calculated with ORIGEN2. To get meteorological data of the atmospheric condition around the release area, a weather station was installed. The release parameters were taken from the safety report or were replaced by worst case parameters. This paper focuses on two accident scenarios: the destruction of the cladding of the fuel element with the highest activity content and the case of a large plane crash. The current accident scenarios show good agreement with the calculations from 1978, hence no technical modifications in the safety report of the TRIGA reactor Vienna were necessary. Even in the very worst case scenario - complete destruction of all fuel elements in a large plane crash - the expected doses in the Atominstitut's neighborhood remain moderate.

  13. Accident scenarios of the TRIGA Mark II reactor in Vienna

    International Nuclear Information System (INIS)

    The safety report of the TRIGA Mark II reactor in Vienna includes three accident scenarios and their deterministic dose consequences to the environment. The destruction of the cladding of the most activated fuel element, the destruction of all fuel elements and a plane crash were considered scenarios in that report. The calculations were made in 1978 with the software program named STRISK. In this paper, the program package PC Cosyma was applied on the TRIGA Mark II reactor in Vienna and the deterministic consequences of the scenarios to the environment were updated. The fission product inventories of all fuel elements were calculated with ORIGEN2. To get meteorological data of the atmospheric condition around the release area, a weather station was installed. The release parameters were taken from the safety report or were replaced by worst case parameters. This paper focuses on two accident scenarios: the destruction of the cladding of the fuel element with the highest activity content and the case of a large plane crash. The current accident scenarios show good agreement with the calculations from 1978, hence no technical modifications in the safety report of the TRIGA reactor Vienna were necessary. Even in the very worst case scenario - complete destruction of all fuel elements in a large plane crash - the expected doses in the Atominstitut's neighborhood remain moderate.

  14. The reactor noise analysis for a TRIGA Mark-II

    International Nuclear Information System (INIS)

    For the purpose of measurement of reactor kinetic parameter, rossi-α experiment in TRIGA Mark-II reactor are performed. The past neutron noise measurement which is using HARDWARE have had defects of inaccuracy. In this study, I developed SOFTWARE to betterment of these defects and using it investigated α which is reciprocal of prompt period. To collect neutron pulses, developed data acquisition system using 16 bit personal computer (IBM-AT) and developed pascal language program to analysis neutron pulses. As a result of experiment, α is 103, 5, 155.6, 172.7, 238.7, 266.5 (1/sec) at -1, -20, -40, -60, -80, (cent) respectively, and compare it with other experiment data convinced accurate, know S/B ratio must be larger then 10% and in case of thermal reactor, low power reactor such as AGN-201 is needed to neutron noise analysis. (Author)

  15. Preliminary neutronic design of TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    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

  16. 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.)

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

    International Nuclear Information System (INIS)

    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.)

  18. On Line Measurement of Reactivity Worth of TRIGA Mark-II Research Reactor Control Rods

    OpenAIRE

    Nusrat Jahan; Mamunur M. Rashid; F. Ahmed; M. G. S. Islam; M. Aliuzzaman; Islam, S.M.A

    2011-01-01

    The reactivity worth measurement system for control rods of the TRIGA MARK-II research reactor of Bangladesh has been design and developed. The theory of the kinetic technique of measuring reactivity has been used by this measurement system. The system comprises of indigenous hardware and software for online acquisition of neutron flux signals from reactor console and then computes the reactivity worth accordingly. Here for the TRIGA MARK-II research reactor, the reactivity measurement system...

  19. Proposal of LDR Ir-192 Production in the TRIGA Mark II Research Reactor

    International Nuclear Information System (INIS)

    The TRIGA MARK II research reactor in Vienna provides some irradiation positions with different flux distribution. In this regard, a case study is under investigation to appraise the possibility of medical radioisotope production in Vienna. For this purpose, neutron flux mapping and the axial neutron flux distribution are calculated by MCNP5 for the TRIGA Mark II core. This paper describes the feasibility of Low Dose Rate (LDR) 192Ir production in the core of the low power research reactor. (author)

  20. Current research projects at the Austrian TRIGA Mark II. Location of failed fuel elements in Austrian TRIGA Mark II

    International Nuclear Information System (INIS)

    The system developed at the Atominstitut monitors the radioactive Krypton- and Xenon nuclides in the primary water circuitry and allows selective control of any fuel element for its fission gas release. A suspected fuel element is enclosed in an underwater capsule attached in the reactor tank. Water is pumped along the fuel element to a vacuum degasser where the gases are separated from the tank water. The degassed water is returned to the reactor pool while the gases are pumped to a very sensitive proportional counter. The fuel elements of the TRIGA core were checked by the described procedure

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

    International Nuclear Information System (INIS)

    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 99mTc, which is the most widely used radionuclide in diagnostic nuclear medicine. The methods were developed for the production of the following isotopes: 18F, 85mKr, 24Na, 82Br, 64Zn, 125I. 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

  2. Neutron Imaging Using Neutrons From TRIGA MARK II PUSPATI Reactor

    International Nuclear Information System (INIS)

    This article reports about the implementation of neutron imaging work utilizing neutron beam from TRIGA MARK II PUSPATI collimation channels. Two methods have been implemented namely radiography and tomography. Advantage of these methods is the fact that, radiograms are obtained from normal radiographic imaging methodology and they are the projections used for tomographic image reconstruction. Therefore, both radiogram and tomogram are obtained consecutively. The method has been implemented on the round robin test sample for contrast and resolution measurement and also to some archaeological objects. (author)

  3. The Application of Estimator Module for Controlling of TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    The estimator module application for control TRIGA Mark II reactor have been done. This application have purpose to help operator quickly and exactly when they control reactor reactivity. Which this module, if in the reactor will do experiment ( neutron activation, radioisotope production ect.) so the operator not need to calculate probability of reactivity changes. The result of estimator is close to measurements result (< 7 sec.), it is cause estimator can be used as equipment that can be used to help operation of TRIGA Mark II. (author)

  4. 44 years of operation - The successful fuel history of the TRIGA Mark II reactor Vienna

    International Nuclear Information System (INIS)

    A review is given on the fuel element situation of the TRIGA Mark II reactor Vienna after 44 years of operation. 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 11.5 g per year. Presently we have 82 TRIGA fuel elements in the core, 51 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. (author)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

  7. Numerical simulation of non-steady state neutron kinetics of the TRIGA Mark II reactor Vienna

    OpenAIRE

    Riede, Julia; Boeck, Helmuth

    2013-01-01

    This paper presents an algorithm for numerical simulations of non-steady states of the TRIGA MARK II reactor in Vienna, Austria. The primary focus of this work has been the development of an algorithm which provides time series of integral neutron flux after reactivity changes introduced by perturbations without the usage of thermal-hydraulic / neutronic numerical code systems for the TRIGA reactor in Vienna, Austria. The algorithm presented takes into account both external reactivity changes...

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

    OpenAIRE

    Cammi, Antonio; Zanetti, Matteo; Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica; Magrotti, Giovanni; Prata, Michele; Salvini, Andrea

    2015-01-01

    In this work, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor of the University of Pavia is performed by coupling Monte Carlo (MC) simulation for neutronics with "Multiphysics" model for thermal-hydraulics. Neutronic analyses have been performed starting from a MC model of the entire reactor system, based on the MCNP5 code, that was already validated in fresh fuel and zero-power configuration (in which thermal effects are negligible) using the availabl...

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

    International Nuclear Information System (INIS)

    This paper aims to describe the modification of the radial beam port of ITU (İstanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au–Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented. - Highlights: • Using MCNP5, radial beam port of ITU TRIGA Mark II research reactor is modified. • Polyethylene and Cerrobend collimators are used to modify the beam port. • Results of two-group neutron/photon flux are presented. • Monte Carlo results are compared with experimental results

  10. 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. PMID:25576735

  11. Decontamination and decommissioning project status of the TRIGA Mark-II and III reactors in Korea

    International Nuclear Information System (INIS)

    The decontamination and decommissioning (D and D) project of the TRIGA Mark-II and Mark-III was started in January 1997, after their shutdown in 1995 due to their life and the operation of a new research reactor, HANARO, at the KAERI site in Taejon. Preparation of the decommissioning plan and environmental impact assessment, and setting up of licensing procedure and documentation for the project were performed in 1997. At the end of 1997, Hyundai Engineering Company (HEC) was selected as the main contractor to do design and licensing documentation for the D and D of both reactors. British Nuclear Fuels Plc. (BNFL) was the technical assisting partner to Heck. Licensing documents were submitted to the Ministry of Science and Technology (MOST) at the end of 1998. And the Korea Institute of Nuclear Safety (KINS) is reviewing the documents. Practical work of the D and D will start at the end of 1999 upon the government issues the license. In the meantime, July 1998, all spent fuels from the TRIGA Mark-II and III were safely transported to the US. The foremost part of the D and D work will be the TRIGA Mark-III reactor hall that will be used as a temporary storage of radioactive waste produced during the D and D work, and followed by the TRIGA Mark-II and auxiliary facilities. This paper summarizes the current status and future plans for the D and D work. (author)

  12. TRIGA mark-II,III reactor safety re-evaluation

    International Nuclear Information System (INIS)

    For two years of 1990 and 1991, the safety of TRIGA Mk-II and III reactor has been re-evaluated. For this, domestic rules on research reactors has been reviewed, and as it was judged that standards on research reactors in USA is applicable to our ones it was evaluated whether TRIGA Mk-II and III reactors satisfy these standards. The site parameters and the environmental impacts during normal operation and hypothetical accident conditions have been analysed, and those parts for reactor facility and structure have been rewritten to fit SAR standard format based on the review of old SAR and maintenance manuals reflecting changes after the construction. Based on this re-evaluation, SAR, Technical Specifications, Radiation Emergency Plan, Environment Report, various procedures,etc. will be amended by the reactor management project. (Author)

  13. Triga mark-II,III reactor safety re-evaluation

    International Nuclear Information System (INIS)

    In order to revise safety analysis report of old TRIGA reactors, safety re-evaluation of these reactor was started for necessary parts. This report contains the first year results of the project scheduled for two years. The guide lines of safety re-evaluation was made by translating that of nuclear power plant from the view point of TRIGA reactor confirming the basic safety philosophy as much as possible. First of all, sections of reactor history and comparison with similar reactors are made, since the actual operation records, changes, any modification of similar reactors constructed after then, etc., are realistic and valuable data from the safety aspect of old reactor. For the effectiveness of nuclear analysis, a PC based analysis system using WIMS-D/4 and VENTURE was established, and a program for the natural convection cooling analysis of TRIGA reactor was developed. As a result of thermal-hydraulic analysis it was confirmed that the operation limit of fuel temperature set at 650 deg C without any logical reason is very close to the DNB limit. (Author)

  14. New practical exercises at the JSI TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Since the 1990s the Jozef Stefan Institute (JSI) TRIGA reactor has been extensively used for performing training in experimental reactor physics. In 2012 we upgraded some of the existing and introduced some new exercises. The pulse mode operation exercise was upgraded by installation of new data acquisition system. The critical experiment exercise was improved by adding a new detector inside the reactor core and changing the data acquisition system. Now we monitor neutron population with two independent fission chambers on different locations. In the past the void reactivity coefficient exercise was performed by inserting Al tube into various positions in the reactor core and measuring the corresponding reactivity changes. In order to make the exercise more realistic, we installed a pneumatic system for generating air bubbles just below the core. The aim of the exercise is to measure reactivity changes versus flow rate and air bubble position. The second new exercise was measurement of water activation. In this exercise we installed special system which pumps the water through the core at a constant flow rate to the reactor platform, where the water activity is measured. The purpose of the exercise is to measure the 16N and 19O gamma line intensity and dose rate versus reactor power. The third new exercise, named in core flux mapping, was performed by measuring the axial fission rate distribution at various radial positions in the core. We used CEA - developed mini fission chambers and a special home developed system for moving the fission chamber in axial direction and measuring the count rate versus fission chamber position. In the paper the experiments are presented together with results. (author)

  15. Pre-Analysis of Triga Mark II Reactor Cooling System

    OpenAIRE

    AKAY, Orhan Erdal

    2012-01-01

    In this study, work of the reactor cooling system is divided into two time zone. The second cooling circuit has been that the conditions required operating. Cooling system which is the center of the heat exchanger total heat transfer coefficient correlations were calculated using the theoretical. The design values were compared with results obtained by calculation.

  16. Fuel element situation and performance data TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Electronic data acquisition of the position and movement of Triga fuel elements (FE) in the TRIGA II Vienna reactor was the objective of this project. Using one month power data and the Fuel element position in core it is possible to calculate their burnup. Fuel element performance data during 1962 to 2003 are provided. (nevyjel)

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

    Energy Technology Data Exchange (ETDEWEB)

    Matsumoto, Tetsuo [Atomic Energy Research Laboratory, Musashi Institute of Technology, Kawasaki, Kanagawa (Japan)

    1999-08-01

    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{sub 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{sub eff} overestimated the experimental data by about 1.0%{delta}k/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)

  18. Investigations of cracks in the shielding concrete of a TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Cracks in the reactor shielding concrete of the TRIGA Mark II reactor, Vienna, caused an experimental and theoretical program to investigate the crack reason. After the investigation of the mechanical concrete data, the crack motion was measured as a function of various environmental temperatures. The temperature stress in the concrete was calculated analytically and with the finite-elements method and good accordance with the actual crack distribution was found. Finally some possibilities to avoid concrete cracks in future research reactor shielding construction are outlined. (orig.)

  19. Numerical simulation of non-steady state neutron kinetics of the TRIGA Mark II reactor Vienna

    CERN Document Server

    Riede, Julia

    2013-01-01

    This paper presents an algorithm for numerical simulations of non-steady states of the TRIGA MARK II reactor in Vienna, Austria. The primary focus of this work has been the development of an algorithm which provides time series of integral neutron flux after reactivity changes introduced by perturbations without the usage of thermal-hydraulic / neutronic numerical code systems for the TRIGA reactor in Vienna, Austria. The algorithm presented takes into account both external reactivity changes as well as internal reactivity changes caused by feedback mechanisms like effects caused by temperature changes of the fuel and poisoning effects. The resulting time series have been compared to experimental results.

  20. Fuel burnup analysis of the TRIGA Mark II Reactor at the University of Pavia

    OpenAIRE

    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

    2015-01-01

    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 analyse neutron fluxes in the reactor core. The software that took care of time evolution, completely designed in-house, used the n...

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

    International Nuclear Information System (INIS)

    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 108 n/ cm2/ s. According to IAEA (2001) flux of 1.00 x 109 n/ cm2/ s requires three hours of treatment. Few modifications were needed to get higher flux. (Author)

  2. Epithermal neutron flux characterization of the TRIGA MARK II reactor, Ljubljana, Yugoslavia, for use in NAA

    International Nuclear Information System (INIS)

    The nonideality of the epithermal neutron flux distribution at a reactor site can be described by a 1/E1+α spectrum representation, with parameter α as a measure of nonideality. α-values were determined in 3 typical irradiation positions of the TRIGA MARK II reactor, Ljubljana, Yugoslavia, using the 'Cd-ratio for multi-monitor' method. The simpler 'Cd-ratio for dual monitor' method also yielded reliable results. This characterization is useful in the ko-method of NAA. (author) 18 refs.; 3 figs

  3. EVALUATION OF COOLING INSTRUMENTATION SYSTEM OF TRIGA MARK II REACTOR OF BANDUNG

    International Nuclear Information System (INIS)

    Evaluation of cooling instrumentation system of Triga Mark II reactor has been done. The reactor has been upgraded from 1 MW to 2 MW. The increasing of power is performed by changing the reactor components and systems. The reactor cooling system has important role in reactor operation, the system transfers heat produced in the core. The operation of the cooling system needed to be back up with qualified instrumentation. Evaluation has been done by doing analysis and observing the equipment design, type and clarification, performance study of instrumentation and system related to cooling system. It is known that the performance and system of Triga mark II reactor included the cooling system. It is also obtained the characteristic data of primary and secondary cooling system, piping diagram and instrumentation, emergency core cooling system. The cooling system has 4 measurement, i.e. flow rate, input and output temperature to heat exchanger, and electricity conductivity of water. The measurement can be observed from the reactor console. From this evaluation it is concluded that cooling system instrumentation followed the required criteria

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

    Science.gov (United States)

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

    2015-05-01

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

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

    International Nuclear Information System (INIS)

    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 (keff) for the TRIGA Mark II research reactor in Malaysia based on Monte Carlo method. This work has been performed to calculate the value of keff 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 keff from MCNP5 were obtained when the control fuel rods were fully inserted, the keff 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 keff value indicates the RTP reactor is in the supercritical condition, that is 1.10773±0.00083. (Author)

  6. 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.

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

    International Nuclear Information System (INIS)

    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 1015 neutrons/cm2 in irradiation time of 20 h

  8. Experience in operation and maintenance of the TRIGA Mark II reactor at the University of Pavia

    International Nuclear Information System (INIS)

    Experience in the operation and maintenance of the 250 kW steady state/250 MW pulsed TRIGA Mark II Reactor of the University of Pavia in the past two years is reported. Data for the reactor utilization and of Health Physics activity are also presented. Since the Second European Conference of TRIGA Reactor Users in 1972, reactor operation continued normally. No major troubles occurred during this time except for rotary specimen rack rotation. Maintenance of reactor facilities, including the substitution of the rotary specimen rack with a new one manufactured on-site is described. In June 1974 measurements of fluxes in the thermal column, with most of the graphite elements removed, were carried out in order to install a neutron converter in thermal column. Some results of fluxes and cadmium ratio values are reported. A description of the converter facility set up is given. (U.S.)

  9. Experience with service and maintenance of a TRIGA Mark II reactor after 24 years of operation

    International Nuclear Information System (INIS)

    The maintenance work and the inspection program carried out at the TRIGA Mark II reactor Vienna after more than two decades of reactor operation is described. With the help of a special underwater telescope all surfaces inside the reactor tank were inspected visually and two beam tubes were inspected with an endoscope. A new water purification loop was installed in 1985, which was followed by a new primary coolant circuit in 1986. The reactor bridge was dismantled, all control rod drives were serviced and some components replaced. As a result of this program it was observed that a TRIGA reactor can be serviced, improved and backfitted even after 24 years of operation with minor efforts. (author)

  10. Operation, maintenance, and utilization of 250 kW TRIGA Mark II reactor at the Institute Jozef Stefan, Ljubljana (Yugoslavia))

    International Nuclear Information System (INIS)

    At the Institute 'Jozef Stefan' in Ljubljana 250 kW TRIGA Mark II Reactor has been in operation since May 31, 1966. It is the steady state operated reactor without pulsing capabilities. In the paper the operational data, maintenance and utilization of the reactor are summarized for the first four years of reactor operation. (author)

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

    International Nuclear Information System (INIS)

    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

  12. Thermal hydraulic parameter studies of heat exchanger for the TRIGA MARK II research reactor

    International Nuclear Information System (INIS)

    Thermal Hydraulic studies have being conducted at PUSPATI TRIGA Mark II (RTP) Nuclear Research Reactor. The purpose of this study is to determine the heat transfer characteristic and heat exchanger performance at difference reactor power. Fundamental concept and a plate type application of heat exchanger in RTP are presented in this study. A plate type heat exchanger is a device for RTP reactor cooling system built for efficient heat transfer from one fluid to another. The study involves the observation of inlet and outlet temperature profile, flow rate and pressure at the reactor pool and heat exchanger. The observed parameters are compared to basic engineering calculation and the output of the study has been beneficial to evaluate the performance of newly-installed plate type heat exchanger. (author)

  13. In-situ gamma spectrometry measurements of time-dependent Xenon-135 inventory in the TRIGA Mark II reactor Vienna

    OpenAIRE

    Riede, Julia; Boeck, Helmuth

    2013-01-01

    In this work, it has been shown that the time dependent Xe-135 inventory in the TRIGA Mark II reactor in Vienna, Austria can be measured via gamma spectrometry even in the presence of strong background radiation. It is focussing on the measurement of (but not limited to) the nuclide Xe-135. The time dependent Xe-135 inventory of the TRIGA Mark II reactor Vienna has been measured using a temporary beam line between one fuel element of the core placed onto the thermal column after shutdown and ...

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

    International Nuclear Information System (INIS)

    Reactor operation at the Triga Mark II LENA plant, at the University of Pavia, in the past two years has been greatly affected by fulfilment of the new Italian fire prevention act's requirements, by the final red-tape work to get the renewal of the operation licence and by answering to the observations of Inspectors of the Italian Ministry of Labour and Social Security. All personnel was involved in the revision of manuals and prescriptions according to government rules and new ideas on modern nuclear safety. Consequently reactor operation was largely reduced due to works going on in the plant and to the lack of practicability of the Radiochemistry Laboratory. Finally, at the end of May 1990, the Reactor Operation Licence was renewed for the time period 1990-1995 by the Italian Ministry of Industry. (orig.)

  15. TRIGA MARK II first research reactor facility in Kingdom of Morocco

    International Nuclear Information System (INIS)

    The research reactor facility is located at Centre d'Etudes Nucleaires de la Maamora(CENM), located approximately 25 kilometers north of the city of Rabat. This facility will enable CNESTEN, as the operating organization, to fulfil its missions for promotion of nuclear technology in Morocco, contribute to the implementation of a national nuclear power program, and assist the state in monitoring nuclear activities for protection of the public and environment. The reactor building include TRIGA Mark II research reactor with an initial power level of 2000kW (t), and equipped for a planned future upgrade to 3,000-kilowatts.The facility is the keystone structure of CENM, and contain in addition to the TRIGA research reactor, extensively equipped laboratories and all associate support systems, structures, and supply facilities with the support of the AIEA, French CEA and LLNL (USA). The CENM with its TRIGA reactor and fully equipped laboratories will give the kingdom of Morocco its first nuclear installation with extensive capabilities. These will include the production of radioisotopes for medical, industrial and environmental uses, metallurgy and chemistry, implementation of nuclear analytical techniques such as neutron activation analysis and non-destructive examination techniques, as well as carrying out basic research programs in solid state and reactor physics. The feedback from the commissioning and the implementation of the safety standards during this phase was very interesting from safety point of view. The TRIGA Mark II research reactor at CENM achieved initial criticality on May 2, 2007 at 13:30 with 71 fuel elements and culminated with the successful completion of the full power endurance testing on 6 September, 2007.

  16. Optimization of a Potential New Core of the TRIGA Mark II Reactor Vienna

    International Nuclear Information System (INIS)

    The TRIGA Mark II Vienna is one of the last TRIGA reactors utilizing a mixed core with High Enrich Uranium (HEU) fuel. Due to the US Fuel Return Program, the Vienna University of Technology/Atominstitut (ATI) is obliged to return its HEU fuel by 2019. There is no final decision on any further utilization of the Vienna research reactor beyond that point. However, of all possible scenarios of the future, the conversion of the current core into Low Enriched Uranium (LEU) fuel and the complete replacement of all existing 83 burned FE(s) by new fresh FE(s) are investigated herein. This paper presents detailed reactor design calculations for three different reactor cores. The core 1 employs 104-type, core 2 uses 108-type and core 3 is loaded with mixed TRIGA fuels (i.e. 104 and 108). The combination of the Monte Carlo based neutronics code MCNP5, Oak Ridge Isotope Generation and depletion code ORIGEN2 and diffusion theory based reactor physics program TRIGLAV is used for this study. On the basis of this neutronics study, the amount of fuel required for a possible future reactor operation and its cost minimization is presented in this paper. The criticality, core excess reactivity, length of initial life cycle and thermal flux density distribution is simulated for three different cores. Keeping the utilization of existing fourteen 104-type FE(s) (i.e. six burned and eight fresh FE(s)) in view, the core 3 is found the most economical, enduring and safe option for future of the TRIGA Mark II reactor in Vienna. (author)

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

    International Nuclear Information System (INIS)

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

    Energy Technology Data Exchange (ETDEWEB)

    Snoj, L.; Stancar, Z.; Radulovic, V.; Podvratnik, M.; Zerovnik, G.; Trkov, A. [Josef Stefan Inst., Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Barbot, L.; Domergue, C.; Destouches, C. [CEA DEN, DER, Instrumentation Sensors and Dosimetry laboratory Cadarache, F-13108 Saint-Paul-Lez-Durance (France)

    2012-07-01

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

  19. The research reactor TRIGA Mark II of the Johannes Gutenberg-University Mainz

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, Gabriele; Eberhardt, Klaus [Mainz Univ. (Germany). Inst. of Nuclear Chemistry

    2012-10-15

    The TRIGA Mark II research reactor of the University of Mainz was built in the 1960ies on the initiative of Fritz Strassmann, co-discoverer of the fission, at that time the director of the Institute for Inorganic and Nuclear Chemistry. On August 3{sup rd}, 1965 the TRIGA Mainz reached first criticality with the insertion of the 57{sup th} fuel element in the reactor core. Two years later, in April 1967, the Nobel Prize laureate Otto Hahn initiated the first of now more than 18,000 pulses at the official inauguration. Since then, the TRIGA Mainz has operated without failure about 200 days per year. The TRIGA Mainz can be operated in the steady state mode at power levels ranging up to 100 kW{sub th}, depending on the requirements of the different experiments. Pulse-mode operation is also possible. (orig.)

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

    International Nuclear Information System (INIS)

    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)

  1. Enhancement of mechanical properties of blended polyethylene radiation capsules for the TRIGA MARK II Research Reactor

    International Nuclear Information System (INIS)

    Mechanical properties of blended polyethylene (PE) containing the antioxidant Irganox 1010 and the UV-absorber Tinuvin 326 were studied for future use as radiation capsule material for the TRIGA Mark II research reactor. High density and low density polyethylene were blended with the additives and tested for elongation at break, impact strength and gel content, before and after irradiation inside the nuclear reactor. Characterization via FTIR as well as determination of crystallization and melt transition temperatures through DSC were also conducted. It was found that the addition of the antioxidant at different amounts (from 0 to 4 phr) had various effects on the properties of the blended PE, with 0 phr being the amount at which there was the biggest increase in elongation at break and impact strength, post-irradiation. (author)

  2. The research reactor TRIGA Mark II of the Johannes Gutenberg-University Mainz

    International Nuclear Information System (INIS)

    The TRIGA Mark II research reactor of the University of Mainz was built in the 1960ies on the initiative of Fritz Strassmann, co-discoverer of the fission, at that time the director of the Institute for Inorganic and Nuclear Chemistry. On August 3rd, 1965 the TRIGA Mainz reached first criticality with the insertion of the 57th fuel element in the reactor core. Two years later, in April 1967, the Nobel Prize laureate Otto Hahn initiated the first of now more than 18,000 pulses at the official inauguration. Since then, the TRIGA Mainz has operated without failure about 200 days per year. The TRIGA Mainz can be operated in the steady state mode at power levels ranging up to 100 kWth, depending on the requirements of the different experiments. Pulse-mode operation is also possible. (orig.)

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

    International Nuclear Information System (INIS)

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

  4. A parametric thermal-hydraulic analysis of I.T.U. TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    In this study, a transient, one-dimensional thermal-hydraulic subchannel analysis for I.T.U. TRIGA Mark-II reactor was employed. The cooling of this reactor is based on natural convection; however, mixed convection is considered in modeling in order to enhance the capability of the computer code. After the continuity, conservation of energy, momentum balance equations for coolant in axial direction and heat conduction equation for fuel rod in radial direction had been written, they were discretized by using the control volume approach to obtain a set of algebraic equations. By the aid of discretized continuity and momentum balance equations, a pressure correction equation was derived. Then, a FORTRAN program called TRIGATH (TRIGA Thermal-Hydraulics) has been developed to solve this set of algebraic equations by using SIMPLE algorithm. As a result, the temperature distributions of the coolant and fuel rods as well as the velocity and pressure distributions of the coolant have been estimated. (authors)

  5. Neutronics analysis of the initial core of the TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    Highlights: → The TRIGA Mark II Vienna is modeled employing MCNP5. → The model is confirmed through three different experiments. → Initial critical, reactivity distribution and flux mapping experiment. - Abstract: The Atominstitute (ATI) of Vienna University of Technology (VUT) operates a TRIGA Mark II research reactor since March 1962. Its initial criticality was achieved on 7th March 1962 when 57th Fuel Element (FE) was loaded to the core. This paper describes the development of the MCNP model of the TRIGA reactor and its validation through three different experiments i.e. initial criticality, reactivity distribution and a thermal flux mapping experiment in the reactor core. All these experiments were performed on the initial core configuration. The MCNP model includes all necessary core components i.e. FE, Graphite Element GE, neutron Source Element (SE), Central IRradiation channel (CIR) etc. Outside the core, this model simulates the annular grooved graphite reflector, the thermal and thermalizing column, four beam tubes and the reactor water tank up to 100 cm in radial and +60 and -60 cm in axial direction. Each grid position at its exact location is modeled. This model employs the ENDF/B-VI data library except for the Sm-isotopes which are taken from JEFF 3.1 because ENDF/B-VI lacks samarium (Sm) cross sections. For the first experiment, the model predicts an effective multiplication factor (κeff) of 1.00183 with an estimated standard deviation 0.00031 which is very close to the experimental value 1.00114. The second experiment measures the reactivity values of four FE and one GE. In comparison to the MCNP results, the percent difference ranges from 4 to 22. The third experiment verifies the model at a local level with the radial and axial thermal flux density distribution in the core. Though the trends are similar, the MCNP model overestimates the radial thermal flux density in the core and underestimates these results at the core periphery.

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

    Science.gov (United States)

    Erradi, L.; Essadki, H.

    2001-06-01

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

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

    International Nuclear Information System (INIS)

    Research programs carried out at the TRIGA Mark II reactor Vienna are reported in the presentation. Many of the research programs presented at the previous TRIGA Conference in Istambul have been completed and a number of new research programs have been started some of them in cooperation or with support of the International Atomic Energy Agency. The most important project titles are: (1) Development of a laser surveillance system for spent fuel pools, (2) Identification of LWR fuel bundeles by magnetic scanning, and (3) Test of fission chambers in intense gamma fields. A damaged TRIGA fuel rod which was stored for more than 20 years has been cut in October 1983 into several pieces. The U-Zr-H samples are now being used for burn-up calibration as they contain only Cs-137. (orig.)

  8. The fuel element situation at the TRIGA mark II reactor Vienna

    International Nuclear Information System (INIS)

    The fuel history, spent fuel storage situation and recent problems covering the period from 1962 until 1.6.2001 were reviewed. After almost 40 years of TRIGA MARK II reactor Vienna operation, it must be mentioned that the experience with TRIGA fuel elements was and is excellent. During this period only 9 fuel elements had to be permanently be removed from the core and 57 fuel elements from the initial start-up are still used in the core. A careful fuel management and a frequent fuel inspection is of most importance, fuel elements should be moved at least two-times a year from their core position to check free movement and a 180 deg. rotation of the fuel element is also recommended (nevyjel)

  9. Characterization of the neutron flux gradients in typical irradiation channels of a TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    The neutron distribution in a defined volume (gradient) for different matrices (air, water, cellulose, biological material and silicon dioxide) in two typical irradiation channels (pneumatic tube (PT) and IC40-channel in the carousel facility) in the TRIGA Mark II reactor at the Jozef Stefan Institute (IJS) was studied. Experiment was based on inserting Fe wires (flux monitors) into the chosen matrices. The wires were cut into small pieces after irradiation and the induced activities of 59Fe measured. The results showed that for the studied geometry the average spatial thermal neutron flux inhomogeneities (for five studied matrices) are about 2.3% in the PT-channel and about 2.9% in the IC40-channel. (author)

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

    International Nuclear Information System (INIS)

    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 100 pcm. Further validation was performed with analyses of the normalized reaction rates and computations of kinetic parameters for various core configurations. - Highlights: • TRIGA Benchmark keff calculated with the TRIPOLI code. • Reaction rate profiles in TRIGA calculated with TRIPOLI code. • TRIPOLI model of the JSI TRIGA was validated. • TRIGA Kinetic parameters were calculated with TRIPOLI code. • All results are in good agreement, largest discrepancies due to nuclear data

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

  13. Utilization and operating experience of the 250 kw TRIGA Mark II research reactor in Ljubljana

    International Nuclear Information System (INIS)

    In its 35th year, the TRIGA Mark II 250 kW pulsing research reactor in Ljubljana is continuing its busy operation. With the maximum neutron flux in the central thimble of 10 13 n/cm 2 sec and many sample radiation positions the reactor has been used to perform many experiments in the following fields: solid state physics (elastic and inelastic neutron scattering), neutron dosimetry, neutron radiography, reactor physics including burn up measurements and calculations, boron neutron capture therapy and neutron activation analysis which represents one of the major usage of our reactor. Besides these, applied research around the reactor has been conducted, such as doping of silicon monocrystals, a routine production of various radioactive isotopes for industry ( 60Co, 64Zn, 24Na, 82Br) and medical use ( 18F, 99m Tc, etc.) and other activities. During the past decade the reactor was almost completely reconstructed (new grid plates, the control mechanisms and the control unit, modification of the spent fuel storage pool, etc). The main novelty in the reactor physics and operation features of the reactor was the installation of a pulse rod, therefore the reactor can be operated in a pulse mode. After reconstruction, the core was loaded with fresh 20% enriched fuel elements. In 1999 all spent fuel elements were shipped to the USA. (author)

  14. Utilization and operating experience of the TRIGA Mark II research reactor in Ljubljana

    Energy Technology Data Exchange (ETDEWEB)

    Dimic, V. (J. Stefan Institute, Ljubljana (Slovenia))

    1999-12-15

    The operating experience of the 250 kW TRIGA Mark-II reactor of the J. Stefan Institute in Ljubljana, Slovenia in the years 1996 and 1997 is reported. The reactor has been in operation without long undesired shut-down. In 1996 the production of energy was 401 MWh (around 1600 hours in operation) and there was 7 unplanned shut-downs because of electricity broke down. In 1997 the production of energy was 272 MWh (around 1090 hours in operation). In 1991 and 1997 the reactor was almost completely reconstructed and upgraded. The reconstruction consisted mainly of replacing the grid plates, the control rod mechanisms and the control unit. Recently, the new PC based system was adopted and developed to collect the operational radiation data of the reactor. The new wiring of the electric power system, part of the primary and secondary coolant system piping and the spent fuel storage pool have been modified and the new air-exchange system in the control room were installed. Because of this large reconstruction of the reactor, for the last years in the operation of the reactor no significant problems have been detected. The facility is expected to operate without major investment at least until 2006. The reactor has been utilized in the projects: Neutron activation analysis, Boron neutron capture therapy, Real time neutron radiography, Neutron tomography, and Dosimetry research. The activities of neutron activation analysis, neutron radiography and tomography as well as boron neutron capture therapy are shortly presented

  15. Utilization and operating experience of the TRIGA Mark II research reactor in Ljubljana

    International Nuclear Information System (INIS)

    The operating experience of the 250 kW TRIGA Mark-II reactor of the J. Stefan Institute in Ljubljana, Slovenia in the years 1996 and 1997 is reported. The reactor has been in operation without long undesired shut-down. In 1996 the production of energy was 401 MWh (around 1600 hours in operation) and there was 7 unplanned shut-downs because of electricity broke down. In 1997 the production of energy was 272 MWh (around 1090 hours in operation). In 1991 and 1997 the reactor was almost completely reconstructed and upgraded. The reconstruction consisted mainly of replacing the grid plates, the control rod mechanisms and the control unit. Recently, the new PC based system was adopted and developed to collect the operational radiation data of the reactor. The new wiring of the electric power system, part of the primary and secondary coolant system piping and the spent fuel storage pool have been modified and the new air-exchange system in the control room were installed. Because of this large reconstruction of the reactor, for the last years in the operation of the reactor no significant problems have been detected. The facility is expected to operate without major investment at least until 2006. The reactor has been utilized in the projects: Neutron activation analysis, Boron neutron capture therapy, Real time neutron radiography, Neutron tomography, and Dosimetry research. The activities of neutron activation analysis, neutron radiography and tomography as well as boron neutron capture therapy are shortly presented

  16. Fuel burnup analysis of the TRIGA Mark II Reactor at the University of Pavia

    CERN Document Server

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

    2015-01-01

    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 analyse 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 experimental reactors from power ones, 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...

  17. Development of neutron beam projects at the University of Texas TRIGA Mark II Reactor

    International Nuclear Information System (INIS)

    Recently, the UT-TRIGA research reactor was licensed and has become fully operational. This reactor, the first new US university reactor in 17 years, is the focus of a new reactor laboratory facility which is located on the Balcones Research Center at The University of Texas at Austin. The TRIGA Mark II reactor is licensed for 1.1 MW steady power operation, 3 dollar pulsing, and includes five beam ports. Various neutron beam-line projects have been assigned to each beam port. Neutron Depth Profiling (NDP) and the Texas Cold Neutron Source (TCNS) are close to completion and will be operational in the near future. The design of the NDP instrument has been completed, a target chamber has been built, and the thermal neutron collimator, detectors, data acquisition electronics, and data processing computers have been acquired. The target chamber accommodates wafers up to 12'' in diameter and provides remote positioning of these wafers. The design and construction of the TCNS has been completed. The TCNS consists of a moderator (mesitylene), a neon heat pipe, a cryogenic refrigerator, and neutron guide tubes. In addition, fission-fragment research (HIAWATHA), Neutron Capture Therapy, and Neutron Radiography are being pursued as projects for the other three beam ports. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Snoj, Luka; Ravnik, Matjaz; Lengar, Igor [Jozef Stefan Institute, Reactor Physics Division, Jamova 39, SI-1000 Ljubljana (Slovenia)

    2008-10-29

    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 {approx}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)

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

    CERN Document Server

    Cammi, Antonio; Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica; Magrotti, Giovanni; Prata, Michele; Salvini, Andrea

    2015-01-01

    In this work, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor of the University of Pavia is performed by coupling Monte Carlo (MC) simulation for neutronics with "Multiphysics" model for thermal-hydraulics. Neutronic analyses have been performed starting from a MC model of the entire reactor system, based on the MCNP5 code, that was already validated in fresh fuel and zero-power configuration (in which thermal effects are negligible) using the available experimental data as benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core is necessary. To evaluate it, a thermal-hydraulic model has been developed, using the power distribution results from 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 introduced in the MC model and a benchmark analysis is carr...

  20. 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.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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 846.76o C which is much less than the limiting maximum value of fuel temperature of 11500 C as reported in SAR. During a pulse if the film boiling occurs for a peak adiabatic fuel temperature of 1000o C, the calculated outer cladding wall temperature was observed to be 702.390 C compared to a value of 760o 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)

  3. Benchmark analysis of the TRIGA MARK II research reactor using Monte Carlo techniques

    Energy Technology Data Exchange (ETDEWEB)

    Huda, M.Q. E-mail: quamrul@dhaka.net; Rahman, M.; Sarker, M.M.; Bhuiyan, S.I

    2004-07-01

    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 3-D 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 ENDF/B-V and S({alpha},{beta}) scattering functions from the ENDF/B-VI library were used. The consistency and accuracy of both the Monte Carlo simulation and neutron transport physics was established by benchmarking the TRIGA experiments. The effective multiplication factor, power distribution and peaking factors, neutron flux distribution, and reactivity experiments comprising control rod worths, critical rod height, excess reactivity and shutdown margin were used in the validation process. The MCNP predictions and the experimentally determined values are found to be in very good agreement, which indicates that the simulation of TRIGA reactor is treated adequately.

  4. Numerical simulation of non-steady state neutron kinetics of the TRIGA Mark II reactor Vienna

    Energy Technology Data Exchange (ETDEWEB)

    Riede, J., E-mail: jriede@ati.ac.at; Boeck, H., E-mail: boeck@ati.ac.at

    2013-12-15

    Highlights: • Power changes after reactivity changes have been measured with high time resolution. • Time dependent power changes after reactivity changes have been calculated numerically including feedback mechanisms. • The model has been verified by comparing numerical results to experimental data. • The verified model has been used to predict time dependent power changes after several reactivity changes. - Abstract: This paper presents an algorithm for numerical simulations of non-steady states of the TRIGA Mark II reactor in Vienna, Austria. The primary focus of this work has been the development of an algorithm which provides time series of integral neutron flux after reactivity changes introduced by perturbations without the usage of thermal-hydraulic/neutronic numerical code systems for the TRIGA reactor in Vienna, Austria. The algorithm presented takes into account both external reactivity changes as well as internal reactivity changes caused by feedback mechanisms like effects caused by temperature changes of the fuel and poisoning effects. The resulting time series have been compared to experimental results.

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

    Science.gov (United States)

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

    2015-09-01

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

  6. Numerical simulation of non-steady state neutron kinetics of the TRIGA Mark II reactor Vienna

    International Nuclear Information System (INIS)

    Highlights: • Power changes after reactivity changes have been measured with high time resolution. • Time dependent power changes after reactivity changes have been calculated numerically including feedback mechanisms. • The model has been verified by comparing numerical results to experimental data. • The verified model has been used to predict time dependent power changes after several reactivity changes. - Abstract: This paper presents an algorithm for numerical simulations of non-steady states of the TRIGA Mark II reactor in Vienna, Austria. The primary focus of this work has been the development of an algorithm which provides time series of integral neutron flux after reactivity changes introduced by perturbations without the usage of thermal-hydraulic/neutronic numerical code systems for the TRIGA reactor in Vienna, Austria. The algorithm presented takes into account both external reactivity changes as well as internal reactivity changes caused by feedback mechanisms like effects caused by temperature changes of the fuel and poisoning effects. The resulting time series have been compared to experimental results

  7. Benchmark analysis of the TRIGA MARK II research reactor using Monte Carlo techniques

    International Nuclear Information System (INIS)

    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 3-D 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 ENDF/B-V and S(α,β) scattering functions from the ENDF/B-VI library were used. The consistency and accuracy of both the Monte Carlo simulation and neutron transport physics was established by benchmarking the TRIGA experiments. The effective multiplication factor, power distribution and peaking factors, neutron flux distribution, and reactivity experiments comprising control rod worths, critical rod height, excess reactivity and shutdown margin were used in the validation process. The MCNP predictions and the experimentally determined values are found to be in very good agreement, which indicates that the simulation of TRIGA reactor is treated adequately

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

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

  10. Plan for the safe decommissioning of the BAEC 3MW TRIGA MARK-II research reactor

    International Nuclear Information System (INIS)

    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 (131I, 99mTc, 46Sc), 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 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 present the reactor is operated 5 days a week at a full power level of 3 MW for production of I-131 and R and D purposes. Up to December 2005 total burn-up of the core stands at about 358 Megawatt Days (MWDs). BAEC has planned to increase the production of 131I and as such, the core burn-up is expected to be increased very significantly in the years to come. There is a declaration from the US DOE that all US origin research reactor spent fuel generated within 2006 will be taken away to the USA at their own cost within 2009. But the fuel burn up of the BAEC research reactor is about 6%. So the reactor can operate for about 10-20 years more. An initial decommissioning plan for the BAEC TRIGA reactor and relevant facilities should be established as early as possible as recommended in the IAEA Safety Standards Series No.WS-G-2.1 (Decommissioning of Nuclear Power Plants and Research Reactors - Safety Standards Series No.WS-G-2.1, IAEA, Vienna, 1999). During the design and construction

  11. Simulation of Collimator for Neutron Imaging Facility of TRIGA MARK II PUSPATI Reactor

    Science.gov (United States)

    Zin, Muhammad Rawi Mohamed; Jamro, Rafhayudi; Yazid, Khairiah; Hussain, Hishamuddin; Yazid, Hafizal; Ahmad, Megat Harun Al Rashid Megat; Azman, Azraf; Mohamad, Glam Hadzir Patai; Hamzah, Nai'im Syaugi; Abu, Mohamad Puad

    Neutron Radiography facility in TRIGA MARK II PUSPATI reactor is being upgraded to obtain better image resolution as well as reducing exposure time. Collimator and exposure room are the main components have been designed for fabrication. This article focuses on the simulation part that was carried out to obtain the profile of collimated neutron beam by utilizing the neutron transport protocol code in the Monte Carlo N-Particle (MCNP) software. Particular interest is in the selection of materials for inlet section of the collimator. Results from the simulation indicates that a combination of Bismuth and Sapphire, each of which has 5.0 cm length that can significantly filter both the gamma radiation and the fast neutrons. An aperture made of Cadmium with 1.0 cm opening diameter provides thermal neutron flux about 1.8 x108 ncm-2s-1 at the inlet, but reduces to 2.7 x106 ncm-2s-1 at the sample plane. Still the flux obtained is expected to reduces exposure time as well as gaining better image resolution.

  12. Determination of the thermal-hydraulic parameters of ITU TRIGA Mark-II reactor

    International Nuclear Information System (INIS)

    In this study, a transient, one-dimensional thermal-hydraulic subchannel analysis for I.T.U. TRIGA Mark-II reactor was employed. Mixed convection is considered in modelling to enhance the capability of the computer code. After the continuity, conservation of energy, momentum balance equations for coolant in axial direction and the heat-conduction equation for the fuel rod in radial direction had been written, they were discretized by using the control volume approach to obtain a set of algebraic equations. By the aid of the discretized continuity and momentum balance equations, a pressure and a pressure-correction equations were derived. Then, two different FORTRAN programs called TRIGATH (TRIGA Thermal-Hydraulics) and TRIGATH-R (TRIGATH Revised) have been developed to solve this set of algebraic equations by using SIMPLE and SIMPLER algorithms respectively. As a result, the temperature distributions of the coolant and the fuel rods as well as the velocity and pressure distributions of the coolant have been estimated for both transient and steady state regimes from both algorithms. Their results, which are in good agreement, are compared to the results of the computer code

  13. Spent Fuel Management Program in the 3MW TRIGA MARK-II Research Reactor of Bangladesh

    International Nuclear Information System (INIS)

    Bangladesh Atomic Energy Commission (BAEC) has been operating a 3 MW TRIGA MARK II research reactor since 1986. The reactor was installed in the campus of the Atomic Energy Research Establishment (AERE) at Savar, Dhaka. It is one of the main nuclear research facilities in the country. The reactor uses TRIGA LEU fuel with uranium content of 20% by weight. The enrichment level of the fuel is 19.7%. The reactor has so far been operated for 7834 hours with a total cumulative burn up of 15898 MWh (662.5 MWd). The total burn up life of the present core is 1200 MWd. The main areas of use are: training of man-power for nuclear power plant applications, radioisotope (RI) production, neutron activation analysis (NAA), neutron radiography (NR) and neutron scattering. The government of Bangladesh has taken decision to establish nuclear power programme in the country. There is an ADP (Annual Development Project) to accomplish necessary activities for construction of medium size nuclear power plant (NPP) in the western zone of the country. Now, with regard to the safe management, storage of spent fuel and disposal of radioactive waste arising from operation of the research reactor and also from the proposed NPP expected to be constructed in future, BAEC is drawing up short and long-term plans and programs. At present, there does not exist any spent fuel element in the reactor facility. It is to be mentioned that Bangladesh is aware of the US DOE’s ‘Take Back Program’ in connection with the research reactor spent fuel of US origin, and is very much interested to take part in this program. The paper presents the current status of handling and storage facilities available for spent fuel and strategy for the safe management of spent fuel to be generated from the research reactor in near future. (author)

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

    International Nuclear Information System (INIS)

    A 2 MW TRIGA MARK II research reactor has been designed by General Atomics (GA) for the National Centre for Energy and Nuclear Sciences and Techniques (CNESTEN) in Morocco. This TRIGA reactor has the particularity of being the only TRIGA reactor designed to operate at the power level of 2 MW with the use of natural convection cooling. The main objective of this study is to check the ability of the reactor to operate at its nominal power with sufficient safety margins. The analysis of the reactor core starts from the basic reactor cells calculations which were performed for all the reactor cells using the LEOPARD code. The zone averaged group constants provided by cell calculations are used to compute the multiplication factor keff of the cold and clean core using the diffusion theory code Mcrac which is a recent version of the earlier code EXTERMINATOR-2. The main objective of the core calculations is to predict the core excess reactivity in cold zero power conditions and the power peaking factors which are very important data for the thermal hydraulic analysis of the core. For the maximum power peaking factors, our results agree with the values given by the reactor designer. Concerning the core excess reactivity, our results from both XY and RZ core calculations models lead to higher values than the results given by GA (about +2000 pcm). However, we should mention that GA results correspond probably to the minimum core excess reactivity which is guaranteed. The thermal hydraulic analysis of the TRIGA core was performed using the French code FLICA developed in CEA/Saclay for transient and study state thermal hydraulic analysis of a large variety of reactor cores. The objective of this analysis is to evaluate the main safety related parameters of the core and to ensure that they are within the safety limits in any operating conditions. The parameters considered in our study are: maximum fuel temperature, minimum DNBR and maximum void fraction. The obtained results

  15. Thermo-hydrodynamic design and safety parameter studies of the TRIGA MARK II research reactor

    International Nuclear Information System (INIS)

    The PARET computer code was used to analyse important thermo-hydrodynamic design and safety parameters of the 3 MW TRIGA MARK II research reactor at Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh. The study involves the determination of the departure from nucleate boiling (DNB) value and studying its effect over the thermo-hydrodynamic design of the reactor. In the process the temperature profile, heat flux and pressure drop across the hottest channel of the TRIGA core were evaluated. The DNB ratio (DNBR), which is defined as the ratio of the critical heat flux to the heat flux achieved in the core, was computed by means of a suitable correlation as defined in PARET code. Over the length 0.381 m of the hottest channel the DNBR varies, starting from 3.8951 to 5.4031, with a minimum of 2.7851. The peak heat flux occurs at the axial centre of the fuel elements; therefore the DNBR is minimum at this location. The reactor core should be designed so as to prevent the DNBR from dropping below a chosen value under a high heat flux transient condition for the most adverse set of mechanical and coolant conditions. The loss-of-flow accident (LOFA) scenario of the reactor has also been studied to ensure that the existing design and procedures are adequate to assure that the consequences from this anticipated occurrence does not lead to a significant accident. The loss-of-flow transient after a trip time of 4.08 s at 85% of loss of normal flow for the TRIGA core shows a peak temperature of 709.22 deg. C in the fuel centreline and 131.94 deg. C in the clad and 46.63 deg. C in the coolant exit of the hottest channel. The transient was terminated at 15% of nominal flow after ∼48.0 s and the time at which the reversal of coolant flow starts is ∼67.0 s

  16. Determination of the parameters α and f of the reactor triga mark II of Cren-K

    International Nuclear Information System (INIS)

    The α parameter and the thermal to epithermal flux ratio (f) have been determined for irradiation channels (LS3, LS5, LS9, LS11 and LS25) of nuclear reactor Triga Mark II of the Regional Nuclear Centre of Kinshasa. The three methods - Cd radio method covered Cd monitor method and base monitor method used for evaluation of α parameter give the same result in each irradiation position. The thermal to epithermal flux ratio f has been determined by the Cd ratio method. Results show that nuclear parameters α and f, change from one point to another of the reactor; α being negative, the resonance integrals I.(α) are increased.

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

    International Nuclear Information System (INIS)

    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

  18. In-situ gamma spectrometry measurements of time-dependent Xenon-135 inventory in the TRIGA Mark II reactor Vienna

    CERN Document Server

    Riede, Julia

    2013-01-01

    In this work, it has been shown that the time dependent Xe-135 inventory in the TRIGA Mark II reactor in Vienna, Austria can be measured via gamma spectrometry even in the presence of strong background radiation. It is focussing on the measurement of (but not limited to) the nuclide Xe-135. The time dependent Xe-135 inventory of the TRIGA Mark II reactor Vienna has been measured using a temporary beam line between one fuel element of the core placed onto the thermal column after shutdown and a detector system located just above the water surface of the reactor tank. For the duration of one week, multiple gamma ray spectra were recorded automatically, starting each afternoon after reactor shutdown until the next morning. One measurement series has been recorded over the weekend. The Xe-135 peaks were extracted from a total of 1227 recorded spectra using an automated peak search algorithm and analyzed for their time-dependent properties. Although the background gamma radiation present in the core after shutdown...

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

    Energy Technology Data Exchange (ETDEWEB)

    Boulaich, Y., E-mail: boulaich@cnesten.org.ma [CEN-Maamora, CNESTEN, Rabat (Morocco); Nacir, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); El Bardouni, T. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan (Morocco); CEN-Maamora, CNESTEN, Rabat (Morocco); Boukhal, H. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan (Morocco); Chakir, E. [LHESIR, Department of Physics, Faculty of Sciences, Kénitra (Morocco); El Bakkari, B.; El Younoussi, C. [CEN-Maamora, CNESTEN, Rabat (Morocco)

    2015-04-01

    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.

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

    International Nuclear Information System (INIS)

    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

  1. COMMIX-1C code estimation for the pool dynamics of Istanbul Technical University TRIGA MARK-II reactor

    International Nuclear Information System (INIS)

    In this study, the COMMIX-1C code is used to investigate the pool dynamics of Istanbul Technical University (ITU)TRIGA MARK-II reactor by simulating the velocity, pressure and temperature distributions in the reactor pool as a function of core design parameters and pool configuration. COMMIX-1C is multi-purpose, three-dimensional. transient, single-phase, thermal-hydraulics computer code. For the mass, momentum and energy equations, it uses a porous-medium formulation, a finite-volume algorithm, a flow modulated skew-upwind discretization scheme to reduce numerical diffusion and k-ε two-equation turbulence model. Its implementation for the particular system requires geometric and physical modelling decisions. ITU TRIGA MARK-II reactor pool is considered partly as continuum and partly as porous medium. All the major pool components are explicitly modelled in the simulation. Shape of the pool structure and computational cells are accounted for using the concept of directional surface permeability, volume porosity, distributed resistance, and distributed heat source or sink. The results are compared to the results of the computer codes TRISTAN, TRIGATH and TRIGATH-R

  2. Implementation of k0-INAA standardisation at ITU TRIGA Mark II research reactor, Turkey based on k0-IAEA software

    Science.gov (United States)

    Esen, Ayse Nur; Haciyakupoglu, Sevilay

    2016-02-01

    The purpose of this study is to test the applicability of k0-INAA method at the Istanbul Technical University TRIGA Mark II research reactor. The neutron spectrum parameters such as epithermal neutron flux distribution parameter (α), thermal to epithermal neutron flux ratio (f) and thermal neutron flux (φth) were determined at the central irradiation channel of the ITU TRIGA Mark II research reactor using bare triple-monitor method. HPGe detector calibrations and calculations were carried out by k0-IAEA software. The α, f and φth values were calculated to be -0.009, 15.4 and 7.92·1012 cm-2 s-1, respectively. NIST SRM 1633b coal fly ash and intercomparison samples consisting of clay and sandy soil samples were used to evaluate the validity of the method. For selected elements, the statistical evaluation of the analysis results was carried out by z-score test. A good agreement between certified/reported and experimental values was obtained.

  3. Utilization of the 250 kW TRIGA Mark II reactor in Ljubljana. Thirty years of experiences

    International Nuclear Information System (INIS)

    In its 30th year, the TRIGA Mark II 250 kW pulsing reactor is continuing its busy operation. With the maximum neutron flux in the central thimble of 1.1013 n/cm2 sec and many sample radiation positions the reactor has been used for a number of sophisticated experiments in the following fields: solid state physics (elastic and inelastic scattering of neutrons), neutron dosimetry, neutron radiography, reactor physics including nuclear burn up measurements and calculations and neutron activation analysis which represents one of the major usage of our reactor. Besides these, applied research around the reactor has been conducted, such as dopping of silicon monocrystals, a routine production of various radioactive isotopes for industry and medical use (18F,99mTc). At the Nuclear Training Centre the TRIGA reactor is the main teaching equipment. This training centre can fulfil the training requirements of the first Slovenian Nuclear Power Plant Krsko. (orig.)

  4. Microfungal Activity Test Of The Triga Mark II Reactor Tank Isolation to Aluminium corrosion

    International Nuclear Information System (INIS)

    In our pres ious study some pure species of micro fungal have been isolated from cooling water and samples taken from surrounding tank wall of TRIGA Mark II Reaktor. This study was conducted to determine their activities to aluminium 6061-T using modified method of Hortative (1962) in the speed of corrosion transmission process. Each isolate was inoculated into mineral nutrient solution. Changes of ph and reduced weight of Aluminium specimen weight between the experimental and the control groups, and the amounts were proportional to to the length of investigation times. The highest degree of the corrosion speed is given by Penicillium simplicissimum inoculant 2,95.10-6, followed by Paecilomyceus carneus 2,61.106, Penicillium canescens 2,59.10-6 and the control 2,11.106 respectively

  5. Feasibility study for production of 99mTc by neutron irradiation of MoO3 in a 250 kW TRIGA Mark II reactor

    International Nuclear Information System (INIS)

    The subject of this paper is to explore the possibility to obtain 99mTc from activation of 98Mo, using the TRIGA Mark II low flux research reactor (Vienna, Austria). Irradiation of both natural and enriched in 98Mo molybdenum oxides was compared. Aims of this work included the determination of neutron fluxes and 98Mo(n, γ)99Mo reaction effective cross section in the TRIGA Mark II reactor irradiation channels, calculation of 99Mo specific activities, determination of optimal irradiation conditions for the subsequent 99mTc separation from MoO3 targets using concentrating technologies. (author)

  6. Analysis of tritium production in TRIGA Mark II reactor at JSI for the needs of fusion research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jazbec, Anze; Zerovnik, Gasper; Snoj, Luka; Trkov, Andrej [Jozef Stefan Institute, Ljubljana (Slovenia)

    2013-12-15

    In future, electricity could be produced in fusion power plants. One of the steps towards development of fusion power plants is the construction of an experimental fusion reactor ITER where deuterium (D) and tritium (T) will be fused and energy will be released. As natural concentrations of T are extremely low, the T as fusion fuel will have to be produced artificially. A series of calculations were made to investigate the possibility of producing small quantities of T for experimental fusion reactors such as JET and ITER in a small research reactor like the TRIGA Mark II reactor at the Jozef Stefan Institute (JSI). The T production is the largest if all irradiation channels in reactor's reflector are filled with LiAlO{sub 2} samples. When samples are inserted, the excess reactivity decreases by around 200 pcm. In the second part of the work an estimate was made of how long the reactor can operate with current fuel supplies. Calculations were made with the TRIGLAV computer code. TRIGA can operate at full power for at least 2,860 days, during which 152 mg of T could be produced. We conclude that small TRIGA reactors can not produce any significant quantities of T for the needs of the future experimental fusion reactors. (orig.)

  7. Analysis of tritium production in TRIGA Mark II reactor at JSI for the needs of fusion research reactors

    International Nuclear Information System (INIS)

    In future, electricity could be produced in fusion power plants. One of the steps towards development of fusion power plants is the construction of an experimental fusion reactor ITER where deuterium (D) and tritium (T) will be fused and energy will be released. As natural concentrations of T are extremely low, the T as fusion fuel will have to be produced artificially. A series of calculations were made to investigate the possibility of producing small quantities of T for experimental fusion reactors such as JET and ITER in a small research reactor like the TRIGA Mark II reactor at the Jozef Stefan Institute (JSI). The T production is the largest if all irradiation channels in reactor's reflector are filled with LiAlO2 samples. When samples are inserted, the excess reactivity decreases by around 200 pcm. In the second part of the work an estimate was made of how long the reactor can operate with current fuel supplies. Calculations were made with the TRIGLAV computer code. TRIGA can operate at full power for at least 2,860 days, during which 152 mg of T could be produced. We conclude that small TRIGA reactors can not produce any significant quantities of T for the needs of the future experimental fusion reactors. (orig.)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    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{sub 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.

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

    International Nuclear Information System (INIS)

    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, keff 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.

  12. TRIGA Mark II benchmark experiment

    International Nuclear Information System (INIS)

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

  13. Burnup analysis and in-core fuel management study of the 3 MW TRIGA MARK II research reactor

    International Nuclear Information System (INIS)

    The principal objective of this study is to formulate an effective optimal fuel management strategy for the TRIGA MARK II research reactor at AERE, Savar. The core management study has been performed by utilizing four basic types of information calculated for the reactor: criticality, power peaking, neutron flux and burnup calculation. This paper presents the results of the burnup calculations for TRIGA LEU fuel elements. The fuel element burnup for approximately 20 years of operation was calculated using the TRIGAP compute code. The calculation is performed in one-dimensional radial geometry in TRIGAP. Inter-comparison of TRIGAP results with other two calculations performed by MVP-BURN and MCNP4C-ORIGEN2.1 show very good agreement. Reshuffling at 20,000 MWh step provides the highest core lifetime of the reactor, which is 64,500 MWh. Besides, the study gives valuable insight into the behaviour of the reactor and will ensure better utilization and operation of the reactor in future

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

    International Nuclear Information System (INIS)

    Over the last two years the TRIGA Mark II reactor in Ljubljana has been operated at an energy release of about 2500 MWh or about 4100 hour per year. In this period, about 1800 samples were irradiated. In 1983, a new core configuration was established because all Al-clad fuel elements in the core were replaced by the SS-clad elements. The 'J.Stefan' Institute received in 1983, namely, from the TRIGA reactor in Neuherberg, Federal Republic of Germany 107 SS-clad partly burned fuel elements together with some instrumentation which will gradually replace the old radiological and safety instrumentation. The transportation and the dischange of the highly radioactive fuel was done quickly and without any problem. During the last two years the reactor has been operated without any longer shut-down due to technical difficulties. In 1983 we noticed only a fuel element failure during operation. After the short inspection the fuel element with a small clading hole was found and replaced by a new one. (orig.)

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

    International Nuclear Information System (INIS)

    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)

  16. Validation of eureka-2/rr code for analysis of pulsing parameters of triga mark ii research reactor in bangladesh

    International Nuclear Information System (INIS)

    Some parametric studies on pulsing mode for fresh core of TRIGA Mark II research reactor in AERE, Savar, have been carried out with coupled thermal-hydraulics code EUREKA-2/RR in association with neutronics code SRAC. At the beginning, role of some important parameters in pulsing like delayed neutron fraction (beta eff) and reactivity insertion have been studied keeping prompt neutron life time (lp) fixed at 33.4 micro-sec. After a series of experiments, we found that the pulsing peak that is consistent with the Safety Analysis Report (SAR) is for the delayed neutron fraction (beta eff) of 0.007 and reactivity insertion of 2. Study has determined the pulsing peak of the fresh core for this particular condition to be 857.86 MW which is 852 MW according to SAR. Experiment also shows the pulsing peak increases with the increase of reactivity insertion whereas decreases with increase of delayed neutron fraction. With the utilization of the particular values of these parameters, pulsing parameters like prompt energy released, reactor period, pulse width at half maxima, alongwith safety parameters including peak power and clad maximum temperature, have been analyzed. The clad maximum temperature for fresh core is simulated to be 144.54 MW, which is much less than the SAR Value, ensuring the validity of codes and the safety of pulsing in that particular condition. (author)

  17. Characterization of typical irradiation channels of CNESTEN's TRIGA MARK II reactor (Rabat, Morocco) using NAA k0-Method

    International Nuclear Information System (INIS)

    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 a set of Al (99.9%), Au (0.l %), Zn (99.99%) and Zr (99.8%) monitors. Results obtained for f and α in two irradiation channels show that f parameter determined in this way is different in the carousel facility (CRl) 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 neut ron spectrum is relatively well thermalized. Parameter α in the PT has a negative value, which is very small and can not significantly influence the final result 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.

  18. Loss of Coolant Accident Analysis for 1MW PUSPATI Triga Mark II Research Reactor (RTP) Using MARS-KS Code

    Energy Technology Data Exchange (ETDEWEB)

    Abd, Aziz Sadri [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Shin, Andong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    RTP is a pool type reactor cooled by natural circulation and the reactor core is located at the bottom of a demineralized water-filled aluminum liner tank of 2.0 meter diameter and 6.5 meter depth. The core assembly is composed of 100 cylindrical fuel rods including of 4 control rods in circular array. From the literature, development of thermal hydraulic analysis of RTP using computer code has not been well established. Therefore, establishment and development of appropriate thermal hydraulic safety analysis model is very critical to ensure the safety operation of the reactor. Hence, key thermal hydraulic parameters of RTP reactor operating under steady state and transient condition were investigated. In this paper, Loss Of Coolant Accident (LOCA) were calculated and analyzed and compared with corresponding values in Safety Analysis Report (SAR) 2008 and test report. PUSPATI Triga Mark II research reactor (RTP) has been operated at Malaysian Nuclear Agency since 1982 and primary cooling system was modified in 2010. Thermal hydraulic modeling of RTP of 1MWt has been successfully investigated with MARS-KS code. The calculated normal operation parameters have been compared with reactor Safety Analysis Report (SAR) and experimental data. Most of the thermal hydraulic parameters show good agreement with SAR and experimental data within an acceptable percentage error. The loss of coolant accident was simulated in case of leak of primary side heat exchanger gasket. The calculation result showed fast decrease of reactor pool level. About 5 minutes after the leak, reactor tank was fully depleted. Furthermore, claddings temperature was reached 1173.4K at 3270s which could result in failure of SS304 cladding. Based on the assessment, it is found that appropriate remedies including physical modifications or emergency procedures need be prepared to protect the reactor tank depletion by the heat exchanger leak accident.

  19. Loss of Coolant Accident Analysis for 1MW PUSPATI Triga Mark II Research Reactor (RTP) Using MARS-KS Code

    International Nuclear Information System (INIS)

    RTP is a pool type reactor cooled by natural circulation and the reactor core is located at the bottom of a demineralized water-filled aluminum liner tank of 2.0 meter diameter and 6.5 meter depth. The core assembly is composed of 100 cylindrical fuel rods including of 4 control rods in circular array. From the literature, development of thermal hydraulic analysis of RTP using computer code has not been well established. Therefore, establishment and development of appropriate thermal hydraulic safety analysis model is very critical to ensure the safety operation of the reactor. Hence, key thermal hydraulic parameters of RTP reactor operating under steady state and transient condition were investigated. In this paper, Loss Of Coolant Accident (LOCA) were calculated and analyzed and compared with corresponding values in Safety Analysis Report (SAR) 2008 and test report. PUSPATI Triga Mark II research reactor (RTP) has been operated at Malaysian Nuclear Agency since 1982 and primary cooling system was modified in 2010. Thermal hydraulic modeling of RTP of 1MWt has been successfully investigated with MARS-KS code. The calculated normal operation parameters have been compared with reactor Safety Analysis Report (SAR) and experimental data. Most of the thermal hydraulic parameters show good agreement with SAR and experimental data within an acceptable percentage error. The loss of coolant accident was simulated in case of leak of primary side heat exchanger gasket. The calculation result showed fast decrease of reactor pool level. About 5 minutes after the leak, reactor tank was fully depleted. Furthermore, claddings temperature was reached 1173.4K at 3270s which could result in failure of SS304 cladding. Based on the assessment, it is found that appropriate remedies including physical modifications or emergency procedures need be prepared to protect the reactor tank depletion by the heat exchanger leak accident

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

    International Nuclear Information System (INIS)

    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

  1. Neutronic and thermal-hydraulic analysis of new irradiation channels inside the Moroccan TRIGA Mark II research reactor core.

    Science.gov (United States)

    Chham, E; El Bardouni, T; Benaalilou, K; Boukhal, H; El Bakkari, B; Boulaich, Y; El Younoussi, C; Nacir, B

    2016-10-01

    This study was conducted to improve the capacity of radioisotope production in the Moroccan TRIGA Mark II research reactor, which is considered as one of the most important applications of research reactors. The aim of this study is to enhance the utilization of TRIGA core in the field of neutron activation and ensure an economic use of the fuel. The main idea was to create an additional irradiation channel (IC) inside the core. For this purpose, three new core configurations are proposed, which differ according to the IC position in the core. Thermal neutron flux distribution and other neutronic safety parameters such as power peaking factors, excess reactivity, and control rods worth reactivity were calculated using the Monte Carlo N-Particle Transport (MCNP) code and neutron cross-section library based on ENDF/B-VII evaluation. The calculated thermal flux in the central thimble (CT) and in the added IC for the reconfigured core is compared with the thermal flux in the CT of the existing core, which is taken as a reference. The results show that all the obtained fluxes in CTs are very close to the reference value, while a remarkable difference is observed between the fluxes in the new ICs and reference. This difference depends on the position of IC in the reactor core. To demonstrate that the Moroccan TRIGA reactor could safely operate at 2MW, with new configurations based on new ICs, different safety-related thermal-hydraulic parameters were investigated. The PARET model was used in this study to verify whether the safety margins are met despite the new modifications of the core. The results show that it is possible to introduce new ICs safely in the reactor core, because the obtained values of the parameters are largely far from compromising the safety of the reactor.

  2. Neutronic and thermal-hydraulic analysis of new irradiation channels inside the Moroccan TRIGA Mark II research reactor core.

    Science.gov (United States)

    Chham, E; El Bardouni, T; Benaalilou, K; Boukhal, H; El Bakkari, B; Boulaich, Y; El Younoussi, C; Nacir, B

    2016-10-01

    This study was conducted to improve the capacity of radioisotope production in the Moroccan TRIGA Mark II research reactor, which is considered as one of the most important applications of research reactors. The aim of this study is to enhance the utilization of TRIGA core in the field of neutron activation and ensure an economic use of the fuel. The main idea was to create an additional irradiation channel (IC) inside the core. For this purpose, three new core configurations are proposed, which differ according to the IC position in the core. Thermal neutron flux distribution and other neutronic safety parameters such as power peaking factors, excess reactivity, and control rods worth reactivity were calculated using the Monte Carlo N-Particle Transport (MCNP) code and neutron cross-section library based on ENDF/B-VII evaluation. The calculated thermal flux in the central thimble (CT) and in the added IC for the reconfigured core is compared with the thermal flux in the CT of the existing core, which is taken as a reference. The results show that all the obtained fluxes in CTs are very close to the reference value, while a remarkable difference is observed between the fluxes in the new ICs and reference. This difference depends on the position of IC in the reactor core. To demonstrate that the Moroccan TRIGA reactor could safely operate at 2MW, with new configurations based on new ICs, different safety-related thermal-hydraulic parameters were investigated. The PARET model was used in this study to verify whether the safety margins are met despite the new modifications of the core. The results show that it is possible to introduce new ICs safely in the reactor core, because the obtained values of the parameters are largely far from compromising the safety of the reactor. PMID:27552124

  3. Monte Carlo simulation of the thermal column and beam tube of the TRIGA Mark II research reactor

    International Nuclear Information System (INIS)

    Highlights: → Neutronics parameters of the reactor shielding. → Biological shielding of the TRIGA reactor. → Thermal flux measurement in the thermal column and BT-A. → MCNP model validation. - Abstract: The Monet Carlo simulation of the TRIGA Mark II research reactor core has been performed employing the radiation transport computer code MCNP5. The model has been confirmed experimentally in the PhD research work at the Atominstitute (ATI) of the Vienna University of Technology. The MCNP model has been extended to complete biological shielding of the reactor including the thermal column, radiographic collimator and four beam tubes. This paper presents the MCNP simulated results in the thermal column and one of the beam tubes (beam tube A) of the reactor. To validate these theoretical results, thermal neutron flux density measurements using the gold foil activation method have been performed in the thermal column and beam tube A (BT-A). In the thermal column, the theoretical and experimental results are in fairly good agreement i.e. maximum thermal flux density in the centre decreases in radial direction. Further, it is also agreed that thermal flux densities in the lower part is greater than the upper part of the thermal column. In the BT-A experiment, the thermal flux density distribution is measured using gold foil. The experimental and theoretical diffusion lengths have been determined as 10.77 cm and 9.36 cm respectively with only 13% difference, reflecting good agreement between the experimental and simulated results. To save the computational cost and to incorporate the accurate and complete information of each individual Monte Carlo MC particle tracks, the surface source writing capability of MCNP has been utilized to the TRIGA shielding model. The variance reduction techniques have been applied to improve the statistics of the problem and to save computational efforts.

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

    International Nuclear Information System (INIS)

    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 m3/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.)

  5. Development and experimental validation of a Monte Carlo simulation model for the Triga Mark II reactor

    OpenAIRE

    Chiesa,

    2014-01-01

    In recent years, many computer codes, based on Monte Carlo methods or deterministic calculations, have been developed to separately analyze different aspects regarding nuclear reactors. Nuclear reactors are very complex systems, which require an integrated analysis of all the variables which are intrinsically correlated: neutron fluxes, reaction rates, neutron moderation and absorption, thermal and power distributions, heat generation and transfer, criticality coefficients, fuel burnup, e...

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

    International Nuclear Information System (INIS)

    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

  7. 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.

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

    Science.gov (United States)

    Kamal, I.; Yunus, S. M.; Datta, T. K.; Zakaria, A. K. M.; Das, A. K.; Aktar, S.; Hossain, S.; Berliner, R.; Yelon, W. B.

    2016-07-01

    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 6mm thickness each. The monochromator design was optimized to provide maximum flux on 3mm 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

  9. Periodic Safety review of JSI TRIGA Mark II and inspection of the reactor vessel

    Energy Technology Data Exchange (ETDEWEB)

    Jazbec, Anze; Snoj, Luak; Smodis, Borut [Jozef Stefan Institute, Ljubljana (Slovenia)

    2013-07-01

    Reactor TRIGA at the Jozef Stefan Institute (JSI) has been in operation since the year 1966. Most of the components were replaced during the process of maintenance and modernisation, but some of the equipment is still original or was replaced many years ago. Because of the ageing mechanisms, periodic safety review (PSR) is one of the crucial points for future utilization. According to legislation, PSR should be performed every 10 years. It features systematic inspection of structures, systems and components (SSC) of the reactor. Impacts of ageing, modernisation, operational experiences, technical progress, and changes of the site on the radiation and nuclear safety are verified. However, PSR does not give only inspection of the SSC, but also allows for the review of operating staff, their competence, operating procedures and other safety related procedures. PSR is pre-condition for extending operating licence. One of the components that have never been replaced is the aluminium reactor vessel. An externally contracted company made extensive analysis of the reactor vessel condition. Firstly, a visual inspection using underwater camera was made. Then all critical areas and welds were examined by using the ultrasound. Thickness of the wall was carefully measured and analysed. Using the same method, inspection for possible cracks inside aluminium was made. No failures were discovered and reactor vessel was found to be in a good condition.

  10. Long-lived activation products in TRIGA Mark II research reactor concrete shield: calculation and experiment

    Energy Technology Data Exchange (ETDEWEB)

    Zagar, Tomaz [Reactor Physics Department, Jozef Stefan Institute, Jamova 39, 1000 Ljubljana (Slovenia)]. E-mail: tomaz.zagar@ijs.si; Bozic, Matjaz [Nuklearna elektrarna Krsko, Vrbina 12, 8270 Krsko (Slovenia); Ravnik, Matjaz [Reactor Physics Department, Jozef Stefan Institute, Jamova 39, 1000 Ljubljana (Slovenia)

    2004-12-01

    In this paper, a process of long-lived activity determination in research reactor concrete shielding is presented. The described process is a combination of experiment and calculations. Samples of original heavy reactor concrete containing mineral barite were irradiated inside the reactor shielding to measure its long-lived induced radioactivity. The most active long-lived ({gamma} emitting) radioactive nuclides in the concrete were found to be {sup 133}Ba, {sup 60}Co and {sup 152}Eu. Neutron flux, activation rates and concrete activity were calculated for actual shield geometry for different irradiation and cooling times using TORT and ORIGEN codes. Experimental results of flux and activity measurements showed good agreement with the results of calculations. Volume of activated concrete waste after reactor decommissioning was estimated for particular case of Jozef Stefan Institute TRIGA reactor. It was observed that the clearance levels of some important long-lived isotopes typical for barite concrete (e.g. {sup 133}Ba, {sup 41}Ca) are not included in the IAEA and EU basic safety standards.

  11. Long-lived activation products in TRIGA Mark II research reactor concrete shield: calculation and experiment

    Science.gov (United States)

    Žagar, Tomaž; Božič, Matjaž; Ravnik, Matjaž

    2004-12-01

    In this paper, a process of long-lived activity determination in research reactor concrete shielding is presented. The described process is a combination of experiment and calculations. Samples of original heavy reactor concrete containing mineral barite were irradiated inside the reactor shielding to measure its long-lived induced radioactivity. The most active long-lived (γ emitting) radioactive nuclides in the concrete were found to be 133Ba, 60Co and 152Eu. Neutron flux, activation rates and concrete activity were calculated for actual shield geometry for different irradiation and cooling times using TORT and ORIGEN codes. Experimental results of flux and activity measurements showed good agreement with the results of calculations. Volume of activated concrete waste after reactor decommissioning was estimated for particular case of Jožef Stefan Institute TRIGA reactor. It was observed that the clearance levels of some important long-lived isotopes typical for barite concrete (e.g. 133Ba, 41Ca) are not included in the IAEA and EU basic safety standards.

  12. Neutron dosimetry and damage calculations for the TRIGA MARK-II reactor in Vienna

    Science.gov (United States)

    Weber, H. W.; Böck, H.; Unfried, E.; Greenwood, L. R.

    1986-02-01

    In order to improve the source characterization of the reactor, especially for recent irradiation experiments in the central irradiation thimble, neutron activation experiments were made on 16 nuclides and the neutron flux spectrum was adjusted using the computer code STAY'SL. The results for the total, thermal and fast neutron flux density at a reactor power of 250 kW are as follows: 2.1 × 10 17, 6.1 × 10 16 ( E 0.1 MeV) and 4.0 × 10 16 ( E > 1 MeV) m -2 s -1. respectively. Calculated damage energy cross sections and gas production rates are presented for selected elements.

  13. Tank Design Evaluation Of TRIGA Mark II Reactor For 2 MW Power

    International Nuclear Information System (INIS)

    . Design calculation, safety factor choosing, and welding procedure on tank design of Bandung nuclear reactor for 2 MW power have been evaluated. For design calculation, the evaluation has especially done based on material strength input which was used on tank thickness calculation. Evaluation on safety factor choosing has been done by comparing the result of final calculation after inputting the value of safety factor to the physics condition will be occurred. On welding procedure, the evaluation has been carried to see the chance will be occurred if the excising design followed. From this evaluation, it can be concluded that the calculation just done to meet the result of the calculation to the thickness of material has been excised so it can be assumed as proper material of tank reactor

  14. Validation of WIMS-SNAP code systems for calculations in TRIGA-MARK II type reactors

    International Nuclear Information System (INIS)

    The following paper contributes to validate the Nuclear Engineering Department methods to carry out calculations in TRIGA reactors solving a Benchmark. The benchmark is analyzed with the WIMS-D/4-SNAP/3D code system and using the cross section library WIMS-TRIGA. A brief description of the DSN method is presented used in WIMS/d4 code and also the SNAP-3d code is shortly explained. The results are presented and compared with the experimental values. In other hand the possible error sources are analyzed. (author)

  15. Design of sample carrier for neutron irradiation facility at TRIGA MARK II nuclear reactor

    Science.gov (United States)

    Abdullah, Y.; Hamid, N. A.; Mansor, M. A.; Ahmad, M. H. A. R. M.; Yusof, M. R.; Yazid, H.; Mohamed, A. A.

    2013-06-01

    The objective of this work is to design a sample carrier for neutron irradiation experiment at beam ports of research nuclear reactor, the Reaktor TRIGA PUSPATI (RTP). The sample carrier was designed so that irradiation experiment can be performed safely by researchers. This development will resolve the transferring of sample issues faced by the researchers at the facility when performing neutron irradiation studies. The function of sample carrier is to ensure the sample for the irradiation process can be transferred into and out from the beam port of the reactor safely and effectively. The design model used was House of Quality Method (HOQ) which is usually used for developing specifications for product and develop numerical target to work towards and determining how well we can meet up to the needs. The chosen sample carrier (product) consists of cylindrical casing shape with hydraulic cylinders transportation method. The sample placing can be done manually, locomotion was by wheel while shielding used was made of boron materials. The sample carrier design can shield thermal neutron during irradiation of sample so that only low fluencies fast neutron irradiates the sample.

  16. Recent research programs at the TRIGA Mark II reactor in Ljubljana

    International Nuclear Information System (INIS)

    Recent developments and new research activities which make use of the TRIGA reactor in Ljubljana are reported. They are spread over a broad range of research fields from nuclear and solid state physics, reactor physics and engineering, neutron radiography, analytical chemistry, medicine and biology, and industrial applications. The following investigations are briefly described: Improvements in the thermal neutron beam facility for nuclear capture studies, a rotating crystal time-of-flight spectrometer and its use for measurements of dynamics of crystal lattices in liquid crystals and ferroelectrics, measurements by the fast neutron spectroscopy and dosimetry group of fission-spectrum averaged activation cross-sections for some threshold detectors; measurements of fast neutron spectra in standard TRIGA seed irradiation facilities and improvements of activation data unfolding program ITER II and its application to unfolding of single crystal fast neutron scintillation spectrometers, a simple nuclear power plant simulator to be used for education of plant personnel; neutron activation analysis falls into two parts: ecological studies of the uptake and distribution of mercury and some other micro-elements in particular in the Idrija area (mercury mining), and the development of methods for the analysis of trace elements in standard reference materials, biological samples, and high purity materials. (U.S.)

  17. Design of sample carrier for neutron irradiation facility at TRIGA MARK II nuclear reactor

    International Nuclear Information System (INIS)

    The objective of this work is to design a sample carrier for neutron irradiation experiment at beam ports of research nuclear reactor, the Reaktor TRIGA PUSPATI (RTP). The sample carrier was designed so that irradiation experiment can be performed safely by researchers. This development will resolve the transferring of sample issues faced by the researchers at the facility when performing neutron irradiation studies. The function of sample carrier is to ensure the sample for the irradiation process can be transferred into and out from the beam port of the reactor safely and effectively. The design model used was House of Quality Method (HOQ) which is usually used for developing specifications for product and develop numerical target to work towards and determining how well we can meet up to the needs. The chosen sample carrier (product) consists of cylindrical casing shape with hydraulic cylinders transportation method. The sample placing can be done manually, locomotion was by wheel while shielding used was made of boron materials. The sample carrier design can shield thermal neutron during irradiation of sample so that only low fluencies fast neutron irradiates the sample.

  18. TRIGA Mark II reactor at L.E.N.A., operation and security

    International Nuclear Information System (INIS)

    The operational data in the period July 1980 - June 1982, are summarized, showing no significant variations in the total operation. Irradiation applications are presented. Two experiments of great importance will take place in near future: Sodium Experiment in Euracos Facility and the Oscillation n ? n-bar Nadir experiment in Thermal Column. Regular maintenance of the reactor and auxiliary systems was performed continuously; therefore no significant troubles with electronic instrumentation and mechanical components were experienced. The rotary specimen rack, that was changed eight years ago, is giving few troubles mainly related to the rotary movement. In 1967 a crack appeared on the concrete biological shield below the water level of the bulk shielding tank. I t was then decided to cover the internal surface of the bulk shielding pool with an aluminum liner. Corrosion phenomena took place in the last two years and are now increasing with time. All around the liner, almost uniformly distributed and especially in the regions near the welds, white flocks were observed. The corrosion products were analyzed and the results are reported. In the future, to prevent similar corrosions, the whole aluminium liner will be painted with epoxy coating. General security of the plant has been planned as a primary problem in the LENA activity

  19. Neutron flux variability at the TRIGA MARK II reactor, Ljubljana, as a parameter with applying the k0-method of NAA

    International Nuclear Information System (INIS)

    Neutron flux behaviour during irradiation should be known when applying the k0 method of neutron activation analysis. During two 100-hour operating periods of the TRIGA MARK II reactor, Ljubljana, the flux was measured by means of a 197Au(n,γ)198Au monitor (Eγ=411.8 keV). Cadmium-covered irradiations were also performed to obtain the epithermal flux and thermal-to-epithermal flux ratio variations. Consistency was found between these results and the reactor operators' logbook record. (author) 5 refs.; 3 figs

  20. Reactivity calculations for the fuel elements of I.T.U. TRIGA MARK-II reactor by means of one-group perturbation theory

    International Nuclear Information System (INIS)

    The reactivities of the fuel elements of I.T.U. TRIGA MARK-II reactor has been calculated by using both one-group perturbation theory and a one-dimensional, two-group diffusion computer code TRIGAP. For each fuel element, reactivities calculated by both methods are compared with those measured experimentally. It is seen that the reactivity calculations made by using the one-group perturbation theory give the results with better accuracy in comparison to TRIGAP. One-group perturbation theory can be easily applied to the reactivity calculations of fuel elements of TRIGA type reactors in acceptable range (orig.)

  1. Thermal hydraulic transient study of 3 MW TRIGA Mark-II research reactor of Bangladesh using the EUREKA-2/RR code

    International Nuclear Information System (INIS)

    Highlights: ► Reactor power transition time depends on magnitude and form of reactivity. ► This time also depends on existing reactor power during reactivity insertion. ► Pattern of power transition depends on form of reactivity insertion. ► Doppler’s effect is seen for lower reactivity insertion when reactor power is low. ► EUREKA-2/RR code performs well for RIA and LOFA of TRIGA Mark-II research reactor. - Abstract: EUREKA-2/RR code has been used for the analyses of reactivity insertion accident (RIA) and loss of flow accident (LOFA) of 3 MW TRIGA Mark-II research reactor of Bangladesh. Transient characteristics of different parameters such as core power, fuel temperature, clad temperature, departure from nucleate boiling ratio (DNBR) due to the different form and magnitude of reactivity insertion has been focused. It is found from the analysis that the magnitude of insertion reactivity and the reactor operating power during this insertion impose a total effect on the core safety. Also, transient effects on reactor were studied for 15% loss of flow of the primary coolant. Provided the scram system is available, the reactor is found to shutdown safely in both cases. From these two studies in series, it is seen that EUREKA-2/RR is well suited for the analyses of reactor safety parameters with good approximations.

  2. The thermal column. A new irradiation position for fission-track dating in the University of Pavia Triga Mark II nuclear reactor

    International Nuclear Information System (INIS)

    In the present paper a new irradiation position arranged for fission-track dating in the Triga Mark II reactor of the University of Pavia is described. Fluence values determined using the NIST glass standard SRM 962a for fission-track dating and the traditional metal foils are compared. Relatively high neutron thermalization (cadmium ratio of 85.3 for gold and 643 for cobalt) and lack of significant fluence spatial gradients are very favorable 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). 9 refs., 2 figs., 4 tabs

  3. In-core fuel management, safety, and thermal hydraulics studies for upgrading TRIGA MARK II research reactor

    International Nuclear Information System (INIS)

    Bangladesh Atomic Energy Commission has approved a project to upgrade the research reactor to higher flux to meet the growing demand of medical radio-isotopes production and other irradiation facilities. Preliminary studies with the various core parameters showed that it might be possible to create new irradiation flux traps, increase the neutron flux at desired location, and at the same time the fuel burn-up can be made optimal. This will need major reshuffling and reconfiguration of the core with fuel rods initially loaded. The principal objective of this study is focused to make the above improvements in the core without disturbing the safety parameters. This presentation deals with the neutronic and thermal hydraulic analysis of the 3 MW TRIGA MARK II research reactor to upgrade it to a higher flux. To realize this objective, the overall strategy followed is: (I) generation of problem dependent cross section library from basic Evaluated Nuclear Data Files such as ENDF/B-VI, JENDL 3.2 with NJOY94.10+, (ii) use WIMSD-5 package to generate cell constants for all of the materials in the core and its immediate neighborhood, (iii) use CITATION to perform 3-D global analysis of the core to study multiplication factor, neutron flux and power distribution, power peaking factors, temperature reactivity coefficients, etc., (iv) check the validity of the deterministic codes with the Monte Carlo code MCNP-4B2, (v) couple output of CITATION with PARET to study thermal hydraulic behavior to predict safety margins, and (vi) reshuffle the current core configuration to achieve the desired objectives. The computational methods, tools and techniques, customization of cross section libraries, various models for cells and super cells, and a lot of associated utilities have been standardized 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 were performed

  4. Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections. Integral tests of differential cross sections of neutron threshold reactions

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.S.; Hossain, S.M.; Khan, R. [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology (INST); Sudar, S. [Debrecen Univ. (Hungary). Inst. of Experimental Physics; Zulquarnain, M.A. [Bangladesh Atomic Energy Commission, Dhaka (Bangladesh); Qaim, S.M. [Forschungszentrum Juelich (Germany). Inst. fuer Neurowissenschaften und Medizin (INM-5)

    2013-07-01

    The spectrum of fast neutrons having energies from 0.5 to 20 MeV in the core of the 3MW TRIGA Mark II reactor at Savar, Dhaka, Bangladesh, was unfolded by activating several metal foils to induce threshold nuclear reactions covering the whole spectrum, and then doing necessary iterative calculations utilizing the activation results and the code SULSA. The analysed shape of the spectrum in the TRIGA core was found to be similar to that of the pure {sup 235}U-fission spectrum, except for the energies between 0.5 and 1.5 MeV, where it was slightly higher than the fission spectrum. Spectrum-averaged cross sections were determined by integral measurements. The integral values measured in this work were compared with the recommended values for a pure fission spectrum as well as with the integrated data deduced from measured and evaluated excitation functions of a few reactions given in some data files. The good agreement between integral measurements and integrated data in case of well-investigated reactions shows that the fast neutron field at the TRIGA Mark II reactor can be used for validation of evaluated data of neutron threshold reactions. (orig.)

  5. Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections. Integral tests of differential cross sections of neutron threshold reactions

    International Nuclear Information System (INIS)

    The spectrum of fast neutrons having energies from 0.5 to 20 MeV in the core of the 3MW TRIGA Mark II reactor at Savar, Dhaka, Bangladesh, was unfolded by activating several metal foils to induce threshold nuclear reactions covering the whole spectrum, and then doing necessary iterative calculations utilizing the activation results and the code SULSA. The analysed shape of the spectrum in the TRIGA core was found to be similar to that of the pure 235U-fission spectrum, except for the energies between 0.5 and 1.5 MeV, where it was slightly higher than the fission spectrum. Spectrum-averaged cross sections were determined by integral measurements. The integral values measured in this work were compared with the recommended values for a pure fission spectrum as well as with the integrated data deduced from measured and evaluated excitation functions of a few reactions given in some data files. The good agreement between integral measurements and integrated data in case of well-investigated reactions shows that the fast neutron field at the TRIGA Mark II reactor can be used for validation of evaluated data of neutron threshold reactions. (orig.)

  6. Operating experience and maintenance of the 250 kW TRIGA Mark II Reactor Vienna in the period July 1982 to July 1984

    International Nuclear Information System (INIS)

    The operation and maintenance of the TRIGA Mark II Reactor Vienna during the period July 1982 to July 1984 is reported. The reactor operated without any major undesired shutdown period. The total power production was 261 MWh in 1982 and 200 MWh in 1983. The reactor was still operated without a rotary specimen rack, several irradiation positions were provided by tubes. The damaged Lazy Susan was finally shipped in a concrete container to a waste storage facility. Some problems were encountered with reactor components due to aging or wear such as the control rod drive motors, the fuel handling tool and the rod magnets. To increase the use and to facilitate the access to the thermal column a movable shielding platform was designed and constructed. Within the next year reinspection of the reactor tank and the supporting facilities will take place, especially the thermalizing column, presently housing a cold neutron source facility will be replaced by a neutron radiography installation

  7. Determination of the effect of xenon-135 poisoning on reactivity for the I.T.U. TRIGA MARK-II reactor

    International Nuclear Information System (INIS)

    The reactivity change due to the Xe135 poisoning was determined by the aid of an experiment and a simple mathematical model for the I. T. U. TRIGA MARK-II reactor. Temperature coefficients of reactivity for the fuel and the other components were determined experimentally. Then, the total reactivity change rising from the xenon poisoning and the temperature feedbacks was measured during the operation of the reactor for 100 hours. Time, rod positions, power level, temperature of the instrumented fuel element and water were recorded periodically during the experiment. After the reactor had operated at a power of 100 kW for 65 hours, xenon reactivity reached approximately an equilibrium level. In the second part of the experiment, instead of shutdown, the reactor power was decreased to a very low level in order to carry on the measurements continuously. Subtracting the change of the reactivity related to the temperature feedbacks for the fuel and the other components from that of the total, the reactivity change corresponding to the xenon poisoning was determined. An analytical expression for the variation of the xenon reactivity with time for a given power was fitted to the experimental data that were obtained during the first 65 hours of the experiment. Consequently, the macroscopic thermal fission cross section of the fuel, the total absorption cross section and the average thermal neutron flux were obtained. The resultant expression was tested by comparing its predictions with the data obtained in the second part of the experiment. It was also checked with the results of a new experiment in which the reactor was operated at a power of 200 kW. The predictions are in good agreement with the results of the measurements. This model makes possible to calculate the reactivity changes from xenon poisoning at various times for different power levels beginning from any Xe135 concentration for the I.T.U. TRIGA MARK-II reactor. (orig.)

  8. 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)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Boulaich, Y., E-mail: boulaich@cnesten.org.m [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Nacir, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); El Bardouni, T.; Zoubair, M. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); El Bakkari, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Merroun, O. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); El Younoussi, C. [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Htet, A. [CEN-Maamora, CNESTEN, Rabat (Morocco); Boukhal, H. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Chakir, E. [LRM/EPTN, Department of Physics, Faculty of Sciences, Kenitra (Morocco)

    2011-01-15

    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.

  10. Chromosome aberrations induced in human lymphocytes by U-235 fission neutrons: I. Irradiation of human blood samples in the "dry cell" of the TRIGA Mark II nuclear reactor.

    Science.gov (United States)

    Fajgelj, A; Lakoski, A; Horvat, D; Remec, I; Skrk, J; Stegnar, P

    1991-11-01

    A set-up for irradiation of biological samples in the TRIGA Mark II research reactor in Ljubljana is described. Threshold activation detectors were used for characterisation of the neutron flux, and the accompanying gamma dose was measured by TLDs. Human peripheral blood samples were irradiated "in vitro" and biological effects evaluated according to the unstable chromosomal aberrations induced. Biological effects of two types of cultivation of irradiated blood samples, the first immediately after irradiation and the second after 96 h storage, were studied. A significant difference in the incidence of chromosomal aberrations between these two types of samples was obtained, while our dose-response curve fitting coefficients alpha 1 = (7.71 +/- 0.09) x 10(-2) Gy-1 (immediate cultivation) and alpha 2 = (11.03 +/- 0.08) x 10(-2) Gy-1 (96 h delayed cultivation) are in both cases lower than could be found in the literature.

  11. Chromosome aberrations induced in human lymphocytes by U-235 fission neutrons: I. Irradiation of human blood samples in the "dry cell" of the TRIGA Mark II nuclear reactor.

    Science.gov (United States)

    Fajgelj, A; Lakoski, A; Horvat, D; Remec, I; Skrk, J; Stegnar, P

    1991-11-01

    A set-up for irradiation of biological samples in the TRIGA Mark II research reactor in Ljubljana is described. Threshold activation detectors were used for characterisation of the neutron flux, and the accompanying gamma dose was measured by TLDs. Human peripheral blood samples were irradiated "in vitro" and biological effects evaluated according to the unstable chromosomal aberrations induced. Biological effects of two types of cultivation of irradiated blood samples, the first immediately after irradiation and the second after 96 h storage, were studied. A significant difference in the incidence of chromosomal aberrations between these two types of samples was obtained, while our dose-response curve fitting coefficients alpha 1 = (7.71 +/- 0.09) x 10(-2) Gy-1 (immediate cultivation) and alpha 2 = (11.03 +/- 0.08) x 10(-2) Gy-1 (96 h delayed cultivation) are in both cases lower than could be found in the literature. PMID:1962281

  12. Measurement of DNA damage induced by irradiation with gamma-rays from a TRIGA Mark II research reactor in human cells using Fast Micromethod.

    Science.gov (United States)

    Hassanein, Hamdy; Müller, Claudia I; Schlösser, Dietmar; Kratz, Karl-Ludwig; Senyuk, Olga F; Schröder, Heinz C

    2002-06-01

    The Fast Micromethod is a novel quick and convenient microplate assay for determination of DNA single-strand breaks. This method measures the rate of unwinding of cellular DNA upon exposure to alkaline conditions using a fluorescent dye which preferentially binds to double-stranded DNA. Here we applied this method to determine the levels of DNA single-strand breaks in HeLa cells induced by y-irradiation deriving from fission isotopes and activation products at the TRIGA Mark II research reactor in Mainz. An increased strand scission factor (SSF) value, which is indicative for DNA damage, was found at doses of 1 Gy and higher. A similar increase in SSF value, which further increased in a dose-dependent manner, was found in human peripheral blood mononuclear cells after irradiation with 6 MV X-rays from a linear accelerator to give a total exposure of 0.5 to 10 Gy. PMID:12064446

  13. Measurements of miniature ionization chamber currents in the JSI TRIGA Mark II reactor demonstrate the importance of the delayed contribution to the photon field in nuclear reactors

    Science.gov (United States)

    Radulović, Vladimir; Fourmentel, Damien; Barbot, Loïc; Villard, Jean-François; Kaiba, Tanja; Gašper, Žerovnik; Snoj, Luka

    2015-12-01

    The characterization of experimental locations of a research nuclear reactor implies the determination of neutron and photon flux levels within, with the best achievable accuracy. In nuclear reactors, photon fluxes are commonly calculated by Monte Carlo simulations but rarely measured on-line. In this context, experiments were conducted with a miniature gas ionization chamber (MIC) based on miniature fission chamber mechanical parts, recently developed by the CEA (French Atomic Energy and Alternative Energies Commission) irradiated in the core of the Jožef Stefan Institute TRIGA Mark II reactor in Ljubljana, Slovenia. The aim of the study was to compare the measured MIC currents with calculated currents based on simulations with the MCNP6 code. A discrepancy of around 50% was observed between the measured and the calculated currents; in the latter taking into consideration only the prompt photon field. Further experimental measurements of MIC currents following reactor SCRAMs (reactor shutdown with rapid insertions of control rods) provide evidence that over 30% of the total measured signal is due to the delayed photon field, originating from fission and activation products, which are untreated in the calculations. In the comparison between the measured and calculated values, these findings imply an overall discrepancy of less than 20% of the total signal which is still unexplained.

  14. 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)

    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)

  15. 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. PMID:24316530

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

    International Nuclear Information System (INIS)

    The neutronic and thermal hydraulic analysis of the 3 MW TRIGA MARK II research reactor to upgrade it is presented. The upgrading will need a major reshuffling and reconfiguration of the current core. To realize this objective, the overall strategy followed is: 1.) generation of problem dependent cross section library from basic Evaluated Nuclear Data Files such as ENDF/B-VI, JENDL3.2 with NJOY94.10+, 2.) use WIMSD-5 package to generate cell constants for all of the materials in the core and its immediate neighborhood, 3.) use CITATION to perform 3-D global analysis of the core to study multiplication factor, neutron flux and power distributions, power peaking factors, temperature reactivity coefficients, etc., 4.) couple output of CITATION with PARET to study thermal hydraulic behavior to predict safety margins, 5.) check the validity of the deterministic codes with the Monte Carlo code MCNP4B2 , and 6.) reshuffle the current core configuration to achieve the desired objectives. The computational methods, tools and techniques, customization of cross section libraries, various models for cells and super cells, and a lot of associated utilities have been standardized and established/validated for the overall core analysis

  17. Analysis of the DNB ratio and the loss-of-flow accident (LOFA) of the 3 MW TRIGA MARK II research reactor

    International Nuclear Information System (INIS)

    The PARET code was used to analyze two most important thermal hydraulic design parameters of the 3 MW TRIGA MARK II research reactor. The first design parameters is the DNB (departure from nucleate boiling) ratio, which is defined as the ratio of the critical heat flux to the heat flux achieved in the core and was computed by means of a suitable correlation as defined in PARET code. The reactor core should be designed so as to prevent the DNBR from dropping below a chosen value under a high heat flux transient condition for the most adverse set of mechanical and coolant conditions. Over the length 0.381 m of the hottest channel the DNB ratio varies, starting from 3.8951 to 5.4031, with a minimum of 2.7851. The peak heat flux occurs at the axial center of the fuel elements; therefore the DNB ratio is minimum at this location. The second design parameter is the loss-of-flow accident scenario of the TRIGA reactor. The Bergles-Rohsenow correlation was selected for detecting onset of nucleate boiling, the transition model with the McAdams correlation was included for fully developed two-phase flow, and the Seider-Tate correlation was used for the single-phase forced convection regime. The loss-of-flow transient after a trip time of 4.08 sec at 85% of loss of normal flow for the TRIGA core shows a peak temperature of 709.22 C in the fuel centerline and 131.94 C in the clad and 46.63 C in the coolant exit of the hottest channel. The transient was terminated at 15% of nominal flow after about 48.0 sec. The time at which the reversal of coolant flow starts is about 67.0 sec. (author)

  18. Neutron flux characterization of the Moroccan Triga Mark II research reactor and validation of the k0 standardization method of NAA using k0-IAEA program

    International Nuclear Information System (INIS)

    The aim of this work was to implement and to validate the k0 standardization method in neutron activation analysis (k0-NAA) at the Moroccan TRIGA Mark II research reactor. This technique was used in order to determine, the calibration of several HPGe detectors and calibration of neutron flux parameters in the typical irradiation channels [rotary specimen rack (RSR) and the pneumatic tube system (PTS) facilities]. Calibrations and calculations of k0-NAA results were carried out using the k0-IAEA program. 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 PTS as in the RSR facilities 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 RSR and the PTS facilities. This can be explained by the fact that the RSR channel is situated in a graphite reflector and is relatively far from the reactor core, while the PTS is in the core. Five reference materials of different origin obtained from USGS (basalt BE-N, bauxite BX-N, biotite mica-Fe, granite GS-N) and IAEA (Soil-7) were used to evaluate the validity of this method in our laboratory by analyzing the elemental concentrations with respect to the certified values. In general, good agreement was obtained between results of this work and values in certificates of the individual reference materials, thus proving the accuracy of our results and successful implementation of the method for analysis of real samples. (author)

  19. Validation of WIMS-SNAP code systems for calculations in TRIGA-MARK II type reactors; Validacion del sistema de codigos WIMS-SNAP para calculos en reactores nucleares tipo TRIGA-MARK II

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez Valle, S.; Lopez Aldama, D. [Centro de Investigaciones Nucleares, Tecnologicas y Ambientales, La Habana (Cuba). E-mail: svalle@ctn.isctn.edu.cu

    2000-07-01

    The following paper contributes to validate the Nuclear Engineering Department methods to carry out calculations in TRIGA reactors solving a Benchmark. The benchmark is analyzed with the WIMS-D/4-SNAP/3D code system and using the cross section library WIMS-TRIGA. A brief description of the DSN method is presented used in WIMS/d{sup 4} code and also the SNAP-3d code is shortly explained. The results are presented and compared with the experimental values. In other hand the possible error sources are analyzed. (author)

  20. Estimation of (41)Ar activity concentration and release rate from the TRIGA Mark-II research reactor.

    Science.gov (United States)

    Hoq, M Ajijul; Soner, M A Malek; Rahman, A; Salam, M A; Islam, S M A

    2016-03-01

    The BAEC TRIGA research reactor (BTRR) is the only nuclear reactor in Bangladesh. Bangladesh Atomic Energy Regulatory Authority (BAERA) regulations require that nuclear reactor licensees undertake all reasonable precautions to protect the environment and the health and safety of persons, including identifying, controlling and monitoring the release of nuclear substances to the environment. The primary activation product of interest in terms of airborne release from the reactor is (41)Ar. (41)Ar is a noble gas readily released from the reactor stacks and most has not decayed by the time it moves offsite with normal wind speed. Initially (41)Ar is produced from irradiation of dissolved air in the primary water which eventually transfers into the air in the reactor bay. In this study, the airborne radioisotope (41)Ar generation concentration, ground level concentration and release rate from the BTRR bay region are evaluated theoretically during the normal reactor operation condition by several governing equations. This theoretical calculation eventually minimizes the doubt about radiological safety to determine the radiation level for (41)Ar activity whether it is below the permissible limit or not. Results show that the estimated activity for (41)Ar is well below the maximum permissible concentration limit set by the regulatory body, which is an assurance for the reactor operating personnel and general public. Thus the analysis performed within this paper is so much effective in the sense of ensuring radiological safety for working personnel and the environment. PMID:26736180

  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. Thermal-Hydraulic Analysis of the 3-MW TRIGA MARK-II Research Reactor Under Steady-State and Transient Conditions

    International Nuclear Information System (INIS)

    Important thermal-hydraulic parameters of the 3-MW TRIGA MARK-II research reactor operating under both steady-state and transient conditions are reported. Neutronic analyses were performed by using the CITATION diffusion code and the MCNP4B2 Monte Carlo code. The output of CITATION and MCNP4B2 were input to the PARET thermal-hydraulic code to study the steady-state and transient thermal-hydraulic behavior of the reactor. To benchmark the PARET model, data were obtained from different measurements performed by thermocouples in the instrumented fuel (IF) rod during the steady-state operation both under forced- and natural-convection mode and compared with the calculation. The mass flow rates needed for input to PARET were taken from the Final Safety Analysis Report for a downward forced coolant flow equivalent to 3500 gal/min. For natural convection cooling of the reactor, the mass flow rate was generated using the NCTRIGA code. Peak fuel temperatures measured by the thermocouples in the IF rods at different power levels of the TRIGA core were compared with the values calculated by PARET. The axial distribution of the temperatures of the fuel centerline, fuel surface, and the cladding surface in the hot channel were calculated for the reactor operating at the full-power level. Fuel surface heat flux and heat transfer coefficients for the hot channel were also calculated for the reactor operating at the full-power level. The investigated results were found to be in good agreement with the experimental and operational values. The testing of the PARET model calculations through benchmarking the available TRIGA experimental and operational data for pulse-mode operations showed that PARET can successfully be used to analyze the transient behavior of the reactor. Major transient parameters, such as peak power and prompt energy released after pulse, full-width at half-maximum of pulse peak, and maximum fuel centerline temperatures for different fuel elements at different

  3. Present and future beam tube experiments at the 250 kW TRIGA Mark II reactor Wien

    International Nuclear Information System (INIS)

    The four beam tubes and the thermal column at the TRIGA reactor Wien were well used in the reporting period. Since the thermal column is used as a gamma source for different irradiation experiments and as a neutron source for radiography, the other facilities are mainly used for neutron spectroscopy experiments: polarized neutrons, neutron interferometry, small angle scattering and neutron choppers, In the piercing beam tube a fast rabbit system is installed which is mainly used for high precision activation analysis. (author)

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

    International Nuclear Information System (INIS)

    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)

    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. An experience on the purification of bacterially infested I.T.U. TRIGA Mark-II reactor water

    International Nuclear Information System (INIS)

    Because of the failure of conductivity meter at the makeup water purification system, highconductivity water was added into the tank water. For this reason, the conductivity of the tank water rose to 12.5 μS/cm and the tank water became turbid. Bacteriological analysis showed that the tank water became infested with bacteria. A suitable method for the sterilization of the tank water by means of the irradiation and the chemical materials was searched. Hydrogen-Peroxide (H2P2) was chosen as the most suitable material for the chemical sterilization. However, it was not used since it was not experienced in any reactor previously and the tank water was cleaned from the bacteria by means of the irradiation and the purification system. The makeup water purification system was modified permanently for this purpose. As a result, conductivity of the tank water was decreased to 0.2 μS/cm by using this modified system. Some new experiences about the purification and protection of tank water from the bacteria were gained during these operations. (orig.)

  7. 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)

    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, keff, 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

  8. Estimation of radiological doses due to the failure of a single element of a 3 MW (T) TRIGA Mark-II research reactor

    International Nuclear Information System (INIS)

    Radiological doses due to the failure of a single fuel element of a 3 MW (t) TRIGA Mark-II Research Reactor was estimated for both anticipated and design basis releases considering hypothetical accident conditions. The noble gas and halogen fission product inventory has been calculated assuming a burn-up of 2000 MWd occurring in 1.8 calendar years. For both of the releases, one hundred percent of the noble gases in the fuel-cladding gap were assumed to release from the fuel element and subsequently transferred directly to the reactor hall and twenty-five percent of the halogens in the fuel-cladding gap were assumed to release from the fuel element (with the remainder assumed to plat out on the relatively cool cladding). For the removal of the fission product gases from the reactor hall to the environment, two mechanisms were considered. These are: (1) removal by the emergency ventilation system through an activated charcoal trap in the event of a design basis release and (2) removal by the normal ventilation system for anticipated release. For the first removal mechanism, the system has been designed with activated charcoal filters having an efficiency of 0% for noble gases and 99 % for halogens. For both the cases, only the bottom one-fifth of the reactor hall volume was assumed to be involved in the air circulation (i.e., the top four-fifths was considered to be stagnant). The dispersion of the escaped fission products to the environment through the stack of the reactor was estimated using a Gaussian plume model and basing on the design parameters of the TRIGA reactor as well as the meteorological data of the site. Total individual doses in the reactor hall as well as in the environment were calculated applying the methodologies described in the IAEA publications with the assumptions as mentioned above. The total dose was regarded as the doses caused by immersion in the radioactive air plume (for both noble gas and halogen), inhaled halogen and the deposited

  9. Experience in the operation and maintenance of the L.E.N.A. 250 kW TRIGA Mark II reactor at the University of Pavia, 1966-1970

    International Nuclear Information System (INIS)

    Experience in the operation and maintenance of the L.E.N.A. 250 Kw TRIGA Mark II reactor at the University of Pavia - Italy is described. First the Laboratorio Energia Nucleare Applicata (L.E.N.A.) is presented including some historical notes, administration and personnel. Reactor operation since 1966 is reported together with the cost of a recent one year period. Some minor operational difficulties such as a crack in the biological shield and fuel element elongations are described in detail. The activity of the health physics group is also presented. (author)

  10. Criticality and Safety Parameter Studies of a 3-MW TRIGA MARK-II Research Reactor and Validation of the Generated Cross-Section Library and Computational Method

    International Nuclear Information System (INIS)

    This study deals with the analysis of some neutronics and safety parameters of the current core of a 3-MW TRIGA MARK-II research reactor and validation of the generated macroscopic cross-section library and calculational techniques by benchmarking with experimental, operational, and available Safety Analysis Report (SAR) values. The overall strategy is: (a) generation of the problem-dependent cross-section library from basic Evaluated Nuclear Data Files such as ENDF/B-VI and JENDL-3.2 with NJOY94.10+, (b) use of the WIMSD-5 package to generate a few-group neutron macroscopic cross section for all of the materials in the core and its immediate neighborhood, (c) use the three-dimensional CITATION code to perform the global analysis of the core, and (d) checking of the validity of the CITATION diffusion code with the MCNP4B2 Monte Carlo code. The ultimate objective is to establish methods for reshuffling the current core configuration to upgrade the thermal flux at irradiation locations for increased isotope production. The computational methods, tools and techniques, customization of cross-section libraries, various models for cells and supercells, and many associated utilities are standardized and established/validated for the overall neutronic analysis. The excess reactivity, neutron flux, power distribution, power peaking factors, determination of the hot spot, and fuel temperature reactivity coefficients αf in the temperature range of 45 to 1000 deg. C are studied. All the analyses are performed using the 4- and 7-group libraries of the macroscopic cross sections generated from the 69-group WIMSD-5 library. The 7-group calculations yield comparatively better agreement with the experimental value of keff and the other core parameters. The CITATION test runs using different cross-section sets based on the different models applied in the WIMSD-5 calculations show a strong influence of those models on the final integral parameter. Some of the cells are specially

  11. 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

    Energy Technology Data Exchange (ETDEWEB)

    Khan, Jahirul Haque [Bangladesh Atomic Energy Commission, Dhaka (Bangladesh)

    2013-07-01

    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

  12. 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)

    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

  13. TRIGA Mark II benchmark experiment

    International Nuclear Information System (INIS)

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

  14. Ljubljana TRIGA Mark II, 40 years of successful operation

    International Nuclear Information System (INIS)

    The research reactor TRIGA Mark II at the 'Jozef Stefan' Institute is located in the vicinity of Ljubljana. It was designed by General Atomics. It was commissioned in 1966 and reconstructed and equipped for pulse mode operation in 1991. It is a 250 kW light water pool type reactor cooled by natural convection and designed for training, research with neutrons and isotope production. The reactor has accumulated 40 years of continuous operation without any failure of major equipment or any event violating safety limits. After reconstruction, the reactor was loaded with fresh, low enriched fuel elements. All spent fuel elements were shipped back to the USA in 1999. Ten fresh fuel elements were exported to France in July 2007. The questions related to nuclear safety are treated in detail in a TRIGA Mark II Safety Analysis Report. The enforcement is provided by national and international bodies. New regulations for research reactors are currently under preparation in Slovenia. The requirement for a research reactor periodic safety review will be included in new regulations. The graded approach to safety is taken into account. Application of the IAEA 'Code of Conduct on the Safety of Research Reactors' will be accomplished through the new regulations pertaining to all stages in the life of the reactor. TRIGA has been playing an important role in developing nuclear technology and safety culture in Slovenia. At present it is planned that the reactor will operate at least until 2016. (author)

  15. Ljubljana TRIGA Mark II, 40 years of successful operation

    International Nuclear Information System (INIS)

    The research reactor TRIGA Mark II is part of the Jozef Stefan Institute, located near Ljubljana. It was built by General Atomics. The research reactor was commissioned in 1966 and in 1991 it was reconstructed and equipped for pulse mode operation. The reactor TRIGA Mark II is a typical 250 kW light water reactor cooled by natural convection. It is designed for training in reactor operation and technology, research with neutrons and isotope production. It has been used for experiments in the following fields: solid state physics, neutron radiography, reactor physics including burn up measurements and calculations, boron neutron capture therapy, environmental studies and researches of advanced materials. The reactor has accumulated 40 years of continuous operation without any failure of major equipment or any event violating safety standards. There has been no release of radioactivity into the environment exceeding limiting values prescribed by the regulatory requirements. Major refurbishment included installation of a pulse rod, reconstruction of control mechanisms and control units, replacement of the primary coolant pumps with new ones, modification of a spent fuel storage pool and installation of new pneumatic mail. The United States nuclear non-proliferation policy provided Slovenia with the opportunity to return the spent fuel from the research reactor TRIGA Mark II back to the USA. After reconstruction, the reactor was loaded with fresh low enrichment fuel elements and all spent fuel elements were shipped back to the USA in July 1999. At present there are 94 fuel elements with 20% enriched uranium on site. All questions related to nuclear safety are treated in detail in a Safety Analysis Report. Its operation is regulated by several national and international nuclear laws, regulations and standards. The enforcement is provided by national and international bodies: Slovenian Nuclear Safety Administration (SNSA), Health Inspectorate of the Republic of Slovenia

  16. Deployment of a three-dimensional array of Micro-Pocket Fission Detector triads (MPFD3) for real-time, in-core neutron flux measurements in the Kansas State University TRIGA Mark-II Nuclear Reactor

    Science.gov (United States)

    Ohmes, Martin Francis

    A Micro-Pocket Fission Detector (MPFD) is a miniaturized type of fission chamber developed for use inside a nuclear reactor. Their unique design allows them to be located between or even inside fuel pins while being built from materials which give them an operational lifetime comparable to or exceeding the life of the fuel. While other types of neutron detectors have been made for use inside a nuclear reactor, the MPFD is the first neutron detector which can survive sustained use inside a nuclear reactor while providing a real-time measurement of the neutron flux. This dissertation covers the deployment of MPFDs as a large three-dimensional array inside the Kansas State University TRIGA Mark-II Nuclear Reactor for real-time neutron flux measurements. This entails advancements in the design, construction, and packaging of the Micro-Pocket Fission Detector Triads with incorporated Thermocouple, or MPFD3-T. Specialized electronics and software also had to be designed and built in order to make a functional system capable of collecting real-time data from up to 60 MPFD3-Ts, or 180 individual MPFDs and 60 thermocouples. Design of the electronics required the development of detailed simulations and analysis for determining the theoretical response of the detectors and determination of their size. The results of this research shows that MPFDs can operate for extended times inside a nuclear reactor and can be utilized toward the use as distributed neutron detector arrays for advanced reactor control systems and power mapping. These functions are critical for continued gains in efficiency of nuclear power reactors while also improving safety through relatively inexpensive redundancy.

  17. Control System Dynamics Analysis Of TRIGA Mark II Bandung

    International Nuclear Information System (INIS)

    The root locus analysis of TRIGA MARK II reactor was performed. The parameters were calculated based from the experimental data. The experiment was performed between 100 kW to 1 MW of power, average fuel temperature was 189oC and water average temperature was 37.3oC to measure temperature and xenon poisoning feedback. On the design analysis of PID system the characteristic of the controller are gain K=2.72, tp=13.65 seconds, Mp=0.0075%, Ti=4.1 seconds and Td=0.24 seconds. The controller transient time is less than 30 seconds and the settling time is less than 2% as well

  18. Operation maintenance and utilization of the TRIGA Mark II reactor at the University of Pavia in the time period July 1978 - June 1980

    International Nuclear Information System (INIS)

    In the past two years the reactor was operated 1653 hours at steady - state full power (250 kW). During the same period, July 1978 - June 1980, 680 applications for reactor use were submitted. Total reactor time utilized (6843 hours) is increased in comparison with the previous two years period. Some modernization to the equipment is also made

  19. EURACOS II facility in the modified thermal column of the TRIGA Mark II reactor at the University of Pavia LENA Laboratory

    International Nuclear Information System (INIS)

    The EURACOS II (Enriched Uranium Converter Source) project foresees the installation of an U--Al alloy converter plate at the end of the thermal column in the Pavia University LENA reactor. The incident thermal flux on the 5 Kg of 235U generates a fast neutron source whose power is 0.4 kW. The fast flux near the center exceeds 109 neutrons/cm2-sec. The fission plate is cooled by a forced air flow of 500 m3/h; the use of air instead of water reduces to a minimum the initial spectrum deformation of source neutrons. An irradiation chamber of 3.75 x 1.5 x 1.8 m3 is placed in front of the source and contains the mock-up under investigation. The facility is principally intended for benchmark-and mock-up-experiments in the reactor shielding field, but irradiations to different types and materials not directly related to shielding can be extended. The modification of the TRIGA thermal column, the characteristics of the EURACOS II facility, and the experiments now in preparation are described. The source intensity allows the study of neutron attenuation factor of 105 for fast, and 108 for thermal neutrons. The neutron spectra are investigated with the sandwich technique in the epithermal range, and with threshold detectors, organic and telescopic spectrometers in the fast energy range. (U.S.)

  20. TRIGA Mark II Criticality Benchmark Experiment with Burned Fuel

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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)

  2. Current research projects at the Austrian TRIGA Mark II. High sensitive detection of rare fission gas release of a fuel element sample of the TRIGA Mark II reactor in Vienna

    International Nuclear Information System (INIS)

    It is intended to study the temperature dependent release of rare fission gas products, thus providing information for the calculation of cladding material thickness and burn-up. The fuel clement sample has a diameter of 15/32 inch and 1/2 inch height. The temperature is controlled by 5 thermocoax thermocouples. Pellet, thermocouples and heating coils are encapsulated in a stainless steel tube with an inlet and an outlet for the Helium carrier stream. The Helium is free of Ar, Kr and Xe. The counter system consists of a NaJ crystal in connection with two photomultipliers, the crystal being surrounded by two coaxial annular proportional counters. The radioactive gases are measured while they are flowing through the counting volume

  3. Temperature feedback of TRIGA MARK-II fuel

    Energy Technology Data Exchange (ETDEWEB)

    Usang, M. D., E-mail: mark-dennis@nuclearmalaysia.gov.my; Minhat, M. S.; Rabir, M. H.; Rawi, M. Z. M. [Malaysia Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)

    2016-01-22

    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.

  4. 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.

  5. Temperature feedback of TRIGA MARK-II fuel

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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)

  7. TRIGA MARK-II source term

    Energy Technology Data Exchange (ETDEWEB)

    Usang, M. D., E-mail: mark-dennis@nuclearmalaysia.gov.my; Hamzah, N. S., E-mail: mark-dennis@nuclearmalaysia.gov.my; Abi, M. J. B., E-mail: mark-dennis@nuclearmalaysia.gov.my; Rawi, M. Z. M. Rawi, E-mail: mark-dennis@nuclearmalaysia.gov.my; Abu, M. P., E-mail: mark-dennis@nuclearmalaysia.gov.my [Bahagian Teknologi Reaktor, Agensi Nuklear Malaysia, 43000 Kajang (Malaysia)

    2014-02-12

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

  8. TRIGA MARK-II source term

    Science.gov (United States)

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

    2014-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Paik, S.T.; Park, S.K.; Chung, K.W.; Chung, U.S.; Jung, K.J. [Nuclear Fuel Cycle Development Group, Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-08-01

    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)

  10. ÝTÜ TRIGA MARK-II REAKTÖRÜNDE ÞEBEKE FREKANSI ETKÝSÝNÝN DALGACIK ANALÝZÝYLE FÝLTRELENMESÝ

    OpenAIRE

    BARUTCU, Burak; EKER, Serhat

    2011-01-01

    In this research, data acquisition studies for signals from the neutron detectors and fuel thermo -couplesof ITU TRIGA MARK-II nuclear reactor was implemented. Also, spectral properties related to the datawere examined using frequency and time-frequency domain techniques. Fundamental frequencycomponent at 50 Hz of electric power network and its harmonics were removed from the originalsignals by wavelet analysis approach.Key Words : TRIGA MARK II Nuclear Reactor, frequency domain analysis, Wav...

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

    International Nuclear Information System (INIS)

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

  12. Radiochemical measurement of neutron-spectrum averaged cross sections for the formation of {sup 64}Cu and {sup 67}Cu via the (n,p) reaction at a TRIGA Mark-II reactor. Feasibility of simultaneous production of the theragnostic pair {sup 64}Cu/{sup 67}Cu

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M. Shuza; Hossain, Syed Mohammod [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology; Rumman-uz-Zaman, M. [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology; Dhaka Univ. (Bangladesh). Dept. of Applied Chemistry and Chemical Engineering; Qaim, Syed M. [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Neurowissenschaften und Medizin (INM-5) - Nuklearchemie

    2014-09-01

    Integral cross sections of the {sup 64}Zn(n,p){sup 64}Cu and {sup 67}Zn(n,p){sup 67}Cu reactions were measured for the fast neutron spectrum of TRIGA Mark-II reactor at Savar, Dhaka, Bangladesh. A clean radiochemical separation was performed to isolate the copper radionuclides from the target element zinc. The radioactivities produced in the irradiation were measured by HPGe γ-ray spectroscopy. The neutron flux over the energy range 0.5-20 MeV was determined using the {sup 58}Ni(n,p){sup 58}Co monitor reaction. The measured results amount to 28.9 ± 2.0 mb and 0.84 ± 0.07 mb for the formation of {sup 64}Cu and {sup 67}Cu, respectively. These values are slightly lower than the respective values for a pure fission spectrum. The present results were compared with data calculated using the neutron spectral distribution and the recently critically analysed excitation function of each reaction given in the literature. The good agreement validates the reliability of those excitation functions. The feasibility of simultaneous production of {sup 64}Cu and {sup 67}Cu with fast neutrons is discussed. (orig.)

  13. Simulation of TRIGA Mark II Benchmark Experiment using WIMSD4 and CITATION codes; Simulacao com WIMSD4 e CITATION do Triga Mark II benchmark experiment

    Energy Technology Data Exchange (ETDEWEB)

    Dalle, Hugo Moura [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); Pereira, Claubia [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Dept. de Engenharia Nuclear

    2000-07-01

    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{sub 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{sub 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{sub eff} and fuel elements reactivity worth distribution. (author)

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

    OpenAIRE

    Mahmood, M. S.; 長家 康展; 森 貴正

    2004-01-01

    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. 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 keff obtained by the MVP...

  15. Gamma spectrometry inspection of TRIGA MARK II fuel using caesium isotopes

    International Nuclear Information System (INIS)

    Research highlights: → Cs isotopes are the best choices for the burn up determination of spent fuel. → Gamma spectrometer calibration using MCNP5. → Cs-ratio can be applied by relative calibration method. - Abstract: Gamma spectrometry is one of the common methods to inspect the spent fuel from research reactors. This method has been applied to in-pool measurements of the Spent Fuel Elements (SPEs) of the TRIGA Mark II research reactor. Due to mixed nature of the reactor core and complicated irradiation history of the fuel elements (FEs), the gamma spectrometry of the FE establishes improvements in the calculation and measurement of the SPE. In order to inspect the TRIGA SPE from dry storage and cooled fuel from the reactor pool, the selected spend fuels are scanned and measured using the fuel-scanning machine. Gamma spectrometry is performed by HPGe detector for spend fuel inspection and determination of the 137Cs activity and 134Cs/137Cs ratio. In this work, the steps of the detector calibration and the use of the Monte Carlo radiation transport code (MCNP5) have been described. In addition, the fuel-scanning machine and the gamma spectrometer are modelled by MCNP5 to simulate the gamma transport from fuel to detector. It also simulate the gamma spectrometer calibration for the burn up determination of the spend fuel. The results from MCNP5 simulation are applied to spectroscopic measurements and compared with the theoretical predictions of the neutronics code ORIGEN2 in this research work.

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

    International Nuclear Information System (INIS)

    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, Keff, 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 Keff 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 Keff and fuel elements reactivity worth distribution. (author)

  17. The startup tests for TRIGA Mark II at the Institute for Nuclear Energy

    International Nuclear Information System (INIS)

    This paper briefly describes the start-up tests for TRIGA Mark-II at the Institute for Nuclear Energy and some of the problems during the construction. This Report consists of three parts: 1. Shield Construction and Installation of ITU-TRR Components. 2. Start-up Experiments. 3. Experience Gained in Operation and Maintenance

  18. Investigation of subcritical multiplication parameters in TRIGA Mark II accelerator driven system

    International Nuclear Information System (INIS)

    Highlights: • TRIGA ADS neutron external source was numerically investigated. • Source target material, radius, position, and incident beam energy were studied. • Maximum neutron yield for W, Pb, and W–Cu targets are at radii 3.25, 3.5 and 7 cm. • Maximum source efficiency for targets at the given core is achieved at the center. • Maximum source efficiency is achieved at 40 MeV incident electron beam energy. - Abstract: The accelerator driven system (ADS) is a very interesting option to improve the safety of nuclear power reactor and for transmutation of spent fuel. The Texas phase of the reactor–accelerator coupling experiment (RACE), completed in March 2006, demonstrated the feasibility of operating a training research isotopes general atomic (TRIGA) research reactor in a subcritical configuration driven to a significant power by an electron LINAC neutron source (photoneutron). In the present study, the effects of changing the source cylindrical target material, radius, position and the electron beam energy on the final neutron production, fission probability, and the subcritical system multiplication of TRIGA Mark II research reactor, have been numerically investigated. Three target materials are used: Tungsten, Lead and Tungsten–Copper alloy, while varying the target radius from 2 to 8 cm, the source position at three locations, and the beam energy from 10 to 55 MeV. The investigation is based on the numerical calculation of the subcritical multiplication factor and the external source efficiency using Monte Carlo MCNPX code. Through the comparison of the studied cases results, the favorable target material and radius, source position, and beam energy can be obtained

  19. An Object Oriented Approach to Simulation of TRIGA Mark II Dynamic Response

    International Nuclear Information System (INIS)

    This paper deals with the development of a model for the nuclear research reactor TRIGA Mark II operating at University of Pavia. The purpose of the modeling is to reproduce the dynamic behavior of the reactor on the entire operative power range, i.e. 0-250 kW, using the object oriented approach, implemented by the Modelica language. The main advantage is the a-causal formulation of the model, based on equations instead of statement assignment. Equations do not specify which variables are inputs and which are outputs, thus the causality in the model is unspecified and is fixed only when the corresponding equation system is solved. In this way, equations can be solved according to the data flow context in which the solution is computed. The model describes the entire plant, including the heat removal system. The component representing the reactor core contains a series of sub-components linked together through rigorously defined interfaces: in this way, it is possible to consider the interactions between the different physical aspects of the system. Equations governing natural circulation have been implemented in a component which defines the mass flow rate through the core, according to the temperature difference at the ends of the channels. Secondary and tertiary cooling loops are modeled using a simplified heat exchangers configuration: concentric tube version is adopted, which allows recreating the heat exchange dynamics without a great modeling effort. The developed a-causal model has been validated through the comparison with experimental data collected on the site, concerning three different power transients at 100 kW, 50 kW and 1 kW. A corresponding causal model has been referenced as concerns fuel and coolant temperatures evolution during the transients. The predictions of the two main approaches to dynamic modeling have been compared. A very satisfying accordance is found as discrepancies observed on the coolant temperature are comprised between 0.5% and 1

  20. Radioactive waste management plan for TRIGA Mark-II and III deecommissioning activities

    International Nuclear Information System (INIS)

    A radioavtive waste management plan was set-up for the decontamination and decommissioning of the TRIGA Mark II and III. They were categorized by the radioactivity and by the physical properties, solid , liquid, gaseous radioactive waste. The gaseous waste will be treated by the existing filtration equipment. The use of temporary containment with a portable ventilation system is planned during the dismantling work where there is the potential to generate particles. Liquid radioactive waste will be concentrated by a natural evaporator and the concentrate will then be solidified by using cement. All of the solid wastes will be packed in a 4 m3 ISO container and stored until a final disposal facility for low- and intermediate-level radioactive waste is operational. This paper covers a general plan of the radioactive waste management during the TRIGA Mark-II and III decontamination and decommissioning activities. (author)

  1. A Zero Dimensional Model for Simulation of TRIGA Mark II Dynamic Response

    Energy Technology Data Exchange (ETDEWEB)

    Cammi, A.; Poli, A. Fusar; Ponciroli, R. [Politecnico di Milano, Department of Energy, Nuclear Engineering Division (CeSNEF), Via Ponzio 34/3, 20133 Milano (Italy); Tigliole, A. Borio Di [University of Pavia, Department of Nuclear and Theoretical Physics and Laboratory of Applied Nuclear Energy (L.E.N.A), Via Bassi 4, 27100 Pavia (Italy); Magrotti, G. [University of Pavia, Laboratory of Applied Nuclear Energy (L.E.N.A), Via Aselli 41, 27100 Pavia (Italy)

    2011-07-01

    In this paper the development of a model for the nuclear research reactor TRIGA Mark II operating at University of Pavia is presented. Purpose of the modeling is to reproduce the dynamic behavior of the reactor on the entire operative power range, i.e. 0-250 kW. A zero dimensional approach is accounted for and the coupling between neutronics and thermal-hydraulics in natural circulation is considered. The model has been validated through comparison with experimental data, concerning three different power transients. For neutronics, point reactor kinetics model with one energy group and six delayed neutron precursors groups has been adopted. The system reactivity can be modified moving the control rods, which allow the reactor to operate at different power levels. As far as thermal-hydraulics is concerned, two regions have been defined, i.e. the fuel and the coolant. Heat exchange (convective and conductive) has been modeled by proper adoption of a global heat transfer coefficient. This has been considered as a function of coolant mass flow rate through the core to introduce the effects of natural circulation, evaluated using Boussinesque approximation for buoyancy effects. Neutronics and thermal-hydraulics are coupled together by means of fuel and moderator temperature feedback coefficients. The large thermal inertia due to the mass of water in the tank containing the reactor core causes temperature variation during transients to be very small. Therefore, moderator temperature feedback coefficient can be neglected. On the contrary, the fuel temperature coefficient strongly influences the dynamic behavior of the system and has been estimated making a best-fit between the model response and the experimental data regarding positive reactivity insertion in the system at three different power levels, i.e. 1 kW, 50 kW and 100 kW. The results obtained show that the fuel temperature coefficient is a monotonically increasing function of fuel temperature and its magnitude is

  2. A Zero Dimensional Model for Simulation of TRIGA Mark II Dynamic Response

    International Nuclear Information System (INIS)

    In this paper the development of a model for the nuclear research reactor TRIGA Mark II operating at University of Pavia is presented. Purpose of the modeling is to reproduce the dynamic behavior of the reactor on the entire operative power range, i.e. 0-250 kW. A zero dimensional approach is accounted for and the coupling between neutronics and thermal-hydraulics in natural circulation is considered. The model has been validated through comparison with experimental data, concerning three different power transients. For neutronics, point reactor kinetics model with one energy group and six delayed neutron precursors groups has been adopted. The system reactivity can be modified moving the control rods, which allow the reactor to operate at different power levels. As far as thermal-hydraulics is concerned, two regions have been defined, i.e. the fuel and the coolant. Heat exchange (convective and conductive) has been modeled by proper adoption of a global heat transfer coefficient. This has been considered as a function of coolant mass flow rate through the core to introduce the effects of natural circulation, evaluated using Boussinesque approximation for buoyancy effects. Neutronics and thermal-hydraulics are coupled together by means of fuel and moderator temperature feedback coefficients. The large thermal inertia due to the mass of water in the tank containing the reactor core causes temperature variation during transients to be very small. Therefore, moderator temperature feedback coefficient can be neglected. On the contrary, the fuel temperature coefficient strongly influences the dynamic behavior of the system and has been estimated making a best-fit between the model response and the experimental data regarding positive reactivity insertion in the system at three different power levels, i.e. 1 kW, 50 kW and 100 kW. The results obtained show that the fuel temperature coefficient is a monotonically increasing function of fuel temperature and its magnitude is

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

    International Nuclear Information System (INIS)

    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)

  4. Design of the instrument fault detection for TRIGA Mark II Bandung

    International Nuclear Information System (INIS)

    The instrument fault detection of Bandung trigra mark II reactor has been designed. The validated reactor model was applied to design three instruments observers which each of them will estimate the reactor power, fuel element and coolant water temperatures. the observer inputs were the inputs and outputs of the system. By comparing the outputs of each observer, the faulty instrument can be determined. The result obtained from the reactor simulation show that there is no deviation in the steady state between observers and the model. All state variable of observer 1 are sensitive to power changes that these variables can be used to determine whether the fault occurs or not. On the contrary, only the 6th and 70th suite variables of observer 2 and 3 can be used to determine the instrument condition because these variables are sensitive to fuel element temperature changes for observer 2 and sensitive to coolant water temperature changes for observer 3. (author)

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

    Science.gov (United States)

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

    2016-01-01

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

  6. Benchmark analysis of TRIGA mark II reactivity experiment using a continuous energy Monte Carlo code MCNP

    International Nuclear Information System (INIS)

    The benchmark analysis of reactivity experiments in the TRIGA-II core at the Musashi Institute of Technology Research Reactor (Musashi reactor; 100 kW) was performed by a three-dimensional continuous-energy Monte Carlo code MCNP4A. The reactivity worth and integral reactivity curves of the control rods as well as the reactivity worth distributions of fuel and graphite elements were used in the validation process of the physical model and neutron cross section data from the ENDF/B-V evaluation. The calculated values of integral reactivity curves of the control rods were in agreement with the experimental data obtained by the period method. The integral worth measured by the rod drop method was also consistent with the calculation. The calculated values of the fuel and the graphite element worth distributions were consistent with the measured ones within the statistical error estimates. These results showed that the exact core configuration including the control rod positions to reproduce the fission source distribution in the experiment must be introduced into the calculation core for obtaining the precise solution. It can be concluded that our simulation model of the TRIGA-II core is precise enough to reproduce the control rod worth, fuel and graphite elements reactivity worth distributions. (author)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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)

  11. Benchmark analysis of criticality experiments in the TRIGA mark II using a continuous energy Monte Carlo code MCNP

    International Nuclear Information System (INIS)

    The criticality analysis of the TRIGA-II benchmark experiment at the Musashi Institute of Technology Research Reactor (MuITR, 100kW) was performed by the three-dimensional continuous-energy Monte Carlo code (MCNP4A). To minimize errors due to an inexact geometry model, all fresh fuels and control rods as well as vicinity of the core were precisely modeled. Effective multiplication factors (keff) in the initial core critical experiment and in the excess reactivity adjustment for the several fuel-loading patterns as well as the fuel element reactivity worth distributions were used in the validation process of the physical model and neutron cross section data from the ENDF/B-V evaluation. The calculated keff overestimated the experimental data by about 1.0%Δk/k for both the initial core and the several fuel-loading arrangements (fuels or graphite elements were added only to the outer-ring), but the discrepancy increased to 1.8%Δk/k for the some fuel-loading patterns (graphite elements were inserted into the inner-ring). The comparison result of the fuel element worth distribution showed above tendency. All in all, the agreement between the MCNP predictions and the experimentally determined values is good, which indicates that the Monte Carlo model is enough to simulate criticality of the TRIGA-II reactor. (author)

  12. The construction, installation and commissioning of the PUSPATI TRIGA reactor

    International Nuclear Information System (INIS)

    A TRIGA Mark II research reactor has been installed at the Tun Ismail Atomic Research Centre (PUSPATI), Selangor, Malaysia. The reactor was commissioned in July 1982. With the commissioning of the reactor, a new era in the development of nuclear science and technology in Malaysia has just begun. This report describes the construction, installation and commissioning of the reactor. (author)

  13. Component failure data base of TRIGA reactors

    International Nuclear Information System (INIS)

    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)

  14. Gamma residual radioactivity measurements on rats and mice irradiated in the thermal column of a TRIGA Mark II reactor for BNCT.

    Science.gov (United States)

    Protti, Nicoletta; Manera, Sergio; Prata, Michele; Alloni, Daniele; Ballarini, Francesca; di Tigliole, Andrea Borio; Bortolussi, Silva; Bruschi, Piero; Cagnazzo, Marcella; Garioni, Maria; Postuma, Ian; Reversi, Luca; Salvini, Andrea; Altieri, Saverio

    2014-12-01

    The current Boron Neutron Capture Therapy (BNCT) experiments performed at the University of Pavia, Italy, are focusing on the in vivo irradiations of small animals (rats and mice) in order to evaluate the effectiveness of BNCT in the treatment of diffused lung tumors. After the irradiation, the animals are manipulated, which requires an evaluation of the residual radioactivity induced by neutron activation and the relative radiological risk assessment to guarantee the radiation protection of the workers. The induced activity in the irradiated animals was measured by high-resolution open geometry gamma spectroscopy and compared with values obtained by Monte Carlo simulation. After an irradiation time of 15 min in a position where the in-air thermal flux is about 1.2 × 10(10) cm(-2) s(-1), the specific activity induced in the body of the animal is mainly due to 24Na, 38Cl, 42K, 56Mn, 27Mg and 49Ca; it is approximately 540 Bq g(-1) in the rat and around 2,050 Bq g(-1) in the mouse. During the irradiation, the animal body (except the lung region) is housed in a 95% enriched 6Li shield; the primary radioisotopes produced inside the shield by the neutron irradiation are 3H by the 6Li capture reaction and 18F by the reaction sequence 6Li(n,α)3H → 16O(t,n)18F. The specific activities of these products are 3.3 kBq g(-1) and 880 Bq g(-1), respectively. PMID:25353239

  15. Small Angle Neutron Scattering instrument at Malaysian TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

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

    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)

  16. Verification of Monte Carlo calculations of the neutron flux in typical irradiation channels of the TRIGA reactor, Ljubljana

    NARCIS (Netherlands)

    Jacimovic, R; Maucec, M; Trkov, A

    2003-01-01

    An experimental verification of Monte Carlo neutron flux calculations in typical irradiation channels in the TRIGA Mark II reactor at the Jozef Stefan Institute is presented. It was found that the flux, as well as its spectral characteristics, depends rather strongly on the position of the irradiati

  17. 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

  18. Upgrading Status Of Bandung Triga 2000 Reactor

    International Nuclear Information System (INIS)

    Upgrading Status Of Bandung TRIGA 2000 Reactor. Upgrading of TRIGA Mark II Reactor from 1000 k W to 2000 k W has been done. On June 24, 2000 it has been inaugurated by the Vice President, Madame Megawati Soekarnoputri. The solution of the problems faced in the upgrading should be described here since some experiences got during the process probably are very useful, especially the methods in finishing the project

  19. TRIGA research reactor activities around the world

    International Nuclear Information System (INIS)

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

  20. Fuel experience at a 37 year old TRIGA type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Boeck, H. [Atominstitut der Oesterreichischen Universitaeten, Wien (Austria)

    1999-07-01

    A survey is given on 37 years of TRIGA fuel experience at the 250 kW TRIGA Mark II reactor Vienna. Approximately 3000 fuel-years of experience have accumulated at this facility with only minor problems. Totally only 8 fuel elements had to be removed permanently from the core. Various inspection methods which have been developed throughout the years are described in this paper. (author)

  1. Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup

    OpenAIRE

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

    2014-01-01

    Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been carried out utilizing coupled point kinetics, neutronics and thermal hydraulics code EUREKA-2/RR. From the previous calculations of neutronics parameters including percentage burnup of individual fuel elements performed so far for 700 MWD burnt core of TRIGA reactor showed that the fuel rod predicted as hottest at the beginning of cycle (fresh core) was found to remain as the hottest until 200 ...

  2. Feasibility analysis of I-131 production in the Moroccan TRIGA research reactor

    International Nuclear Information System (INIS)

    Highlights: • A feasibility analysis for I-131 production at the Moroccan TRIGA MARK II research reactor was conducted. • Two production scenarios were discussed with several TeO2 target masses. • The MCNPX v2.7 computer code with its depletion capabilities was used. • A production activity of about 4.63 Ci per 80 MWh irradiation period is obtained. - Abstract: Since the commissioning of the Moroccan 2 MW TRIGA MARK II research reactor hosted by the Centre National de l’Energie des Sciences et des Techniques Nucléaires (CNESTEN), the latter institution has established a radioisotope production program to supply radiopharmaceuticals for use in nuclear medicine. This paper presents a feasibility analysis for I-131 production using two in-core irradiation positions within the Moroccan TRIGA MARK II research reactor. The MCNPX v2.7 code, with its depletion capabilities, was used for the evaluation of two different production scenarios using several masses of TeO2 target samples. The maximum achievable activities were found to be 3.90 Ci/week for scenario 1 and 4.63 Ci/week for scenario 2. Thermal analysis shows that safety limits of capsules used for these experiments were not violated

  3. Operation experience with the TRIGA reactor Wien

    Energy Technology Data Exchange (ETDEWEB)

    Boeck, H. (Atominstitut, Vienna (Austria))

    1999-12-15

    The TRIGA Mark-II reactor Wien has been in operation more than 36 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 cources at low power level. Pulse operation is rather infrequent with about 5 to 10 pulses per year. The TRIGA reactor Wien is well utilized and in an excellent technical state. There are no technical or economical reasons to consider an imminent shut-down. However, the present fuel return policy might influence the destiny of this facility in the next decade. (orig.)

  4. Extraction of pure thermal neutron beam for the proposed PGNAA facility at the TRIGA research reactor of AERE, Savar, Bangladesh

    Science.gov (United States)

    Alam, Sabina; Zaman, M. A.; Islam, S. M. A.; Ahsan, M. H.

    1993-10-01

    A study on collimators and filters for the design of a spectrometer for prompt gamma neutron activation analysis (PGNAA) at one of the radial beamports of the TRIGA Mark II reactor at AERE, Savar has been carried out. On the basis of this study a collimator and a filter have been designed for the proposed PGNAA facility. Calculations have been done for measuring neutron flux at various positions of the core of the reactor using the computer code TRIGAP. Gamma dose in the core of the reactor has also been measured experimentally using TLD technique in the present work.

  5. Extraction of pure thermal neutron beam for the proposed PGNAA facility at the TRIGA research reactor of AERE, Savar, Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Alam, S. (Physics Dept., Jahangirnagar Univ., Savar, Dhaka (Bangladesh)); Zaman, M.A. (Physics Dept., Jahangirnagar Univ., Savar, Dhaka (Bangladesh)); Islam, S.M.A. (Physics Dept., Jahangirnagar Univ., Savar, Dhaka (Bangladesh)); Ahsan, M.H. (Inst. of Nuclear Science and Technology (INST), AERE, Savar, Dhaka (Bangladesh))

    1993-10-01

    A study on collimators and filters for the design of a spectrometer for prompt gamma neutron activation analysis (PGNAA) at one of the radial beamports of the TRIGA Mark II reactor at AERE, Savar has been carried out. On the basis of this study a collimator and a filter have been designed for the proposed PGNAA facility. Calculations have been done for measuring neutron flux at various positions of the core of the reactor using the computer code TRIGAP. Gamma dose in the core of the reactor has also been measured experimentally using TLD technique in the present work. (orig.)

  6. Extraction of pure thermal neutron beam for the proposed PGNAA facility at the TRIGA research reactor of AERE, Savar, Bangladesh

    International Nuclear Information System (INIS)

    A study on collimators and filters for the design of a spectrometer for prompt gamma neutron activation analysis (PGNAA) at one of the radial beamports of the TRIGA Mark II reactor at AERE, Savar has been carried out. On the basis of this study a collimator and a filter have been designed for the proposed PGNAA facility. Calculations have been done for measuring neutron flux at various positions of the core of the reactor using the computer code TRIGAP. Gamma dose in the core of the reactor has also been measured experimentally using TLD technique in the present work. (orig.)

  7. Validation of the Monteburns code for criticality calculation of TRIGA reactors

    Energy Technology Data Exchange (ETDEWEB)

    Dalle, Hugo Moura [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); Jeraj, Robert [Jozef Stafan Institute, Ljubljana (Slovenia)

    2002-07-01

    Use of Monte Carlo methods in burnup calculations of nuclear fuel has become practical due to increased speed of computers. Monteburns is an automated computational tool that links the Monte Carlo code MCNP with the burnup and decay code ORIGEN2.1. This code system was used to simulate a criticality benchmark experiment with burned fuel on a TRIGA Mark II research reactor. Two core configurations were simulated and k{sub eff} values calculated. The comparison between the calculated and experimental values shows good agreement, which indicates that the MCNP/Monteburns/ORIGEN2.1 system gives reliable results for neutronic simulations of TRIGA reactors. (author)

  8. Monochromatic Neutron Tomography Using 1-D PSD Detector at Low Flux Research Reactor

    Science.gov (United States)

    Ashari, N. Abidin; Saleh, J. Mohamad; Abdullah, M. Zaid; Mohamed, A. Aziz; Azman, A.; Jamro, R.

    2008-03-01

    This paper describes the monochromatic neutron tomography experiment using the 1-D Position Sensitive Neutron Detector (PSD) located at Nuclear Malaysia TRIGA MARK II Research reactor. Experimental work was performed using monochromatic neutron source from beryllium filter and HOPG crystal monochromator. The principal main aim of this experiment was to test the detector efficiency, image reconstruction algorithm and the usage of 0.5 nm monochromatic neutrons for the neutron tomography setup. Other objective includes gathering important parameters and features to characterize the system.

  9. The investigation of nonlinear dynamics behaviour of ITU TIGRA Mark-II reactor

    International Nuclear Information System (INIS)

    In this study a new dynamic code, YAVCAN is developed and applied to ITU TRIGA Mark-II Reactor. The mathematical model of the code is based on seven neutronic and two thermal hydrolic equations. It is assumed that a core averaged fuel temperature is sufficient to define the reactivity feedback. Thus, promt temperature feedback effect is taken into consideration and delayed temperature feedback due to the changes in coolant temperature is neglected. Thermal-hydraul1c properties of the fuel and coolant depend on temperature. All equations can be solved simultaneously by using the modified Hansen's method (orig.)

  10. Studies of the behavior of a reactor neutron beam at the sample position of a diffractometer using silicon monochromators

    Science.gov (United States)

    Ahmed, F. U.; Ahsan, M. H.; Khan, Aysha A.; Kamal, I.; Awal, M. A.; Ahmad, A. A. Z.

    1992-02-01

    A computer program TISTA has been developed for calculation of different aspects of designing a double axis neutron spectrometer at the TRIGA Mark II research reactor of the Atomic Energy Research Establishment, Dhaka, Bangladesh. The mathematical algorithms used in this program are based on the formalisms used by Fischer, Sabine and Bacon. Angle and energy resolutions and flux density as functions of neutron wave length, beam collimation, crystal asymmetry and deviation from zero-Bragg-angle position for different silicon crystal planes (111, 220, 311) have been calculated.

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

    International Nuclear Information System (INIS)

    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

  12. Status report of Indonesian research reactors

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

  14. Qualitative Analysis on Void Fraction of TRIGA 2000 Reactor in Bandung

    International Nuclear Information System (INIS)

    A qualitative analysis concerning the void fraction of TRIGA 2000 reactor has been done. That analysis is performed by studying the void phenomenon theoretically, followed by studying the cooling system performance, measuring the fuel element and cooling temperature, and visually observing the operation of reactor system. TRIGA 2000 reactor is a TRIGA Mark II reactor, which originally has 1000 kW thermal power, and then is upgraded up to 2000 kW. During reactor operation, voids are observed beginning at 1000 kW power and increased at higher power. The are several probability on where the voids come from. They might be caused by boiling process, water radiolysis, pump leakage, or cavitation. From the analysis performed, the voids might be caused by nucleate boiling, which do not affect the safety of reactor operation at certain margin. (author)

  15. 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.

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

    Science.gov (United States)

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

    2016-05-01

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

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

    Science.gov (United States)

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

    2015-10-01

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

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

    International Nuclear Information System (INIS)

    Currently, four research reactors with a thermal power ranging from 0.1 to 23 MWth are in operation in Germany and one new reactor (20 MWth) 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 kWth and in the pulse mode with a peak power of 250 MWth. 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.)

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

    Science.gov (United States)

    Ciftcioglu, Özer

    1987-05-01

    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 converted 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 program 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.

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

    International Nuclear Information System (INIS)

    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

  1. ENEA TRIGA RC -1 research reactor and trade project: An important contribution to the ADS road map

    International Nuclear Information System (INIS)

    TRIGA Mark II reactor of ENEA's Casaccia research Center (in Italy named RC-1) reached first criticality in 1960 and it is still running at 1 MW power level, mainly for short mean life time radioisotopes production (for medical purposes) and neutron radiography. Since 2001, plant personnel and other national/international scientist, were involved in the TRADE (TRiga Accelerator Driven Experiment) project. TRADE experiment, that consists in the coupling of an external proton accelerator to a target to be installed in the central channel of the TRIGA core scrammed to sub-criticality, was based on an original idea of Prof. Carlo Rubbia, presented at CEA in October 2000 and was aimed at a global demonstration of the ADS concept. The TRADE layout, the studies about Target, Target Cooling System, Shielding and other matters that were investigated will be described in order to evidence their impact on the Triga reactor and reactor activity. (author)

  2. 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.

  3. Power and neutron flux calculation for the PUSPATI TRIGA Reactor using MCNP

    International Nuclear Information System (INIS)

    The Malaysian 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency 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 calculation of neutron flux and power distribution in PUSPATI TRIGA REACTOR (RTP) 14th core configuration. The 3-D continuous energy Monte Carlo code MCNP was used to develop a versatile and accurate full model of the TRIGA core and fuels. 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 as well as S (α, β) thermal neutron scattering functions distributed with the MCNP code were used. Results of calculations are analyzed and discussed. (author)

  4. Increasing the power of FiR 1 TRIGA reactor by a factor of 2 1/2

    International Nuclear Information System (INIS)

    An early domestic reactor engineering project was increasing the neutron flux of the Triga Mark II reactor in Otaniemi by a factor of 2 1/2, thirty-five years ago. The thermal power of the facility was increased from 100 kW to 250 kW by modifications made in the fuel loading, control rods, control and protection systems, radiation shielding structures and in the heat removal system. This improved the efficiency of the plant and reduced time requirements in proportion for physical research, isotope production and medical irradiations. Experimental runs were made at 318 kW power, and the final approval inspection for continuous operation at 250 kW was completed on August 3, 1967. (author)

  5. 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. PMID:22885391

  6. Preparation and quantification of radioactive particles for tracking hydrodynamic behavior in multiphase reactors.

    Science.gov (United States)

    Yunos, Mohd Amirul Syafiq Mohd; Hussain, Siti Aslina; Yusoff, Hamdan Mohamed; Abdullah, Jaafar

    2014-09-01

    Radioactive particle tracking (RPT) has emerged as a promising and versatile technique that can provide rich information about a variety of multiphase flow systems. However, RPT is not an off-the-shelf technique, and thus, users must customize RPT for their applications. This paper presents a simple procedure for preparing radioactive tracer particles created via irradiation with neutrons from the TRIGA Mark II research reactor. The present study focuses on the performance evaluation of encapsulated gold and scandium particles for applications as individual radioactive tracer particles using qualitative and quantitative neutron activation analysis (NAA) and an X-ray microcomputed tomography (X-ray Micro-CT) scanner installed at the Malaysian Nuclear Agency. PMID:24907683

  7. Preliminary TRIGA fuel burn-up evaluation by means of Monte Carlo code and computation based on total energy released during reactor operation

    International Nuclear Information System (INIS)

    Aim of this work was to perform a rough preliminary evaluation of the burn-up of the fuel of TRIGA Mark II research reactor of the Applied Nuclear Energy Laboratory (LENA) of the Univ. of Pavia. In order to achieve this goal a computation of the neutron flux density in each fuel element was performed by means of Monte Carlo code MCNP (Version 4C). The results of the simulations were used to calculate the effective cross sections (fission and capture) inside fuel and, at the end, to evaluate the burn-up and the uranium consumption in each fuel element. The evaluation, showed a fair agreement with the computation for fuel burn-up based on the total energy released during reactor operation. (authors)

  8. Status report of Indonesian research reactor

    International Nuclear Information System (INIS)

    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)

  9. 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

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh)], E-mail: jahirulkhan@yahoo.com; Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2009-10-15

    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{sub 2}-1, BAPL-UO{sub 2}-2 and BAPL-UO{sub 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.

  10. Research reactor's role in Korea

    International Nuclear Information System (INIS)

    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)

    Pham Van Lam [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. Physical Characteristics of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    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

  13. Fuel burnup analysis for the Moroccan TRIGA research reactor

    International Nuclear Information System (INIS)

    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

  14. 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)

    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-UO2-1, BAPL-UO2-2 and BAPL-UO2-3 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 execute

  15. The DALAT nuclear research reactor operation and conversion status

    International Nuclear Information System (INIS)

    This paper presents operation and conversion status of the DALAT Nuclear Research Reactor (DNRR). The DNRR is a pool type research reactor which was reconstructed from the 250 kW TRIGA-MARK II reactor. The core is loaded with Soviet-designed standard type WWR-M2 fuel assemblies with 36% enrichment. The reconstructed reactor reached its initial criticality in November 1983 and attained its nominal power of 500 kW in February 1984. The DNRR is operated mainly in continuous runs of 100 hours, once every 4 weeks, for radioisotope production, neutron activation analyses, training and research purposes. The remaining time between two continuous runs, is devoted to maintenance activities and to short runs. Until now 4 fuel reloading were executed. The reactor control and instrumentation system was upgraded in 1994. And now the reactor control system is being replaced by new one, the replacement will be fulfilled in March 2007. The study on fuel conversion has been done on the basis of a new LEU of 19.75% with UO2-Al dispersion fuel meat instead of the current HEU of 36% with aluminium-uranium alloy. The results of the study show that operation time of mixed core by inserting 36 LEU fuel assemblies lasts much longer than by inserting 36 HEU fuel assemblies (14.5 instead of 10.5 years). Neutron flux performances at irradiation positions are not significantly changed. Now we are working for realizing fuel conversion of the DNRR

  16. The Management of TRIGA Spent Fuel at ENEA RC-1 Research Reactor

    International Nuclear Information System (INIS)

    TRIGA Mark II reactor of ENEA's Casaccia research Center (in Italy named RC-1) reached first criticality in 1960. Reactor core was realized with 61 standard TRIGA fuel elements, aluminium clad. In this condition, the reactor was operated until August 1965 at a steady state power level of 100 kW. In the summer of 1965, a programme was established to increase the reactor power to 1 MW. After significant plant modifications (in order both to adapt the reactor to the new operative circumstances, including safety regulations, and to extend reactor flexibility in the widest research areas), the new criticality was reached in July 1967. The 1 MW reactor operative configuration was initially obtained with 76 standard TRIGA fuel elements, but stainless steel clad. The RC-1 Reactor is still operational and during these years, many fuel elements were used. In this paper we describe the facility, the infrastructure available for spent fuel storage, and the operative experience accumulated during these years in the management of RC-1 Spent Nuclear Fuel (SNF). The activities and the incumbencies during SNF shipment that was carried out in 1999, in the frame of the USA Return of Foreign Research Reactors Spent Fuel Programme, are also described. (author)

  17. Reactor TRIGA at the J.Stefan institute in Ljubljana

    International Nuclear Information System (INIS)

    The TRIGA Mark II Reactor began its operation on May 1966. The power of the reactor is 250 kW. TRIGA utilizes solid fuel elements in which the zirconium hydride moderator is homogeneously mixed 20% or 70% enriched uranium. The inique featUre of these fuel - moderator elements is the prompt negative temperature coefficient of reactivity, which gives TRIGA its built-in safety. The reactor core consist of a lattice of cylindrical fuel-moderator elements and graphite (dummy) elements at the bottom of the 6 m high tank full of light water which is used for cooling and radiation protection. The reactor has the following experimental and irradiation facilities: 2 radial beam channels, 2 tangential beam channels, 2 thermal colomns, 40 position rotary specimen rack, pneumatic transfer tube and central thimble. The reactor operates about 2.500 hours per year and it is utilized for the production of isotopes, as a source of neutrons for various experiments and for the training of personnel for the nuclear power station in Krsko

  18. Optimum burnup of BAEC TRIGA research reactor

    International Nuclear Information System (INIS)

    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

  19. 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 tent

  20. 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

  1. Computational analysis of thermo-hydraulic behavior of TRIGA research reactor

    International Nuclear Information System (INIS)

    Highlights: ► Key thermal hydraulic parameters of the 3 MW TRIGA Mark-II research reactor were investigated under steady-state conditions. ► The thermal hydraulic codes NCTRIGA, PARET and COOLOD-N2 were employed for investigation. ► The NCTRIGA, PARET and COOLOD-N2 model calculations were benchmarked through the TRIGA experimental and operational data. ► The result obtained in this investigation can be used for upgrading the current core configuration of the TRIGA reactor. -- Abstract: Key thermal hydraulic parameters of the 3 MW TRIGA Mark-II research reactor operating under steady-state conditions were investigated using the thermal hydraulic codes NCTRIGA, PARET and COOLOD-N2. Results of the neutronic analysis performed by 3-D Monte Carlo code MCNP4C were used in NCTRIGA and coupled output of neutronic analysis carried out by using 3-D diffusion code CITATION and 3-D Monte Carlo code MCNP4B2 were used in the PARET to study the steady-state thermal hydraulic behavior of the reactor. To benchmark the NCTRIGA, PARET and COOLOD-N2 models, data were obtained from different measurements executed by thermocouples in the instrumented fuel elements (C1 and D2) and the hottest fuel element (C4) during the steady-state operation both under forced and natural convection mode and compared with the calculation found to be quite consistent. The mass flow rates needed for input to PARET and COOLOD-N2 were taken from final safety analysis report (FSAR) for a downward forced coolant flow equivalent to 3500 gpm. For natural convection cooling of reactor, mass flow rate was generated using NCTRIGA code. The testing of the NCTRIGA, PARET and COOLOD-N2 model calculations through benchmarking the available TRIGA experimental and operational data showed that NCTRIGA, PARET and COOLOD-N2 codes can successfully be used to analyze the thermal hydraulic behavior of the reactor for the steady-state operation under both natural and forced convection mode of coolant flow to predict

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

    International Nuclear Information System (INIS)

    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)

  3. Calculation of Kinetic Parameters of TRIGA Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Snoj, Luka; Kavcic, Andrej; Zerovnik, Gasper; Ravnik, Matjaz [' Jozef Stefan' Institute, Jamova 39, SI-1000 Ljubljana (Slovenia)

    2008-10-29

    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, {beta}{sub eff}, and mean neutron generation time, {lambda}. We calculated the {beta}{sub eff} and {lambda} 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, {beta}{sub 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 {beta}{sub 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 {sup 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 {mu}s for 30 wt. % uranium content fuelled core to 48 {mu}s for 8.5 wt. % uranium content LEU fuelled core. The results are especially important for pulse mode operation and analysis of the pulses. (authors)

  4. ENEA TRIGA RC-1 reactor spent fuel elements shipment to the USA

    International Nuclear Information System (INIS)

    TRIGA Mark II reactor of ENEA's Casaccia research Center (in Italy named RC-1) reached first criticality in 1960. In more than thirty years of operation, 1 MW reactor core has been modified many times for fuel elements burn-up optimization. Till now, because of achieved maximum burn-up, 146 fuel elements have been definitively removed from reactor core and transferred to the hot storages in reactor pool (5 racks around reactor vessel) and in the reactor room (pits). The activities planning, the organizing aspect study, the analysis and valuations both nuclear safety and radioprotection have been suitable for the TRIGA RC-1 fuel element shipment. Infact, no operative anomaly is appeared respect the approved procedures. Personnel engagement has been as expectations and the personnel absorbed gamma dose resulted negligible. Finally, the NAC disposable narrow time (only one week at the end of July) has not produced heavy organization problems but it has been a strong goad per all operative structures involved in the TRIGA RC-1 elements shipment

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  7. Preliminary study on new configuration with LEU fuel assemblies for the Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    The fuel conversion of the Dalat Nuclear Research Reactor (DNRR) is being realized. The DNRR is a pool type research reactor which was reconstructed from the 250 kW TRIGA- MARK II reactor. The reconstructed reactor attained its nominal power of 500 kW in February 1984. According to the results of design and safety analyses performed by the joint study between RERTR Program at Argonne National Laboratory (ANL) and Vietnam Atomic Energy Commission (VAEC) the mixed core of irradiated HEU and new LEU WWR-M2 fuel assemblies will be created soon. This paper presents the results of preliminary study on new configuration with only LEU fuel assemblies for the DNRR. The codes MCNP, REBUS and VARI3D are used to calculate neutron flux performance in irradiation positions and kinetics parameters. The idea of change of Beryllium rod reloading enables to get working configuration assured shutdown margin, thermal-hydraulic safety and increase in thermal neutron flux in neutron trap at the center of DNRR active core. (author)

  8. An Experimental Study of Natural Convection in The Hottest Channel of TRIGA 2000 k W Reactor

    International Nuclear Information System (INIS)

    With the increase of radioisotope demand, in 1995, National Nuclear Energy Agency of Indonesia made a decision to upgrade the power of the TRIGA Mark II reactor from 1 MW to 2 MW maximum power. The reactor reached its first criticality on May 13, 2000. To accomplish the safety evaluation of the reactor, a thermal hydraulic analysis was carried out by using thermal hydraulic computer code. This code calculates the natural convection flow through water coolant bounded by vertical cylindrical heat sources. In this paper, it will be reported the experimental study of natural convection in the hottest channel of TRIGA 2000 k W reactor. The purpose of the experimental study is to verify the theoretical analysis, especially the temperature distribution in the hottest coolant channel. In this experiment, a special probe for temperature detection has been designed and inserted to central thimble (CT). In the experiment, eight thermocouples were used to measure the bulk temperature of the water at different position in the cooling channel and simultaneous quantitative measurement of the temperature distribution were done by using a data acquisition cards system. The result obtained theoretically using the STAT code has been verified by this experimental study. (author)

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

    International Nuclear Information System (INIS)

    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)

  10. 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.

  11. 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 ...

  12. Reactor controller design using genetic algorithms with simulated annealing

    International Nuclear Information System (INIS)

    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.)

  13. Consideration factors on the spent fuel shipment for PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Malaysian Institute for Nuclear Technology Research (MINT) operates a 1MW TRIGA MARK II type research reactor since 1982. The PUSPATI TRIGA Reactor (RTP) reached its first criticality on 23 June 1982 and since then, it has been used for beam experiments, neutron activation analysis, radioisotopes production, education and training. RTP uses three types of fuel elements, namely, 8.5 wt%, 12wt% and 20 wt%. For all the three type the enrichment level of U-235 is 20%. Until the end of 2005, RTP has accumulated 21 906 hrs of operation time, and 13 166 MWhrs of burnup. Based on the neutronics calculation, all the fuel elements are expected to be fully utilized by the year 2015. At present, there is no decision for the government to take part in return of the spent nuclear fuel back to the country of origin, where it was enriched. This paper describes the current status of the fuel elements and the availability of local infrastructure, considering the eventual agreement of the government to join the US Foreign Research Reactor Spent Nuclear Fuel Acceptance Programme for the shipment of the spent nuclear fuels. The involvement of national regulatory body is also briefly described. (author)

  14. Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup

    Directory of Open Access Journals (Sweden)

    M.H. Altaf

    2014-12-01

    Full Text Available Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been carried out utilizing coupled point kinetics, neutronics and thermal hydraulics code EUREKA-2/RR. From the previous calculations of neutronics parameters including percentage burnup of individual fuel elements performed so far for 700 MWD burnt core of TRIGA reactor showed that the fuel rod predicted as hottest at the beginning of cycle (fresh core was found to remain as the hottest until 200 MWD of burn, but, with the progress of core burn, the hottest rod was found to be shifted and another rod in the core became the hottest. The present study intends to evaluate the thermal hydraulic parameters of these hottest fuel rods at different cycles of burnup, from beginning to 700 MWD core burnt considering reactor operates under steady state condition. Peak fuel centerline temperature, maximum cladding and coolant temperatures of the hottest channels were calculated. It revealed that maximum temperature reported for fuel clad and fuel centerline found to lie below their melting points which indicate that there is no chance of burnout on the fuel cladding surface and no blister in the fuel meat throughout the considered cycles of core burnt.

  15. Thermal hydraulic analysis of 3 MW TRIGA research reactor of bangladesh considering different cycles of burnup

    International Nuclear Information System (INIS)

    Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been carried out utilizing coupled point kinetics, neutronics and thermal hydraulics code EUREKA-2/RR. From the previous calculations of neutronics parameters including percentage burnup of individual fuel elements performed so far for 700 MWD burnt core of TRIGA reactor showed that the fuel rod predicted as hottest at the beginning of cycle (fresh core) was found to remain as the hottest until 200 MWD of burn, but, with the progress of core burn, the hottest rod was found to be shifted and another rod in the core became the hottest. The present study intends to evaluate the thermal hydraulic parameters of these hottest fuel rods at different cycles of burnup, from beginning to 700 MWD core burnt considering reactor operates under steady state condition. Peak fuel centerline temperature, maximum cladding and coolant temperatures of the hottest channels were calculated. It revealed that maximum temperature reported for fuel clad and fuel centerline found to lie below their melting points which indicate that there is no chance of burnout on the fuel cladding surface and no blister in the fuel meat throughout the considered cycles of core burnt. (author)

  16. Anarchism and Austrian economics

    OpenAIRE

    Boettke, Peter

    2011-01-01

    In the 2011 Franz Cuhel Memorial Lecture, I argue that the study of endogenous rule formation in economic life (what I term the positive political economy of anarchism) should be studied in-depth and that the economic analysis of the Austrian school of economics provides many of the key analytical insights necessary for such study.

  17. 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)

    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-UO2-1, BAPL-UO2-2 and BAPL-UO2-3 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 of

  18. Maintenance of nuclear knowledge in an antinuclear environment

    International Nuclear Information System (INIS)

    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.

  19. Gas Evolution Measurements on Reactor Irradiated Advanced Fusion Magnet Insulation Systems

    Science.gov (United States)

    Humer, K.; Seidl, E.; Weber, H. W.; Fabian, P. E.; Feucht, S. W.; Munshi, N. A.

    2006-03-01

    Glass-fiber reinforced plastics (GFRPs) are used as insulation materials for the superconducting magnet coils of the International Thermonuclear Experimental Reactor (ITER). The radiation environment present at the magnet location will lead to gas production, swelling and weight loss of the laminate, which may result in a pressure rise combined with undefined stresses on the magnet coil casing. Consequently, these effects are important parameters for the engineering and design criteria of superconducting magnet coil structures. In this study, newly developed epoxy and cyanate-ester (CE) based S2-glass fiber reinforced insulation systems were irradiated at ambient temperature in the TRIGA-Mark II reactor (Vienna) to a fast neutron fluence of 1 and 5×1021 m-2 (E>0.1 MeV) prior to measurements of gas evolution, swelling and weight loss. The CE based laminates show increased radiation resistance, i.e. less gas evolution. The highest radiation hardness up to the highest dose was observed in a pure CE system. In addition, the effects of swelling and weight loss are either negligible or less pronounced for all systems. The results prove that the newly developed CE based composites are serious candidate insulation systems for ITER.

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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

  2. Digitized neutron imaging with high spatial resolution at a low power research reactor: I. Analysis of detector performance

    Science.gov (United States)

    Zawisky, M.; Hameed, F.; Dyrnjaja, E.; Springer, J.

    2008-03-01

    Imaging techniques provide an indispensable tool for investigation of materials. Neutrons, due to their specific properties, offer a unique probe for many aspects of condensed matter. Neutron imaging techniques present a challenging experimental task, especially at a low power research reactor. The Atomic Institute with a 250 kW TRIGA MARK II reactor looks back at a long tradition in neutron imaging. Here we report on the advantages gained in a recent upgrade of the imaging instrument including the acquisition of a thin-plate scintillation detector, a single counting micro-channel plate detector, and an imaging plate detector in combination with a high resolution scanner. We analyze the strengths and limitations of each detector in the field of neutron radiography and tomography, and demonstrate that high resolution digitized imaging down to the 50 μm scale can be accomplished with weak beam intensities of 1.3×10 5 n/cm 2 s, if appropriate measures are taken for the inevitable extension of measurement times. In a separate paper we will present some promising first results from the fields of engineering and geology.

  3. Operational Experience On Ageing Management At The TRIGA Research Reactor Of LENA (Laboratory of Applied Nuclear Energy) - Univ. of Pavia (Italy) -

    Energy Technology Data Exchange (ETDEWEB)

    Magrotti, G.; Alloni, D.; Bellani, G.; Giordand, M.; Lana, F.; Manera, S.; Marchetti, F.; Prata, M.; Salvini, A.; Vinciguerra, G. [Univ. of Pavia, Pavia (Italy)

    2013-07-01

    The Laboratory of Applied Nuclear Energy ('LENA') of the University of Pavia operates, since 1965, a 250 kW TRIGA Mark II nuclear research reactor providing training and services to private enterprises and public institutions as well as being involved in several research projects carried out by the University and other research groups. Being an almost fifty years old facility, ageing, together with its potential premature failures, is a key point in the reactor safety. For these reason, in order to mitigate ageing effects, the facility has had to deal with several issues due to the time-dependent degradation of its structures, systems and components (SSCs). After an accurate assessment of SSCs conditions and the identification of ageing mechanisms, during the past years, several activities were successfully carried out. The paper will provide an overview of the above-mentioned topics and the forthcoming plans, together with lessons learned on ageing management in a small-sized reactor facility.

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

    International Nuclear Information System (INIS)

    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

  5. Status of spent fuel in the 3MW BAEC MK-II research reactor facility of Bangladesh

    International Nuclear Information System (INIS)

    Bangladesh has been operating a 3 MW TRIGA MARK II research reactor since 1986. The reactor is installed in the campus of the Atomic Energy Research Establishment (AERE) at Savar, which is located about 40 km northwest of Dhaka. It is one of the main nuclear research facilities in the country. The reactor uses TRIGA LEU fuel with uranium content of 20% by weight. The enrichment level of the fuel is 19.7%. So far the reactor has been operated for 5624 hours with a total cumulative burnup (BU) of 10 690 MWh (445 MWd). The main areas of use are: training of man-power for research reactor operation and applications, radioisotope (RI) production, neutron activation analysis (NAA), neutron radiography (NR) and neutron scattering. Radioisotopes produced to date are: I-131, Sc-46 and Tc-99m. Bangladesh is a peace loving country with a strong commitment towards nuclear nonproliferation. Accordingly, it has signed several multilateral and bilateral agreements, protocols, treaties, etc. prevailing in the International Nuclear Non-proliferation regime. Bangladesh has also signed a Nuclear Cooperation Agreement with the USA on 17 September 1981, which facilitated export of nuclear technology from the USA to Bangladesh. The research reactor was procured under the provisions of this agreement. In 2003, the tenure of the Agreement was extended up to 2012. At present, there does not exist any spent fuel element in the reactor facility. However, with the recently undertaken RI production enhancement program, it is expected that the reactor will start generating spent fuels from the year 2012. It is to be mentioned that Bangladesh is aware of the US DOE's 'Take Back Program' in connection with the research reactor spent fuel of US origin, and is very much interested to take part in this program. The paper presents the current status of handling and storage facilities available for spent fuel and strategy for the safe management spent fuel to be generated from the research reactor in

  6. Research reactors as sources of atmospheric radioxenon

    International Nuclear Information System (INIS)

    Radioxenon emissions of the TRIGA Mark II research reactor in Vienna were investigated with respect to a possible impact on the verification of the Comprehensive Nuclear Test-Ban-Treaty. Using the Swedish Automatic Unit for Noble Gas Acquisition (SAUNA II), five radioxenon isotopes 125Xe, 131mXe, 133mXe, 133Xe and 135Xe were detected, of which 125Xe is solely produced by neutron capture in stable atmospheric 124Xe and hence acts as an indicator for neutron activation processes. The other nuclides are produced in both fission and neutron capture reactions. The detected activity concentrations ranged from 0.0010 to 190 Bq/m3. The source of the radioxenon is not yet fully clarified, but it could be micro-cracks in the fuel cladding, fission of 235U contaminations on the outside of the fuel elements or neutron activation of atmospheric Xe. Neutron deficient 125Xe with its highly complex decay scheme was seen for the first time in a SAUNA system. In many experiments the activity ratios of the radioxenon nuclides carry the signature of nuclear explosions, if 131mXe is omitted. Only if 131mXe is included into the calculations of the isotopic activity ratios, the majority of the measurements revealed a 'civil' signature (typical for a NPP). A significant contribution of the TRIGA Vienna to the global or European radioxenon inventory can be excluded. Due to the very low activities, the emissions are far below any concern for human health. (author)

  7. Nuclear reactor pulse tracing using a CdZnTe electro-optic radiation detector

    Science.gov (United States)

    Nelson, Kyle A.; Geuther, Jeffrey A.; Neihart, James L.; Riedel, Todd A.; Rojeski, Ronald A.; Ugorowski, Philip B.; McGregor, Douglas S.

    2012-07-01

    CdZnTe has previously been shown to operate as an electro-optic radiation detector by utilizing the Pockels effect to measure steady-state nuclear reactor power levels. In the present work, the detector response to reactor power excursion experiments was investigated. Peak power levels during an excursion were predicted to be between 965 MW and 1009 MW using the Fuchs-Nordheim and Fuchs-Hansen models and confirmed with experimental data from the Kansas State University TRIGA Mark II nuclear reactor. The experimental arrangement of the Pockels cell detector includes collimated laser light passing through a transparent birefringent crystal, located between crossed polarizers, and focused upon a photodiode. The birefringent crystal, CdZnTe in this case, is placed in a neutron beam emanating from a nuclear reactor beam port. After obtaining the voltage-dependent Pockels characteristic response curve with a photodiode, neutron measurements were conducted from reactor pulses with the Pockels cell set at the 1/4 and 3/4 wave bias voltages. The detector responses to nuclear reactor pulses were recorded in real-time using data logging electronics, each showing a sharp increase in photodiode current for the 1/4 wave bias, and a sharp decrease in photodiode current for the 3/4 wave bias. The polarizers were readjusted to equal angles in which the maximum light transmission occurred at 0 V bias, thereby, inverting the detector response to reactor pulses. A high sample rate oscilloscope was also used to more accurately measure the FWHM of the pulse from the electro-optic detector, 64 ms, and is compared to the experimentally obtained FWHM of 16.0 ms obtained with the 10B-lined counter.

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

    International Nuclear Information System (INIS)

    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

  9. Applications of a gas-jet transport system at the research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Research reactors of the TRIGA-type are light water cooled reactors using uranium-zirconium-hydride (UZrH) alloy fuel-moderator elements with 20% enrichment in 235U. The TRIGA Mark II-reactor at the Johannes Gutenberg-Universitat Mainz became first critical in 1965 and since then the reactor was operated failure-free during about 200 days per year. In the steady state mode the TRIGA-Mainz can be operated at power levels ranging from about 100 mWth up to 100 kWth, depending on the requirements of the different experiments. Pulse-mode operation is also possible, corresponding to a maximum pulse peak power of up to 250 MWth, a neutron flux in the order of 1015 cm-2 per pulse and a pulse width (FWHM) of about 30 ms. For irradiation experiments the TRIGA Mainz is equipped with a central experimental tube, a rotary specimen rack and three pneumatic transfer systems. In addition, four horizontal beam ports penetrate the biological shield and extend inside the pool towards the reflector surrounding the reactor core. The TRlGA-SPEC experiment currently being installed at beam port B of the TRlGA Mainz research reactor consists of two branches: (i) the Penning-trap mass spectrometer TRlGA-TRAP and (ii) the collinear laser spectroscopy setup TRlGA-LASER. At TRlGA-SPEC a gas-jet system is connected to a high-temperature ion source and a subsequent mass analyzing magnet. The nuclides of interest are then guided either to TRlGA-TRAP or to TRlGA-LASER. Currently, TRlGA-SPEC is the only facility world-wide that is installed at a nuclear research reactor

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

    Science.gov (United States)

    Protti, N; Ballarini, F; Bortolussi, S; Bruschi, P; Stella, S; Geninatti, S; Alberti, D; Aime, S; Altieri, S

    2011-12-01

    To test the efficacy of a new (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% (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 5×10(12) cm(-2). PMID:21459587

  11. Adaptation of triple axis neutron spectrometer for SANS measurements using alumina samples at TRIGA reactor of Bangladesh

    Science.gov (United States)

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

    2005-09-01

    Double crystal method known as Bonse and Hart's technique has been employed to develop small angle neutron scattering (SANS) facility on a triple axis neutron spectrometer at TRIGA Mark II (3 MW) research reactor of Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh. Two Si(1 1 1) crystals with very small mosaic spread ∼1 min have been used for this purpose. At an incident neutron wavelength of 1.24 Å, this device is useful for SANS in the Q range between 1.6×10 -3 and 10 -1 Å -1. This Q range allows investigating particle sizes and interparticle correlations on a length scale of ∼200 Å. Results of SANS experiments on three alumina (Al 2O 3) samples as performed using above setup are presented. It is seen that Al 2O 3 particles, indeed, scatter neutrons in regions of small angles. It is also seen that scattering is different for different samples showing that it changes with a change in particle size.

  12. Austrian natural scientists in exile

    International Nuclear Information System (INIS)

    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)

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

    Science.gov (United States)

    Koerner, S.; Schillinger, B.; Vontobel, P.; Rauch, H.

    2001-09-01

    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 this beam position is 1.3×10 5 neutrons/cm 2 s and the beam diameter is 8 cm. For a 3D tomographic reconstruction of the sample interior, transmission images of the object taken from different view angles are required. Therefore, a rotary table driven by a step motor connected to a computerized motion control system has been installed at the sample position. In parallel a suitable electronic imaging device based on a neutron sensitive scintillator screen and a CCD-camera has been designed. It can be controlled by a computer in order to synchronize the software of the detector and of the rotary table with the aim of an automation of measurements. Reasonable exposure times can get as low as 20 s per image. This means that a complete tomography of a sample can be performed within one working day. Calculation of the 3D voxel array is made by using the filtered backprojection algorithm.

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

    International Nuclear Information System (INIS)

    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 this beam position is 1.3x105 neutrons/cm2 s and the beam diameter is 8 cm. For a 3D tomographic reconstruction of the sample interior, transmission images of the object taken from different view angles are required. Therefore, a rotary table driven by a step motor connected to a computerized motion control system has been installed at the sample position. In parallel a suitable electronic imaging device based on a neutron sensitive scintillator screen and a CCD-camera has been designed. It can be controlled by a computer in order to synchronize the software of the detector and of the rotary table with the aim of an automation of measurements. Reasonable exposure times can get as low as 20 s per image. This means that a complete tomography of a sample can be performed within one working day. Calculation of the 3D voxel array is made by using the filtered backprojection algorithm

  15. 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.

  16. 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.

  17. Measurement of the thermal neutron capture cross section and the resonance integral of radioactive Hf182

    Science.gov (United States)

    Vockenhuber, C.; Bichler, M.; Wallner, A.; Kutschera, W.; Dillmann, I.; Käppeler, F.

    2008-04-01

    The neutron capture cross sections of the radioactive isotope Hf182 (t1/2=8.9×106 yr) in the thermal and epithermal energy regions have been measured by activation at the TRIGA Mark-II reactor of the Atomic Institute of the Austrian Universities in Vienna, Austria, and subsequent γ-ray spectroscopy of Hf183. High values for the thermal (kT=25 meV) cross section σ0=133±10 b and for the resonance integral I0=5850±660 b were found. Additionally, the absolute intensities of the main γ-ray transitions in the decay of Hf182 have been considerably improved.

  18. Utilisation of the Research Reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    The TRIGA Mark II reactor of the University of Mainz can be operated in the steady state mode with thermal powers up to a maximum of 100 kW and in the pulse mode with a maximum peak power of 250 MW. So far, more than 17 000 pulses have been performed. For irradiations the TRIGA Mainz has a central experimental tube, three pneumatic transfer systems and a rotary specimen rack. In addition, the TRIGA Mainz includes four horizontal beam ports and a graphite thermal column which provides a source of well-thermalised neutrons. A broad spectrum of commercial applications, scientific research and training can be executed. For education and training various courses in nuclear and radiochemistry, radiation protection, reactor operation and physics are held for scientists, advanced students, teachers, engineers and technicians. Isotope production and Neutron Activation Analysis (NAA) are applied in in-core positions for different applications. NAA in Mainz is focused to determine trace elements in different materials such as in archaeometry, forensics, biology and technical materials including semiconductors for photovoltaics. The beam ports and the thermal column are used for commercial as well as for special basic and applied research in medicine, biology, chemistry and physics. Experiments are in preparation to determine the fundamental neutron properties with very high precision using ultra cold neutrons (UCN) produced at the tangential beam port. A second source is under development at the radial piercing beam port. Another experiment under development is the determination of ground-state properties of radioactive nuclei with very high precision using a penning trap and collinear laser spectroscopy. For many years fast chemical separation procedures combining a gas-jet transport system installed in one beam tube with either continuous or discontinuous chemical separation are carried out. In addition the thermal column of the reactor is also used for medical and

  19. 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.

  20. Identification of a leaking TRIGA fuel element at the reactor facility of Pavia

    International Nuclear Information System (INIS)

    On January 28th 2004, during a periodical activity of characterization of the ionic-exchange resins of the demineralizer of the primary cooling circuit of the TRIGA Mark II reactor of the University of Pavia a small but detectable amount of 137Cs contamination was measured. Since the reactor has been running for several hundreds of hours at full power without showing any anomaly in the radiometric and thermo-hydraulic parameters, the reactor was brought at the nominal power of 250 kW for one hour and a sample of water was collected from the reactor tank and analyzed in a low background gamma-ray detector. As a result a small amount of fission products were detected in the reactor pool water (few Bq/g) suggesting the existence of a possible clad defect in one ore more fuel elements. As a consequence of this situation a campaign of gamma-ray spectrometry was implemented in order to evaluate the importance of the release. Analyzes using a HGe detector (1.72 keV FWHM - 31.3 % efficiency - 58.5 Photo Peak/Compton) were performed and the most significant results are presented as well as the identification of the leaking fuel element. The fission products leakage was due to a micro-fissure of a fuel element that released only noble gas when it was heated up to a temperature around 90oC , i.e. at the reactor power of about 100 kW. The oldest SST clad instrumented fuel element in the core was identified as the origin of the release. It was removed from its position and stored in a rack of the reactor pool under 4 m of water shield. The reactor came back in regular operation on March 22nd 2004 and no other fission products leakages were detected. After this situation the reactor pool water is sampled and measured with a low-background gamma-ray detector every month before the reactor start-up and after one hour of operation of the reactor at full nominal power. (nevyjel)

  1. Austrian Economics, Neoclassicism, and the Market Test

    OpenAIRE

    Leland B. Yeager

    1997-01-01

    Professor Sherwin Rosen correctly suggests that the Austrian and neoclassical schools can be complementary, each accepting much from the other. However his recognition of Austrian strengths needs to be amplified and his criticisms need softening. His appeal to the market test risks encouraging anti-intellectual attitudes and practices

  2. 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.

  3. Ageing Management and Preventice Measures for Reactor Pool Liners, Beam Tubes and Spent Fuel Storage Tank at the Dalat Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dien, Nguyen Nhi; Dien, Nguyen Minh; Su, Trang Cao [Nuclear Research Institute, Henoi (Viet Nam)

    2013-07-01

    The 500-kw Dalat Nuclear Research Reactor (DNRR) was reconstructed from the original 250-kW TRIGA Mark II as named of VN-001. In the framework of the reconstruction project during the 1982-1984 period, some structures of the TRIGA reactor constructed in the early sixties, such as the aluminum tank, graphite reflector, thermal column, four horizontal beam tubes, etc. have been remained. It means, such components are more than 50 years old and are facing with ageing issues. The structural materials of the 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. The reactor core has been loaded with HEU VVR-M2 fuel assemblies of 36% enrichment alloy CAV-1. The reactor core has been loaded with HEU VVR-M2 fuel assemblies of U-Al alloy 36% and of UO{sub 2} 19.75% enrichment used aluminum as fuel cladding. For ageing management and preventive measures of corrosion, an underwater high-resolution video camera system had been designed for visual inspections. A home-made cleaning system was also designed for cleaning the pool and other components. Water chemistry of the reactor pool and spent fuel storage was monitored regularly. In September-November 2011, all four horizontal channels were cleaned inside and visual inspection was done using special camera system. It was the first time from 1963 such activity could be done. Based on results obtained we could convince that inside all horizontal channels are in good condition and leakage could not be occurred. All 106 HEU spent fuel assemblies stored in the spent fuel pool in good condition. The visual inspection was done using under water camera too. The results obtained show that the surface of all HEU SFA is good and leakage was not occurred. The

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

    Energy Technology Data Exchange (ETDEWEB)

    Huda, M.Q. [Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh)]. E-mail: quamrul@dhaka.net

    2006-08-15

    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 {sup nat}Zr, {sup nat}Mo, {sup nat}Cr, {sup nat}Fe, {sup nat}Ni, {sup nat}Si, and {sup nat}Mg) at 300 K evaluations were used. Full S({alpha}, {beta}) 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 {approx}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: {delta} {sup 28}, {delta} {sup 25}, {rho} {sup 25}, and C {sup *} 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.

  5. Technical report on treatment of radioactive slurry liquid waste

    Energy Technology Data Exchange (ETDEWEB)

    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)

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

    International Nuclear Information System (INIS)

    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 oC which is substantially lower than ∼627 oC 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Hung, T.C., E-mail: tchung@ntut.edu.t [Department of Mechanical Engineering, National Taipei University of Technology, 1, Sec. 3, Chung-hsiao E. Rd., Taipei 10608, Taiwan (China); Dhir, V.K. [Department of Mechanical and Aerospace Engineering, UCLA, CA (United States); Chang, J.C. [Graduate Institute of Mechanical and Electrical Engineering, National Taipei University of Technology, Taiwan (China); Wang, S.K. [Department of Mechanical and Automation Engineering, I-Shou University, Taiwan (China)

    2011-01-15

    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 {approx}551 {sup o}C which is substantially lower than {approx}627 {sup 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

  8. Schumpeter and Mises as 'Austrian Economists'

    OpenAIRE

    Vanberg, Viktor J.

    2008-01-01

    "Whether and, if so, in what sense Joseph A. Schumpeter (1883-1950) and Ludwig von Mises (1881-1973) may both be classified as ‘Austrian economists’ is a controversial issue. In terms of their biographical background they were, of course, Austrian nationals, and as students of Böhm-Bawerk and von Wieser both qualify in a formal sense as third-generation members of the Austrian School. Yet, whether they so qualify in a substantive sense as well is much more questionable. Apparen...

  9. Síndrome de Austrian

    Directory of Open Access Journals (Sweden)

    Márcio Estevão Midon

    2011-09-01

    Full Text Available Neste relato, é descrito o caso de um paciente masculino, 64 anos, sem história de etilismo, que se apresentou com a Tríade de Osler, que consiste no desenvolvimento de endocardite, pneumonia e meningite, por um mesmo agente. A síndrome é denominada síndrome de Austrian, quando a infecção for por Streptococcus pneumoniae. Serão discutidas as manifestações clínicas, fisiopatológicas e a terapêutica mais adequada para esse quadro. Tendo em vista a raridade do caso e a elevada morbimortalidade, serão enfatizadas a importância do diagnóstico precoce e o tratamento adequado, visando reduzir as complicações inerentes a essa doença.

  10. Austrian emission inventory for dust

    International Nuclear Information System (INIS)

    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 (PM10, PM2.5), 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 PM10 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 PM10 and PM2.5 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-fugitive emissions

  11. The Consumer in Austrian Economics and the Austrian Perspective on Consumer Policy

    OpenAIRE

    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 Austrian economist believes that everyone -the consumer included- acts entrepreneurially, in his elucidation of the market process he gives the role of entrepreneur to the producer only.In Part I, "...

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

    International Nuclear Information System (INIS)

    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

  13. Management of nuclear knowledge on an international scale using a small university research reactor

    International Nuclear Information System (INIS)

    Full text: The Atominstitut Vienna operates a 250 kW TRIGA Mark-II reactor since March 1962 used for nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection, dosimetry, low temperature physics and fusion research. During the past 20 years about 640 students graduated with a diploma - or PhD degree from the Atominstitut attached to the University of Technology Vienna. To perform nuclear relevant academic studies the Atominstitut offers about 100 highly specialised theoretical lectures and about 10 practical courses where students have to perform experiments in small groups of four on subjects mentioned above. Although the TRIGA reactor is a rather low power research reactor it is very easy and cheap to operate and an excellent tool to transfer knowledge and experience to the younger generation. This reactor is therefore not only used by other European universities such as University of Manchester or Bratislava Technical University but also by nuclear institutions such as the GRS/Germany, NPP Bohunice and NPP Mochovce for nuclear training. On an international scale the Atominstitut co-operates closely with the nearby located IAEA in international 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. In the past 20 years more than 120 IAEA fellows from all over the world have been trained at the Atominstitut. The fellows spend between one to twelve month at the Atominstitut and are integrated in the respective work program. Experience showed that out of this fellowship a long-term relation between the institutes continues. The paper focuses especially on the transfer of knowledge between

  14. 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 A

  15. President Hans Ager of Austrian Federal Council Visits China

    Institute of Scientific and Technical Information of China (English)

    2004-01-01

    <正>An Austrian goodwill delegation led by Hans . Ager, president of the Austrian Federal Coun-cil and board member of the Austrian Association for Promotion of Friendship and Cultural Relations with China (AAPFCRC), paid a friendly visit to China in November, 2003 at the invitation of the CPAFFC. On the delegation were Dietmar Bachmann, president of the Industrial Federation of

  16. Austrian Philosophy. The Legacy of Franz Brentano

    OpenAIRE

    Smith, Barry

    1994-01-01

    This book is a survey of the most important developments in Austrian philosophy in its classical period from the 1870s to the Anschluss in 1938. But I hope that the volume will be seen also as a contribution to philosophy in its own right as an attempt to philosophize in the spirit of those, above all Roderick Chisholm, Rudolf Haller, Kevin Mulligan and Peter Simons, who have done so much to demonstrate the continued fertility of the ideas and methods of the Austrian philosophers in our own d...

  17. 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....

  18. A comparison of integral transport and diffusion theory methods in whole-core Triga calculations

    Energy Technology Data Exchange (ETDEWEB)

    Ozgener, H. A.; Ozgener, B.; Buke, T. (Istanbul Technical University (Turkey). Institute of Nuclear Energy)

    1999-12-15

    Whole-core calculations are carried out for ITU-TRIGA Mark-II Reactor, using both integral transport theory and diffusion theory. By comparing effective multiplication factors, flux distributions and average fuel-rod reactivity worths, the merit of diffusion theory, which have been traditionally used in whole-core calculations, is assessed. (orig.)

  19. Gamma spectrometric assessment of nuclear fuel

    Science.gov (United States)

    Krištof, Edvard; Pregl, Gvido

    1990-12-01

    A description is given of a gamma spectrometric technique which has been developed with the aim of determining the amount of a certain radioactive fission product taking into consideration local variations of the linear attenuation coefficient of gamma rays. Also, an experiment using a fuel element of the TRIGA Mark II reactor in Ljubljana is presented.

  20. The Response of Alanine Dosimeters in Thermal Neutron Fields

    DEFF Research Database (Denmark)

    Schmitz, T.; Bassler, Niels; Sharpe, P.;

    Purpose: Boron Neutron Capture Therapy (BNCT) is a special kind of particle therapy, based on the neutron induced fission of the boron isotope 10B [1]. We have performed dosimetry experiments on the mixed neutron and gamma fields at the TRIGA Mark II research reactor in Mainz. Commonly, dosimetry...

  1. Austrian Airlines:Safety is our Business!

    Institute of Scientific and Technical Information of China (English)

    Guo Yan

    2006-01-01

    @@ Mighty Capacity Managed "Although Austrian Airlines is a middle-sized company, it has a mighty capacity of over 10 million customers every year. Because it has an extensive European service network." G(o)tz stressed to China's Foreign Trade.

  2. Irradiation of Fusion Reactor Materials and Bio-Dosimeters in JSI TRIGA Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Snoj, Luka; Ravnik, Matjaz; Lengar, Igor; Rogan, Petra; Novak, Sasa; Sentjurc, Marjeta; Jeraj, Robert [' Jozef Stefan' Institute, Jamova 39, SI-1000 Ljubljana (Slovenia)

    2008-10-29

    The TRIGA research reactor at Jozef Stefan Institute (JSI) is used for irradiation of various samples. Recently two projects have been initiated; the development and improvement of future fusion reactor materials and the development of bio-dosimeters. They both demand a large number of irradiations under different conditions (neutron spectra and flux) and subsequent gamma spectral analyses of the samples. In order to characterize the neutron spectra and fluxes in different irradiation channels that are of vital importance for the quality of irradiation, a detailed computational model of the TRIGA Mark-II reactor with the MCNP Monte Carlo particle transport code was developed, experimentally validated and verified. The projects and the main results are presented in the paper. Irradiation of Eurofer and SiC samples in our reactor is feasible and gives reliable results for material development and optimization in fusion reactors provided that the irradiation is supported with detailed spectrum calculations to take into account also the contribution of fast neutron reactions. Detailed knowledge of gamma and neutron spectrum is vital also in experimental development and calibration of bio-dosimeters. It can be concluded that irradiation of non-standard materials requires support of detailed calculations of spectrum in irradiation facilities not only to improve the accuracy but even to make the irradiation methods feasible. Main isotopes contributing to the long-term activation of Eurofer have relatively short life-times (100 days to several years). This composition of Eurofer is suitable from the radioactive waste disposal point of view. However one should be aware that dose rates inside and around the Eurofer structures will be significant even several months of cooling. The highest contribution to the total activity (80%) in this time interval comes from {sup 182}Ta. It may be speculated that further optimization of Eurofer with respect to the activation could be

  3. 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...

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

    International Nuclear Information System (INIS)

    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 βeff 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

  5. Foreign Identities in the Austrian E-Government

    OpenAIRE

    Ivkovic, Mario; Stranacher, Klaus

    2010-01-01

    With the revision of the Austrian E-Government Act [8] in the year 2008, the legal basis for a full integration of foreign persons in the Austrian e-government, has been created. Additionally, the E-Government Equivalence Decree [1] has been published in June 2010. This decree clarifies which foreign electronic identities are considered to be equivalent to Austrian identities and can be electronically registered within the Austrian identity register. Based on this legal framework a concept ha...

  6. 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.

  7. Studies on the overall safety aspects during irradiation of TeO2 in the central thimble of the TRIGA research reactor

    International Nuclear Information System (INIS)

    The purpose of this study is to provide a detailed safety analysis of overall system and components in terms of their ability to provide optimum output from the irradiation of TeO2 in the central thimble of the 3 MW TRIGA MARK II research reactor at Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh. It identifies safety issues relevant to 131I radioisotope production and ensures that safety analysis and design are consistent. It evaluates threats developed within the facility during the irradiation process and ultimately ensures establishment of in-core safety limits and conditions at all stages of 131I production. In-core irradiation safety not only ensures the safe operation of the reactor but also strengthens the production of radioisotopes (RI). This study attempts to review and modify all safety related events and aspects relating to RI production. The three-dimensional continuous energy Monte Carlo code MCNP is used to develop a versatile and accurate full-core model of the TRIGA core. The cross-section library and fission product inventory are generated by using NJOY and ORIGEN computer codes. The methodology to evaluate heat generation and other relevant parameters necessary to provide enough information for thermal hydraulic analysis are discussed. The neutron flux distribution inside the dry and water filled central thimble is determined in order to locate the highest neutron flux trapping position. The thermal hydraulic and safety analysis are performed by elaborate numerical analysis as well as by using GENGTC computer code. A mock-up facility has also been developed to supplement and verify the theoretically predicted results. The total energy generated during irradiation of 50 gm TeO2 sample in dry condition is found to be 113.84 w of which 75% energy is due to neutron heating and rest of the amount is from gamma heating. Around 11.28 w of heat energy is also generated in the quartz vial. When the total generated-heat transfer is

  8. Studies on the overall safety aspects during irradiation of TeO{sub 2} in the central thimble of the TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Huda, M.Q. [Energy Institute, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka (Bangladesh)], E-mail: quamrul@dhaka.net; Islam, M.S. [Reactor Operation and Maintenance Unit, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka (Bangladesh); Rahman, M.M. [Energy Institute, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka (Bangladesh); Haque, A.; Uddin, M. [Reactor Operation and Maintenance Unit, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka (Bangladesh)

    2009-03-15

    The purpose of this study is to provide a detailed safety analysis of overall system and components in terms of their ability to provide optimum output from the irradiation of TeO{sub 2} in the central thimble of the 3 MW TRIGA MARK II research reactor at Atomic Energy Research Establishment (AERE), Savar, Dhaka, Bangladesh. It identifies safety issues relevant to {sup 131}I radioisotope production and ensures that safety analysis and design are consistent. It evaluates threats developed within the facility during the irradiation process and ultimately ensures establishment of in-core safety limits and conditions at all stages of {sup 131}I production. In-core irradiation safety not only ensures the safe operation of the reactor but also strengthens the production of radioisotopes (RI). This study attempts to review and modify all safety related events and aspects relating to RI production. The three-dimensional continuous energy Monte Carlo code MCNP is used to develop a versatile and accurate full-core model of the TRIGA core. The cross-section library and fission product inventory are generated by using NJOY and ORIGEN computer codes. The methodology to evaluate heat generation and other relevant parameters necessary to provide enough information for thermal hydraulic analysis are discussed. The neutron flux distribution inside the dry and water filled central thimble is determined in order to locate the highest neutron flux trapping position. The thermal hydraulic and safety analysis are performed by elaborate numerical analysis as well as by using GENGTC computer code. A mock-up facility has also been developed to supplement and verify the theoretically predicted results. The total energy generated during irradiation of 50 gm TeO{sub 2} sample in dry condition is found to be 113.84 w of which 75% energy is due to neutron heating and rest of the amount is from gamma heating. Around 11.28 w of heat energy is also generated in the quartz vial. When the total

  9. GEANT4 used for neutron beam design of a neutron imaging facility at TRIGA reactor in Morocco

    Science.gov (United States)

    Ouardi, A.; Machmach, A.; Alami, R.; Bensitel, A.; Hommada, A.

    2011-09-01

    Neutron imaging has a broad scope of applications and has played a pivotal role in visualizing and quantifying hydrogenous masses in metallic matrices. The field continues to expand into new applications with the installation of new neutron imaging facilities. In this scope, a neutron imaging facility for computed tomography and real-time neutron radiography is currently being developed around 2.0MW TRIGA MARK-II reactor at Maamora Nuclear Research Center in Morocco (Reuscher et al., 1990 [1]; de Menezes et al., 2003 [2]; Deinert et al., 2005 [3]). The neutron imaging facility consists of neutron collimator, real-time neutron imaging system and imaging process systems. In order to reduce the gamma-ray content in the neutron beam, the tangential channel was selected. For power of 250 kW, the corresponding thermal neutron flux measured at the inlet of the tangential channel is around 3×10 11 ncm 2/s. This facility will be based on a conical neutron collimator with two circular diaphragms with diameters of 4 and 2 cm corresponding to L/D-ratio of 165 and 325, respectively. These diaphragms' sizes allow reaching a compromise between good flux and efficient L/D-ratio. Convergent-divergent collimator geometry has been adopted. The beam line consists of a gamma filter, fast neutrons filter, neutron moderator, neutron and gamma shutters, biological shielding around the collimator and several stages of neutron collimator. Monte Carlo calculations by a fully 3D numerical code GEANT4 were used to design the neutron beam line ( http://www.info.cern.ch/asd/geant4/geant4.html[4]). To enhance the neutron thermal beam in terms of quality, several materials, mainly bismuth (Bi) and sapphire (Al 2O 3) were examined as gamma and neutron filters respectively. The GEANT4 simulations showed that the gamma and epithermal and fast neutron could be filtered using the bismuth (Bi) and sapphire (Al 2O 3) filters, respectively. To get a good cadmium ratio, GEANT 4 simulations were used to

  10. Experience and challenges on safeguards practices and approaches for BAEC 3 MW TRIGA Mk-II research reactor and other establishment of Bangladesh

    International Nuclear Information System (INIS)

    Bangladesh is deeply committed to nuclear non-proliferation. Signing and accesses to different unilateral protocols, agreements and treaties like Nuclear Non-Proliferation Treaty (NPT), Comprehensive Test Ban Treaty (CTBT), Safeguards Agreements, Nuclear Cooperation Agreements with the USA and other countries etc. are the manifestations of such commitment. The first of such agreements, the NPT was signed in August 1979. Subsequently a bilateral agreement entitled 'Safeguards Agreements' was signed with the International Atomic Energy Agency (IAEA) in June 1982. This provides for international verification of facilities and balancing of nuclear materials and the facility, TRIGA Mark-II Research Reactor Facility of Bangladesh Atomic Energy Commission (BAEC) is inspected physically by the IAEA Safeguards Inspectors on an annual basis. For this purpose, a subsidiary arrangement was made with the IAEA, which had defined the scope of such verification. Bangladesh has also signed a Nuclear Cooperation Agreement with the USA on September 17, 1981, which facilitated export of nuclear technology from USA to Bangladesh. Bangladesh also signed another bilateral agreement entitled 'Protocol Additional to the Safeguards Agreements' with the IAEA in March 30, 2001. This protocol till to-date is the highest level of verification under the non-proliferation regime. The commitment of Bangladesh to non-proliferation is adequately reflected in this document. IAEA would decide on the modalities, frequency and scope of conducting its verification program on the basis of the declaration. Bangladesh signed the CTBT in October 1996. The Treaty was ratified in March 2000. This is a manifestation of Bangladesh's potential nuclear capabilities and by signing this Bangladesh has adequately and convincingly reiterated its commitment to the international community about its peaceful intentions. Atomic Energy Research Establishment (AERE) is the largest R and D establishment of the BAEC. It is

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

    Science.gov (United States)

    Schmitz, Tobias; Blaickner, Matthias; Schütz, Christian; Wiehl, Norbert; Kratz, Jens V; Bassler, Niels; Holzscheiter, Michael H; Palmans, Hugo; Sharpe, Peter; Otto, Gerd; Hampel, Gabriele

    2010-10-01

    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 biological effectiveness (RBE) of liver and cancer cells in our mixed neutron and gamma field. We work with alanine detectors in combination with Monte Carlo simulations, where we can measure and characterize the dose. To verify our calculations we perform neutron flux measurements using gold foil activation 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 FLUKA, a multipurpose Monte Carlo transport code. The pin-diode is augmented by a lithium fluoride foil. This foil converts the neutrons into alpha and tritium particles which are products of the (7)Li(n,α)(3)H-reaction. These particles are detected by the diode and their amount correlates to the neutron fluence directly. Results and discussion. Gold foil activation and the pin-diode are reliable fluence measurement systems for the TRIGA reactor, Mainz. Alanine dosimetry of the photon field and charged particle field from secondary reactions can in principle be carried out in combination with MC-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 of the mixed neutron and gamma field of the TRIGA Mainz is possible in order to characterize the neutron behavior in the thermal column. Currently we also

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

    International Nuclear Information System (INIS)

    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 Univ. of Mainz (DE), it is necessary to have a reliable dose monitoring system. The in vitro experiments are used to determine the relative biological effectiveness (RBE) of liver and cancer cells in our mixed neutron and gamma field. We work with alanine detectors in combination with Monte Carlo simulations, where we can measure and characterize the dose. To verify our calculations we perform neutron flux measurements using gold foil activation and pin-diodes. Material and methods. When L-a-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 FLUKA, a multipurpose Monte Carlo transport code. The pin-diode is augmented by a lithium fluoride foil. This foil converts the neutrons into alpha and tritium particles which are products of the 7Li(n,a)3H-reaction. These particles are detected by the diode and their amount correlates to the neutron fluence directly. Results and discussion. Gold foil activation and the pin-diode are reliable fluence measurement systems for the TRIGA reactor, Mainz. Alanine dosimetry of the photon field and charged particle field from secondary reactions can in principle be carried out in combination with MC-calculations for mixed radiation fields and the Hansen and 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 of the mixed neutron and gamma field of the TRIGA Mainz is possible in order to characterize the neutron behavior in the thermal column. Currently we also speculate on

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

    Science.gov (United States)

    Schmitz, Tobias; Blaickner, Matthias; Schütz, Christian; Wiehl, Norbert; Kratz, Jens V; Bassler, Niels; Holzscheiter, Michael H; Palmans, Hugo; Sharpe, Peter; Otto, Gerd; Hampel, Gabriele

    2010-10-01

    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 biological effectiveness (RBE) of liver and cancer cells in our mixed neutron and gamma field. We work with alanine detectors in combination with Monte Carlo simulations, where we can measure and characterize the dose. To verify our calculations we perform neutron flux measurements using gold foil activation 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 FLUKA, a multipurpose Monte Carlo transport code. The pin-diode is augmented by a lithium fluoride foil. This foil converts the neutrons into alpha and tritium particles which are products of the (7)Li(n,α)(3)H-reaction. These particles are detected by the diode and their amount correlates to the neutron fluence directly. Results and discussion. Gold foil activation and the pin-diode are reliable fluence measurement systems for the TRIGA reactor, Mainz. Alanine dosimetry of the photon field and charged particle field from secondary reactions can in principle be carried out in combination with MC-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 of the mixed neutron and gamma field of the TRIGA Mainz is possible in order to characterize the neutron behavior in the thermal column. Currently we also

  14. Network Topology of the Austrian Airline Flights

    CERN Document Server

    Han, D D; Qian, J H

    2007-01-01

    We analyze the directed, weighted and evolutionary Austrian airline flight network. It is shown that such a specific airline flight network displays features of small-world networks, namely large clustering coefficient and small average shortest-path length. We study the detailed flight information both in a week and on a whole. In both cases, the degree distributions reveal power law with exponent value of 2 $\\sim$ 3 for the small degree branch and a flat tail for the large degree branch. Similarly, the flight weight distributions have power-law for the small weight branch. The degree-degree correlation analysis shows the network has disassortative behavior, i.e. the large airports are likely to link to smaller airports.

  15. Austrian Carbon Calculator (ACC) - modelling soil carbon dynamics in Austrian soils

    Science.gov (United States)

    Sedy, Katrin; Freudenschuss, Alexandra; Zethner, Gehard; Spiegel, Heide; Franko, Uwe; Gründling, Ralf; Xaver Hölzl, Franz; Preinstorfer, Claudia; Haslmayr, Hans Peter; Formayer, Herbert

    2014-05-01

    Austrian Carbon Calculator (ACC) - modelling soil carbon dynamics in Austrian soils. The project funded by the Klima- und Energiefonds, Austrian Climate Research Programme, 4th call Authors: Katrin Sedy, Alexandra Freudenschuss, Gerhard Zethner (Environment Agency Austria), Heide Spiegel (Austrian Agency for Health and Food Safety), Uwe Franko, Ralf Gründling (Helmholtz Centre for Environmental Research) Climate change will affect plant productivity due to weather extremes. However, adverse effects could be diminished and satisfying production levels may be maintained with proper soil conditions. To sustain and optimize the potential of agricultural land for plant productivity it will be necessary to focus on preserving and increasing soil organic carbon (SOC). Carbon sequestration in agricultural soils is strongly influenced by management practice. The present management is affected by management practices that tend to speed up carbon loss. Crop rotation, soil cultivation and the management of crop residues are very important measures to influence carbon dynamics and soil fertility. For the future it will be crucial to focus on practical measures to optimize SOC and to improve soil structure. To predict SOC turnover the existing humus balance model the application of the "Carbon Candy Balance" was verified by results from Austrian long term field experiments and field data of selected farms. Thus the main aim of the project is to generate a carbon balancing tool box that can be applied in different agricultural production regions to assess humus dynamics due to agricultural management practices. The toolbox will allow the selection of specific regional input parameters for calculating the C-balance at field level. However farmers or other interested user can also apply their own field data to receive the result of C-dynamics under certain management practises within the next 100 years. At regional level the impact of predefined changes in agricultural management

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

    Energy Technology Data Exchange (ETDEWEB)

    Auterinen, Iiro; Salmenhaara, Seppo [VTT Technical Research Centre of Finland Otaniemi, Espoo (Finland)

    2008-10-29

    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

  17. 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)

  18. Capital Market-Oriented Financing Prospects for Austrian SMEs

    OpenAIRE

    Michael Halling; Josef Zechner

    2005-01-01

    The performance and growth of the Austrian economy largely depend on small and medium-sized enterprises (SMEs). Despite their diminutive size, SMEs offer attractive investment opportunities that are, however, financed primarily by debt for a variety of reasons. The financing concept presented in this study adopts an innovative approach to provide access to quasi-equity forms of financing to Austrian SMEs, which have successfully and responsibly generated business in recent years and which cur...

  19. Acidification and Nitrogen Eutrophication of Austrian Forest Soils

    OpenAIRE

    Robert Jandl; Stefan Smidt; Franz Mutsch; Alfred Fürst; Harald Zechmeister; Heidi Bauer; Thomas Dirnböck

    2012-01-01

    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...

  20. The Meaning of Market : Comparing Austrian and Institutional Economics

    OpenAIRE

    Dulbecco, Philippe; DUTRAIVE

    1997-01-01

    Our contribution aims at revealing the terms of a confrontation between Austrian and Institutional schools concerning the nature and the role of markets. Such an approach is justified by, on the one hand, the characteristics shared by both theoretical traditions, and on the other by the existence of complementarity, which founds a representation of market mechanisms in terms of process. The point is that if the economic analysis of institutions constitutes an essential link in the Austrian pr...

  1. The radiation protection units of the Austrian fire brigades; Die Strahlenschutz-Einheiten der oesterreichischen Feuerwehren

    Energy Technology Data Exchange (ETDEWEB)

    Aspek, W. [Oesterreichischer Bundesfeuerwehr, Wien (Austria); Schoenhacker, S. [WIRK.ZONE, Wien (Austria)

    2009-07-01

    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.)

  2. PEGASUS - An Austrian Nanosatellite for QB50

    Science.gov (United States)

    Scharlemann, Carsten; Seifert, Bernhard; Kohl, Dominik; Birschitzky, David; Gury, Lionel; Kerschbaum, Franz; Obertscheider, Christof; Ottensamer, Roland; Reissner, Alexander; Riel, Thomas; Sypniewski, Richard; Taraba, Michael; Trausmuth, Robert; Turetschek, Thomas

    2015-04-01

    PEGASUS - An Austrian Nanosatellite for QB50 C. Scharlemann* David Birschitzky* Lionel Gury*, Franz Kerschbaum~, Dominik Kohl#, Christof Obertscheider*, Roland Ottensamer~, Alexander Reissner+, Thomas Riel#, B. Seifert+, Richard Sypniewski*, Michael Taraba?, Robert Trausmuth*, Thomas Turetschek?, …. (*)University of Applied Sciences Wiener Neustadt, Austria (+)FOTEC GmbH, Wiener Neustadt, Austria (+) Spaceteam, TU Wien, Austria (~) University Wien, Wien, Austria The QB50 project is an international project with the goal to send up to 50 Nanosatellites, a.k.a. CubeSat, into the Thermosphere. The scientific goal of this mission is to monitor over a period of up to nine months the prevailing conditions in this rather unknown part of Earth's atmosphere. Each of the 50 nanosatellites will be equipped with one of three possible scientific instruments: (i) a set of Langmuir probes, (ii) atomic oxygen measurement device, (iii) ion/neutral mass spectrometer. All satellites will be launched together and released in a string-of-pearls type fashion. It is predicted that the satellites will drift apart rather rapidly following the release. Therefore, the QB50 missions offers the possibility of a measurement grid in the thermosphere of unprecedented scope and accuracy. One of the satellites, named PEGASUS, is designed and build by a team of Austrian researches and students. PEGASUS will be equipped with the aforementioned Langmuir probes and will provide information about essential properties of the plasma in the thermosphere such as the electrontemperature and -density. In order to ensure the capability to collect and downlink the data over several months, PEGASUS requires about the same types of subsystems as one would find on large-scale satellites. This includes an attitude control system, an on-board computer, telecommunication devices, an electrical power systems allowing to harvest the solar power and either distribute or store it for later use, a thermal control system

  3. Austrian Business Cycle Theory: Did Iceland go through an Austrian Business Cycle?

    OpenAIRE

    Ragnar Haukur Ragnarsson 1978

    2012-01-01

    The question this research tries to answer is if an artificial credit expansion caused the Icelandic economy to go into an Austrian style business cycle in the first decade of this century. To answer that question data from the Statistic of Iceland and the Central Bank of Iceland will be studied. The period that will be looked at is the years from 2001 until 2010. The framework that is used is taken from Jesús Huerta de Soto´s book “Money, Bank Credit, and Economic Cycles”, in that book d...

  4. 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

  5. Natural radionuclides in Austrian bottled mineral waters

    International Nuclear Information System (INIS)

    All commercially available mineral waters of Austrian origin were investigated with regard to the natural radionuclides 228Ra, 226Ra, 210Pb, 210Po, 238U and 234U. From 1 to 1.5 L of sample the nuclides were extracted and measured sequentially: the radium isotopes as well as 210Pb were measured by liquid scintillation counting after separation on a membrane loaded with element-selective particles (Empore Radium Disks), 210Po 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 NdF3. 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 228Ra. Highly mineralised waters showed also higher 226Ra and 228Ra levels. (author)

  6. [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.

  7. Assessment of sustainability in Austrian wine production

    Directory of Open Access Journals (Sweden)

    Rosner Franz Gerhard

    2015-01-01

    Full Text Available The aim of the project was to find out whether environmental sustainability can be measured not only with regard to climate change and carbon consumption but also as to other criteria concerning material consumption, energy, soil, biodiversity and water. We investigated which measures in the vineyard and wine cellar can lead to “better” sustainability while ensuring a high quality standard. 343 activities were identified to fulfill 61 quality objectives. Of the 2,191 sustainability assessments that were determined the measurements of the individual sustainability criteria vary and are in some cases even negatively correlated. Nevertheless, it was still possible to differentiate sustainably managed wineries from others in all of the Austrian wine producing areas. In our approach, a specifically developed online tool can calculate the expression of ecological, economic and social sustainability and show the effects in a spider diagram in the form of a traffic light rating system. Moreover, an algorithm suggests adequately which quality improvements can be achieved. If part of the management system is changed the online tool will show the positive and negative sustainability effects.

  8. 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.

  9. Austrian Books Online. Das Google Books-Projekt an der Österreichischen Nationalbibliothek

    OpenAIRE

    Kaiser, Max

    2012-01-01

    Austrian Books Online. The Austrian National Library’s Google Books Project (Translation of the title). In cooperation with Google, the Austrian National Library is digitising its historical, public-domain book holdings. Some 600,000 volumes from the sixteenth to the nineteenth centuries will be digitised. The project "Austrian Books Online" demonstrates that public-private partnerships can be successful in enabling heritage institutions to provide large-scale access to their holdings, provid...

  10. The Austrian Business Cycle Theory: Validity and Implications

    OpenAIRE

    2009-01-01

    In this thesis the Austrian business cycle theory is analyzed. Based on the work of Eugen von Böhm-Bawerk (1959[1889]), Knut Wicksell (1962[1898]) and Ludwig von Mises (1953[1912]), the theory was further developed and made famous by Friedrich von Hayek in the 1930s. Arguably, Hayek was the main rival of Keynes during this decade, but after heavy criticism and the publication of the General Theory (Keynes, 1936), the Austrian business cycle theory was left with few advocates by the end of Wor...

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

    Energy Technology Data Exchange (ETDEWEB)

    Wan Anuar Wan Awang; Rehir Dahalan; Shaaban Kasim [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)

  12. Electrical characterization of commercial NPN bipolar junction transistors under neutron and gamma irradiation

    OpenAIRE

    OO Myo Min; Rashid Nahrul Khair Bin Alang Md; Karim Julia Bin Abdul; Mohamed Zin Muhammad Rawi Bin; Rahim Rosminazuin Bt.Ab.; Azman Amelia Wong; Hasbullah Nurul Fadzlin

    2014-01-01

    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 irra...

  13. The Response of Alanine Dosimeters in Thermal Neutron Fields

    OpenAIRE

    Schmitz, T; Bassler, Niels; Sharpe, P; Palmans, H.; KRATZ J.v.; Langgruth, P.; HAMPEL G.

    2012-01-01

    Purpose:Boron Neutron Capture Therapy (BNCT) is a special kind of particle therapy, based on the neutron induced fission of the boron isotope 10B [1]. We have performed dosimetry experiments on the mixed neutron and gamma fields at the TRIGA Mark II research reactor in Mainz. Commonly, dosimetry in such fields is realized by foil activation and ion chambers [2]. Here we investigate alanine as an easier and more robust alternative dosimeter.Methods:We have performed four phantom experiments at...

  14. 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

  15. 48. annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    This volume contains short communications of lectures and posters of the 48th 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)

  16. 45. Annual Convention of the Austrian Physical Society

    International Nuclear Information System (INIS)

    This volume contains lectures of the 45th 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)

  17. 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.

  18. 47. annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    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)

  19. 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 should be…

  20. 50. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    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)

  1. 49. annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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)

  3. Occupational incidents with self-propelled machinery in Austrian agriculture.

    Science.gov (United States)

    Mayrhofer, Hannes; Quendler, Elisabeth; Boxberger, Josef

    2013-01-01

    Tractors, self-propelled harvesting machinery, and material handling machinery are the most commonly used self-propelled machineries in Austrian agriculture, and they have similarities in main accident scenarios. Statistical data of all occupational incidents with these machines reported between 2008 and 2010 were analyzed to obtain information about the circumstances of the incidents, and about the victims and their work environments. Criteria of recognized occupational incidents provided by the Austrian Social Insurance Institution for Farmers were analyzed according to machinery category by means of cross-tabulation and chi-square tests. The results were discussed and evaluated in the context of the literature. The results of the analysis of the databases show that 786 occupational incidents with tractors, self-propelled harvesting machinery, and material handling machinery occurred in Austrian agriculture between 2008 and 2010. There were 231 occupational incidents in 2008; the number rose to 268 in 2009 and to 286 in 2010. A total of 41 incidents were fatal. For the machinery categories analyzed, the majority of injured victims were male, older than 40 years, Austrian citizens, and managers of a mixed-agricultural farm. A large number of the incidents occurred in all machinery categories by loss of control during operating a vehicle.

  4. Two centuries of the Austrian Civil code (1811-2011

    Directory of Open Access Journals (Sweden)

    Nikolić Dušan

    2011-01-01

    Full Text Available Austrian civil code (Allgemeines bürgerliches Gesetzbuch - ABGB, ACC succeeded in resisting the challenges of time for two centuries. A number of factors influenced it's longevity. First of all, prior to adoption of the law, a long lasting and well designed work, which has been described in greater detail in this article, was done. The Code was written gradually, with lots of recalculations, checks and public debates. In legal literature, it is often written about a unique lawmaking experiment, which Austrian authorities made by implementing the Code in one part of the state territory. The Code was written for feudal order, but according to principles of natural law. This second thing has, in addition to widely formulated and flexible legal norms, left enough space for extensive interpretation of outdated rules, and filling in the legal lacunas, whose number was increasing as the time passed. Courts often used this opportunity in a creative manner, contributing to survival of the Code. Many additions and changes were made to the Code, but there were few of those who thought that it should be changed by a new one Code. Austrians are preparing a more detailed revision of the ACC, which will allow modernization of the national law and it's synchronization with trends in current European law, but on the other hand, to preserve the two century old legal heritage. The second part of this article is dedicated to the influence of the Austrian Civil Code on the development of civil law in the former Yugoslavia and Serbia. ACC served as model for adoption of the Serbian Civil Code of 1844. It was applied as a positive law in the first half of XX century, in one part of the territory of today's Autonomous Province of Vojvodina. Formally, legal rules of the Austrian Civil Code can even be applied today, according to the Law on Nullity of Legal Regulations Enacted Prior to 6th of April 1941, and During the Enemy Occupation. However, that possibility is more

  5. 57. annual symposium of the Austrian Physical Society. Conference programme

    International Nuclear Information System (INIS)

    Full text: This annual symposium was devoted to present advances in physics research performed in Austrian scientific organizations. It covered a variety of physical topics as well as the 'symposium on carbon nanophysics'. The contributions were speeches and poster sessions on the research fields of acoustics; atoms, molecules, quantum optics and plasma; solid state physics; polymer physics; physics history; nuclear and particle physics; medical, bio- and environmental physics; neutrons and synchrotron radiation physics; and surfaces and thin films. Specific topics such as the application of accelerator mass spectrometry, age dating, ATLAS experiment, electron detachment, electronic structure calculation, nanostructures, international linear collider, isobar suppression, magnetic field analysis, neutron interferometry, neutron experiments, neutron sources, nTOF project results, pionic atoms, quantum simulation, quantum well, quantum dots, quantum entanglement, quark confinement, quark gluon, quantum optics, silicon detectors, string theory development, synchrotron radiation, Austria UV indexing, Austrian radon potential, UV dosimetry were addressed. Those contributions which are in the INIS subject scope are indexed individually. (nevyjel)

  6. Some specific Austrian insights on markets and the "new economy"

    OpenAIRE

    Arena, Richard; Festré, Agnès

    2004-01-01

    In section 1 of this contribution, we will recall the usual arguments which are put forward to analyze the New Economy (NE) as the empirical realization of the Competitive Economic Equilibrium (CEE) model. After having stressed the limits of these arguments, we will try to show that some Austrian concepts and developments better fit to explain the economic impact of Information Technologies on present markets. This purpose is characterized in section 2 of this contribution. Finally, in sectio...

  7. Austrian Economics, Evolutionary Psychology and Methodological Dualism: Subjectivism Reconsidered

    OpenAIRE

    Vanberg, Viktor J.

    2004-01-01

    The methodological individualism and subjectivism of the Austrian tradition in economics is often associated with a methodological dualism, i.e. the claim that the nature of its subject matter, namely purposeful and intentional human action, requires economics to adopt a methodology that is fundamentally different from the causal explanatory approach of the natural sciences. This paper critically examines this claim and advocates an alternative, explicitly naturalistic and empiricist outlook ...

  8. Austrian Science Fund (FWF) Open Access Compliance Monitoring 2015

    OpenAIRE

    Kunzmann, Martina; Reimann, Ralph; Rieck, Katharina; Reckling, Falk

    2016-01-01

    Since 2008 the Austrian Science Fund (FWF), Austria's central funding organisation for basic research, requires from and supports all project leaders and project staff members to make their peer-reviewed research results freely available through the Internet. All principal investigators of FWF funded projects are obliged to submit a final report three months after the project is finished. The average duration of an FWF funded project from the beginning to the delivery of the final pro...

  9. Austrian meat: Authenticity control by stable isotope analysis

    International Nuclear Information System (INIS)

    Full text: The EU has declared that all foodstuff must be able to be traced back from 'fork to farm' to increase the safety of food and the confidence of the consumers in food quality and safety. Additionally, several incidents of 'food diseases and scandals' related with meat (e.g.: BSE, foot and mouth disease, antibiotics abuse, avian flu, etc.) have demonstrated the necessity to trace back the origin of meat, to be able to locate sources of infection/mismanagement. Besides the conventional method of the control of documentation there is the possibility of control of origin by analysing the isotopic composition of meat and herewith controlling the questioned good itself. Stable isotope ratios of the elements HCNOS are varying geographically due to different environmental conditions (e.g.: climate, geology, soil, altitude, geography, etc.) thus every region possesses an individual pattern. The isotopic pattern is imprinted on plants and animals growing in a certain region, and therefore analysis of the stable isotope pattern can allow the identification of agricultural goods from different regions. For the control of origin of Austrian meat about 500 beef and 500 pork samples have been collected from slaughterhouses and were analysed for the isotopic composition of carbon, nitrogen, oxygen and sulphur and compared with the isotopic composition of meat samples from neighbouring countries. As Austria, despite being a small country, is very heterogeneous in its environmental conditions, thus there are significant differences in the isotopic patterns of individual Austrian provinces. The isotopic signature of meat samples from neighbouring countries can overlap with the 'Austrian isotope pattern' due to similar environmental conditions. However, a correct statistical classification has been achieved for 80% and 84% of the analysed beef and pork samples, respectively. If the declared origin of meat can be pinned down to an Austrian province, the discrimination power of

  10. THE AUSTRIAN SCHOOL OF ECONOMICS AND MARKET INSTABILITY

    Directory of Open Access Journals (Sweden)

    Claudiu Peptine

    2013-03-01

    Full Text Available Market equilibrium is an illusion. The economic reality shows us that the main characteristic of the markets is the state of instability. The complexity of the phenomenon and the strong implications engendered by the economic fluctuations in the macro system, justify the rich scientific research activity of the main schools of economic thought to explain it. The Austrian school of economic thought has one of the most realistic analyses of the factors who generate the market instability.

  11. 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.

  12. The emergence, development and demilitarization of the military border of the Austrian Monarchy

    OpenAIRE

    Kulauzov Maša

    2008-01-01

    Military border of the Austrian Monarchy was formed gradually in border areas for the purpose of defending the border from Turkish invasions. In time, as the international political circumstances have changed, the Border itself also modified its primary function. From the beginning of the 18th century soldiers of the Military Border together with the regular troops of Austrian army participate in all wars in which Austria took part. Thanks to those soldiers the military force of the Austrian ...

  13. A Contribution to the Austrian Business Cycle Theory: Uncertainty and Price Expectations

    OpenAIRE

    Frömmel, Tomáš

    2016-01-01

    Common critique of the Austrian business cycle theory states that the Austrian cycle could not be initiated under the rational expectations hypothesis. This thesis therefore investigates the role of price expectations of entrepreneurs in the Austrian cycle theory. We conclude that this theory might be compatible with rational expectations only under several assumptions. The rational expectations hypothesis is, however, evaluated rather critically concluding it is quite strong and unrealistic ...

  14. State aid in the Austrian electricity industry law

    International Nuclear Information System (INIS)

    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

  15. Hydrogeological interpretation of natural radionuclide contents in Austrian groundwaters

    Science.gov (United States)

    Schubert, Gerhard; Berka, Rudolf; Hörhan, Thomas; Katzlberger, Christian; Landstetter, Claudia; Philippitsch, Rudolf

    2010-05-01

    The Austrian Agency for Health and Food Safety (AGES) stores comprehensive data sets of radionuclide contents in Austrian groundwater. There are several analyses concerning Rn-222, Ra-226, gross alpha and gross beta as well as selected analyses of Ra-228, Pb-210, Po-210, Uranium and U-234/U-238. In a current project financed by the Austrian Federal Ministry of Agriculture, Forestry, Environment and Water Management, AGES and the Geological Survey of Austria (GBA) are evaluating these data sets with regard to the geological backgrounds. Several similar studies based on groundwater monitoring have been made in the USA (for instance by Focazio, M.J., Szabo, Z., Kraemer, T.F., Mullin, A.H., Barringer, T.H., De Paul, V.T. (2001): Occurrence of selected radionuclides in groundwater used for drinking water in the United States: a reconnaissance survey, 1998. U.S. Geological Survey Water-Resources Investigations Report 00-4273). The geological background for the radionuclide contents of groundwater will be derived from geological maps in combination with existing Thorium and Uranium analyses of the country rocks and stream-sediments and from airborne radiometric maps. Airborne radiometric data could contribute to identify potential radionuclide hot spot areas as only airborne radiometric mapping could provide countrywide Thorium and Uranium data coverage in high resolution. The project will also focus on the habit of the sampled wells and springs and the hydrological situation during the sampling as these factors can have an important influence on the Radon content of the sampled groundwater (Schubert, G., Alletsgruber, I., Finger, F., Gasser, V., Hobiger, G. and Lettner, H. (2010): Radon im Grundwasser des Mühlviertels (Oberösterreich) Grundwasser. - Springer (in print). Based on the project results an overview map (1:500,000) concerning the radionuclide potential should be produced. The first version should be available in February 2011.

  16. Religion and suicide risk in lesbian, gay and bisexual Austrians.

    Science.gov (United States)

    Kralovec, Karl; Fartacek, Clemens; Fartacek, Reinhold; Plöderl, Martin

    2014-04-01

    Religion is known to be a protective factor against suicide. However, religiously affiliated sexual minority individuals often report a conflict between religion and sexual identity. Therefore, the protective role of religion against suicide in sexual minority people is unclear. We investigated the effect of religion on suicide risk in a sample of 358 lesbian, gay and bisexual Austrians. Religion was associated with higher scores of internalized homophobia, but with fewer suicide attempts. Our data indicate that religion might be both a risk and a protective factor against suicidality in religiously affiliated sexual minority individuals.

  17. Treatment of liquid wastes at the Austrian Research Centre Seibersdorf

    International Nuclear Information System (INIS)

    After a review of the different categories, ammounts, types and sources of liquid wastes, arising at the Austrian Research Centre Seibersdorf, the collection and distribution of these wastes are described. The treatment of these effluents in the categories Cooling Water, Faeces, Inactive Line, Active Line and Alpha Line is shown in several examples. Special attention is given on the treatment of wastes containing organic liquids. A review of the release rates shows the efficiency of the treatment system. A short view on future installations closes the paper. (author)

  18. Austrian diplomacy in a changing global and European context: Between innovation, adaptation and resilience

    NARCIS (Netherlands)

    Maurer, Heidi

    2016-01-01

    Twenty years after Austria joining the EU, this contribution investigates how Austrian diplomacy has been adjusting to the changing European demands and opportunities next to global and domestic pressures for adaptation. Austrian diplomatic adaptation has predominantly been reactive. EU membership a

  19. Regional Networks in Education: A Case Study of an Austrian Project

    Science.gov (United States)

    Rauch, Franz

    2013-01-01

    This case study presents the development of networks in education, using the Austrian IMST (Innovations Make Schools Top) project as illustration. The regional networks are coordinated in every Austrian federal province by groups made up of teachers, representatives of the educational authorities, and members of academia. In the framework of the…

  20. First annual report of the Austrian CML registry.

    Science.gov (United States)

    Schmidt, Stefan; Wolf, Dominik; Thaler, Josef; Burgstaller, Sonja; Linkesch, Wolfgang; Petzer, Andreas; Fridrik, Michael; Lang, Alois; Agis, Hermine; Valent, Peter; Krieger, Otto; Walder, Alois; Korger, Markus; Schlögl, Ernst; Sliwa, Tamer; Wöll, Ernst; Mitterer, Manfred; Eisterer, Wolfgang; Pober, Michael; Gastl, Günther

    2010-10-01

    The Austrian chronic myeloid leukemia (CML) registry monitors individual disease courses, treatments applied, clinical outcome, and side effects of CML patients on a nationwide basis to provide data on the "real-life" situation and to complement the information and interpretation gained from the selected patient population observed in clinical trials. This report summarizes the Austrian CML registry data as of March 2009. A total of 179 patients have been registered with a median number of 1012 follow-up visits and median observation duration of 20 months. At diagnosis most patients (n = 163) were in chronic phase (early, late, and secondary), whereas only 4 were in advanced phase. A total of 137 patients were treated with tyrosine kinase inhibitors (TKIs), of which 14 received first and second generation TKIs sequentially. Other treatment modalities included chemotherapy or interferon and stem cell transplantation (SCT). Cumulative incidence rates for complete hematological responses (CHR) were 91.6% and 94.4% at 12 and 24 months, respectively, compared to cumulative incidence rates of complete cytogenetical response rates of 64% and 80% at these timepoints. A total of 5 patients progressed from chronic phase to accelerated (n = 3) and blastic phase (n = 2) while receiving imatinib standard dose. Estimated overall survival (OS) rate at 60 months was 90% and progression free survival (PFS) according to European Leukemia Net (ELN) failure definition was 58%. PMID:20936366

  1. 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.

  2. Radiation dosimetry and standards at the austrian dosimetry laboratory

    International Nuclear Information System (INIS)

    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 60Co teletherapy unit, a circular exposure system for routine batch calibration of personnel dosemeters with four gamma ray sources (60Co and 137Cs) and a reference source system with six gamma ray sources (60Co and 137Cs). In addition a set of calibrated beta ray sources are provided (147Pm, 204Tl and 90Sr). 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 137Cs and 60Co 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)

  3. 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.

  4. 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.

  5. A fractal comparison of real and Austrian business cycle models

    Science.gov (United States)

    Mulligan, Robert F.

    2010-06-01

    Rescaled range and power spectral density analysis are applied to examine a diverse set of macromonetary data for fractal character and stochastic dependence. Fractal statistics are used to evaluate two competing models of the business cycle, Austrian business cycle theory and real business cycle theory. Strong evidence is found for antipersistent stochastic dependence in transactions money (M1) and components of the monetary aggregates most directly concerned with transactions, which suggests an activist monetary policy. Savings assets exhibit persistent long memory, as do those monetary aggregates which include savings assets, such as savings money (M2), M2 minus small time deposits, and money of zero maturity (MZM). Virtually all measures of economic activity display antipersistence, and this finding is invariant to whether the measures are adjusted for inflation, including real gross domestic product, real consumption expenditures, real fixed private investment, and labor productivity. This strongly disconfirms real business cycle theory.

  6. 51. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    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)

  7. 1993 energy report and energy concept of the Austrian government

    International Nuclear Information System (INIS)

    The ''1993 Energy Report'' and the ''1993 Energy Concept'' were drawn up by the Federal Minister of Economics and published by the Austrian government. Earlier reports were published in 1986 and 1990. The 1990 energy report covered the period of 1970 through 1988, the new update the years 1989 through 1991. The section on useful energy is supplemented by a coloured representation of the 1990 energy flow chart for Austria. Appendices 1 to 3 present the development of the energy economy in 1992, the publication ''Development and situation of energy research in Austria'', which was compiled in May 1993 by the Federal Minister of Science and Research, and the ''Reports on the decision of the National Council of 19 January 1993. (orig.)

  8. 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.

  9. The Herschel space telescope and the Austrian participation

    International Nuclear Information System (INIS)

    Full text: The biggest space telescope ever, Herschel was successfully launched on May 14, 2009. ESA's Space Horizon 2000 cornerstone mission will perform imaging photometry and spectroscopy in the 60-670 micron range and will address astrophysical questions ranging from our planetary system, the galaxy, the local universe out to cosmological distances. The Austrian participation in one of Herschels instruments, namely PACS is lead by the Institute for Astronomy at the University Vienna and carried out in collaboration with partners at the Technical University, Vienna and Joanneum Research, Graz in the framework of an European consortium. Both the technical contributions in the field of the on-board data reduction and compression as well as the scientific projects in the fields of late stages of stellar evolution and astro-mineralogy are outlined in the contribution. First prospective space based data sets will be available in the late August 2009 timeframe well timed for the conference. (author)

  10. 64th Annual Meeting of the Austrian Physical Society

    International Nuclear Information System (INIS)

    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

  11. Investigations of biological processes in Austrian MBT plants

    International Nuclear Information System (INIS)

    Mechanical biological treatment (MBT) of municipal solid waste (MSW) has become an important technology in waste management during the last decade. The paper compiles investigations of mechanical biological processes in Austrian MBT plants. Samples from all plants representing different stages of degradation were included in this study. The range of the relevant parameters characterizing the materials and their behavior, e.g. total organic carbon, total nitrogen, respiration activity and gas generation sum, was determined. The evolution of total carbon and nitrogen containing compounds was compared and related to process operation. The respiration activity decreases in most of the plants by about 90% of the initial values whereas the ammonium release is still ongoing at the end of the biological treatment. If the biogenic waste fraction is not separated, it favors humification in MBT materials that is not observed to such extent in MSW. The amount of organic carbon is about 15% dry matter at the end of the biological treatment.

  12. Investigations of biological processes in Austrian MBT plants.

    Science.gov (United States)

    Tintner, J; Smidt, E; Böhm, K; Binner, E

    2010-10-01

    Mechanical biological treatment (MBT) of municipal solid waste (MSW) has become an important technology in waste management during the last decade. The paper compiles investigations of mechanical biological processes in Austrian MBT plants. Samples from all plants representing different stages of degradation were included in this study. The range of the relevant parameters characterizing the materials and their behavior, e.g. total organic carbon, total nitrogen, respiration activity and gas generation sum, was determined. The evolution of total carbon and nitrogen containing compounds was compared and related to process operation. The respiration activity decreases in most of the plants by about 90% of the initial values whereas the ammonium release is still ongoing at the end of the biological treatment. If the biogenic waste fraction is not separated, it favors humification in MBT materials that is not observed to such extent in MSW. The amount of organic carbon is about 15% dry matter at the end of the biological treatment. PMID:20580543

  13. Flood Change Assessment and Attribution in Austrian alpine Basins

    Science.gov (United States)

    Claps, Pierluigi; Allamano, Paola; Como, Anastasia; Viglione, Alberto

    2016-04-01

    The present paper aims to investigate the sensitivity of flood peaks to global warming in the Austrian alpine basins. A group of 97 Austrian watersheds, with areas ranging from 14 to 6000 km2 and with average elevation ranging from 1000 to 2900 m a.s.l. have been considered. Annual maximum floods are available for the basins from 1890 to 2007 with two densities of observation. In a first period, until 1950, an average of 42 records of flood peaks are available. From 1951 to 2007 the density of observation increases to an average amount of contemporary peaks of 85. This information is very important with reference to the statistical tools used for the empirical assessment of change over time, that is linear quantile regressions. Application of this tool to the data set unveils trends in extreme events, confirmed by statistical testing, for the 0.75 and 0.95 empirical quantiles. All applications are made with specific (discharges/area) values . Similarly of what done in a previous approach, multiple quantile regressions have also been applied, confirming the presence of trends even when the possible interference of the specific discharge and morphoclimatic parameters (i.e. mean elevation and catchment area). Application of a geomorphoclimatic model by Allamano et al (2009) can allow to mimic to which extent the empirically available increase in air temperature and annual rainfall can justify the attribution of change derived by the empirical statistical tools. An comparison with data from Swiss alpine basins treated in a previous paper is finally undertaken.

  14. Experience and challenges on safeguards practices and approaches for BAEC 3 MW TRIGA Mk-II research reactor and other establishment of Bangladesh

    International Nuclear Information System (INIS)

    Bangladesh is deeply committed to nuclear non-proliferation signing and accesses to different unilateral protocols, agreements and treaties like Nuclear Non-Proliferation Treaty (NPT), Comprehensive Test Ban Treaty (CTBT), Safeguards Agreements, Nuclear Cooperation Agreements with the USA and other countries etc. are the manifestations of such commitment. The first of such agreements, the NPT was signed in August 1979. NPT is a national commitment that the signatory country will not engage in activities related on nuclear detonations. Subsequently a bilateral agreement entitled 'Safeguards Agreements' was signed with the International Atomic Energy Agency (IAEA) in June 1982. This provides for international verification of facilities and balancing of nuclear materials. 3MW TRIGA Mark-II Research Reactor Facility of Bangladesh Atomic Energy Commission (BAEC) is inspected physically by the IAEA Safeguards Inspectors on an annual basis. For this purpose, a subsidiary arrangement was made with the IAEA, which had defined the scope of such verification. Bangladesh has also signed a Nuclear Cooperation Agreement with the USA on September 17, 1981, which facilitated export of nuclear technology from USA to Bangladesh. Bangladesh also signed another bilateral agreement entitled 'Protocol Additional to the Safeguards Agreements' with the IAEA in March 30, 2001. The main purpose of this agreement is to provide the IAEA with information on 'so called dual-purpose materials and facilities' including the front end and back end of the nuclear fuel cycle. Its enforcement required filing of an initial declaration, draft of which has been sent to the Ministry of Science, Information and Communication Technology (MOSICT) for approval and transmittal to IAEA through the office of the permanent mission in Geneva. This protocol till to-date is the highest level of verification under the nonproliferation regime. The commitment of Bangladesh to non-proliferation is adequately reflected

  15. Edaphic characteristics of Austrian pine (Pinus nigra Arn.) forests in the Višegrad area

    OpenAIRE

    Blagojević Velibor D.; Knežević Milan N.; Košanin Olivera D.; Kapović-Solomun Marijana B.; Lučić Radovan J.; Eremija Saša M.

    2016-01-01

    This paper presents the results of soil research in Austrian pine (Pinus nigra Arn.) forest communities in the Višegrad area, carried out to determine the basic soil characteristics and eco-production potential of forest habitats as an important basis and framework for the successful management of these forests on the principles of sustainable development. Austrian pine forests in this region are an important and ecologically valuable community. The complex...

  16. From retreating to resisting How Austrian-Turkish women deal with experiences of racism

    OpenAIRE

    Katharina Hametner

    2014-01-01

    Recent European integration discourses are increasingly structured by neo-racist topoi based on orientalist markers of difference. In the Austrian debate, people of Turkish origin are particularly affected by such ascriptions. They are marked as a group not willing to integrate and culturally not fitting into Austrian society. In this discursive conglomerate, women are identified as oppressed victims, lacking education and being in need of help. Using the biographical narratives of young Aust...

  17. On nonneutral relative price effects in monetarist thought : some Austrian misconceptions

    OpenAIRE

    Thomas M. Humphrey

    1984-01-01

    The rise in the rate of inflation during the 1970s was paralleled by a rise in interest in monetarism, which offered the means for controlling inflation. Despite the increased interest, monetarism is still often misunderstood, as Thomas M. Humphrey points out in “On Nonneutral Relative Price Effects in Monetarist Thought: Some Austrian Misconceptions.” Economists of the Austrian school have portrayed monetarism as oblivious to the effects of monetary disturbances on the real economy of output...

  18. Direct investment strategies of Austrian companies in Romania.A comparative study

    Directory of Open Access Journals (Sweden)

    Diana Arjoca

    2011-12-01

    Full Text Available The Austrian companies present in Romania have learned their lessons after the subprime crisis started in year 2008 and although operating in various industrial areas and therefore being differently affected by the crisis, they have followed rather a similar strategy. Despite the unfavourable economic circumstances in Romania, all Austrian investors still recognise the country’s potential and have started consolidating their position on the market.

  19. New Promotion of Austrian Airlines to Celebrate the 10th Anniversary

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

      2005 marks the 10th Anniversary of Austrian Airlines' flight operations to China. Austrian Airlines kicks off the celebration year with super attractive roundtrip fares from Beijing and Shanghai to Europe starting at RMB4,500 (excluding taxes and surcharges). The earlier the tickets are booked and purchased,the lower the airfares are for travel during the period from February 13 to April 15,2005.……

  20. New Promotion of Austrian Airlines to Celebrate the 10th Anniversary

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    @@ 2005 marks the 10th Anniversary of Austrian Airlines' flight operations to China. Austrian Airlines kicks off the celebration year with super attractive roundtrip fares from Beijing and Shanghai to Europe starting at RMB4,500 (excluding taxes and surcharges). The earlier the tickets are booked and purchased,the lower the airfares are for travel during the period from February 13 to April 15,2005.

  1. Assessing the Relevance of Austrian Investment Companies and Mutual Funds for Financial Stability

    OpenAIRE

    Stefan Kavan; Günther Sedlacek; Reinhardt Seliger; Eva Ubl

    2010-01-01

    This paper looks at the role Austrian investment companies and the mutual funds managed by them play in the context of financial stability. At the end of the third quarter 2009, the 30 Austrian investment companies (of which 5 manage real estate funds) had invested around EUR 114 billion in the market. Given the repercussions arising from interlocks between investment companies and other financial intermediaries (such as credit institutions, insurance companies, pension funds and severance fu...

  2. [Recommendations of the Austrian Society of Rheumatology/Austrian Radiology-Rheumatology Initiative for Musculoskeletal Ultrasound for the application of ultrasound in rheumatology].

    Science.gov (United States)

    Duftner, Christina; Dejaco, Christian; Kainberger, Franz; Machold, Klaus; Mandl, Peter; Nothnagl, Thomas; DeZordo, Tobias; Husic, Rusmir; Schüller-Weidekamm, Claudia; Schirmer, Michael

    2014-12-01

    It is the current goal in rheumatology to diagnose and treat inflammatory rheumatic diseases early in order to avoid structural damage. Functional imaging methods such as musculoskeletal sonography are increasingly used to support the clinical diagnosis. To ascertain the quality of ultrasound assessments performed by rheumatologists in Austria, the Austrian Radiology-Rheumatology Initiative for Musculoskeletal Ultrasound (ARRIMUS) proposed recommendations for a training curriculum, technical standards for ultrasound equipment, minimum requirements for documentation, indications for sonography and the use of ultrasound for interventions. These recommendations have been endorsed by the Austrian Society of Rheumatology and should aid rheumatologists to perform high quality ultrasound assessment in clinical practice.

  3. In-core fuel management amd attainable fuel burn-up in TRIGA

    International Nuclear Information System (INIS)

    The principles of in-core fuel management in research reactors, and especially in TRIGA, are discussed. Calculations made to determine the attainable fuel burn-up values of various fuel element types in the Otaniemi TRIGA Mark II reactor are described and the results obtained are given. Recommendations are given of how to perform the in-core fuel management to achieve good fuel utilization. The results obtained indicate that burn-up values of up to 5 and 2.5 MWd/element can be achieved for the 8 wt-% U Al clad and the 8.5 wt-% U SS clad elements, respectively. (author)

  4. Research activities at the TRIGA Mainz

    International Nuclear Information System (INIS)

    The TRIGA Mark II research reactor of the Johannes Gutenberg-Universitaet Mainz is in operation since 1965 with only a few months shutdown for the refurbishment of the cooling circuits. 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. The operation of the reactor will last at least until the year 2010. The paper gives a survey of the research programmes carried out at the TRIGA Mainz. It covers a wide range of applications in nuclear chemistry, nuclear and particle physics, neutron activation analysis and isotope production for various purposes. (author)

  5. Investigations on fiberoptic behaviour during gamma irradiation

    Science.gov (United States)

    Siehs, J.

    1980-12-01

    The behavior of bulk glasses and fiber optics under gamma irradiation and two types of annealing processes (thermal and optical) were investigated. The samples were irradiated in the thermal column of the TRIGA Mark II reactor. 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 C. Photo bleaching was investigated with a quartz-lamp, an arc-lamp and an UV-laser light.

  6. Investigation of Radiation Affected High Temperature Superconductors - YBCO

    Science.gov (United States)

    Veterníková, J.; Chudý, M.; Slugeň, V.; Sojak, S.; Degmová, J.; Snopek, J.

    In this paper, high temperature superconductors are studied in terms of radiation stability, which is necessary for application in fusion reactors. Perspective superconducting materials based on YBCO (Perkovskite structure) were measured by positron annihilation lifetime spectroscopy. Measurements were performed for samples prior to and after fast neutron irradiation in TRIGA MARK II reactor in Vienna. The samples demonstrated accumulation of Cu-O di-vacancies due to the irradiation. Nevertheless, the structure showed regeneration during thermal treatment by defects recombination. Positron spectroscopy results were complemented with values of critical temperature, which also showed changes of superconducting properties after the irradiation and the annealing.

  7. Design and Characterization of a Neutron Calibration Facility for the Study of sub-keV Nuclear Recoils

    OpenAIRE

    Barbeau, P. S.; Collar, J.I.(Enrico Fermi Institute, KICP, University of Chicago, Chicago, IL, United States of America); Whaley, P. M.

    2007-01-01

    As part of an experimental effort to demonstrate sensitivity in a large-mass detector to the ultra-low energy recoils expected from coherent neutrino-nucleus elastic scattering, we have designed and built a highly monochromatic 24 keV neutron beam at the Kansas State University Triga Mark-II reactor. The beam characteristics were chosen so as to mimic the soft recoil energies expected from reactor antineutrinos in a variety of targets, allowing to understand the response of dedicated detector...

  8. Determination of the burn-up of TRIGA fuel elements by calculation and reactivity experiments

    International Nuclear Information System (INIS)

    The burnup of 17 fuel elements of the TRIGA Mark-II reactor in Vienna was measured. Different types of fuel elements had been simultaneously used for several years. The measured burnup values are compared with those calculated on the basis of core configuration and reactor operation history records since the beginning of operation. A one-dimensional, two-group diffusion computer code TRIGAP was used for the calculations. Comparison with burnup values determined by γ-scanning is also made. (orig./HP)

  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. Propositions for the Building of a Quantitative Austrian Modelling: An Answer to Prof. Rizzo and to Prof. Vriend

    OpenAIRE

    Rodolphe Buda

    2007-01-01

    In this paper, we try to promote the building of a Quantitative Austrian Modelling (QAM). QAM must be viewed as a complementary quantitative prolongation of the Austrian methods and as a complementary approach to the already existing quantitative approaches - especially we would like here to answer to the appeal of Prof. N.J.Vriend [61]. As we explain it in the first part, our approach resulted from a critical view of the econometric procedures by Austrian methods and, from a theoretical inst...

  11. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

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

  12. Severe Mycoplasma bovis outbreak in an Austrian dairy herd.

    Science.gov (United States)

    Pothmann, Harald; Spergser, Joachim; Elmer, Josef; Prunner, Isabella; Iwersen, Michael; Klein-Jöbstl, Daniela; Drillich, Marc

    2015-11-01

    A conventional dairy farm, housing 19 Austrian Simmental cows, experienced a spontaneous outbreak of a Mycoplasma bovis infection, showing severe clinical signs of respiratory tract disease, clinical mastitis, and tremendous drop in milk production. Despite intensive therapy, 5 cows died within 2 weeks or were euthanized. From the remaining cows, bacteriological culture and polymerase chain reaction revealed M. bovis in 10 of 14 milk samples. Mycoplasma bovis was found in 1 of 5 randomly collected nasal swabs. Autopsy of 1 cow revealed infection of the lungs and the udder with M. bovis. The 13 M. bovis isolates from milk samples, nasal swabs, lungs, and udder were genotyped by multilocus variable number of tandem-repeat analysis, and indicated that described infections were caused by a single M. bovis strain. The virulent M. bovis strain resulted in dramatic economic loss to the farmer. To control the disease, culling of all animals, including heifers and calves, was recommended, and strict hygienic measures were implemented before introducing new animals to the farm. PMID:26450838

  13. Cornerstones of the Austrian radon risk communication strategy

    International Nuclear Information System (INIS)

    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.

  14. The new Austrian tunnelling method in coal mining

    Energy Technology Data Exchange (ETDEWEB)

    Thierse, D.

    1987-12-03

    The new Austrian tunnelling method (NATM), as a composite support and lining system of bolts, steel mats and shotcrete, prevents the deconsolidation of the strata and activates the self-supporting properties of the strata envelope. By bringing in the strata for support it provides an exceptionally high support resistance, which outdoes steel supports and which is needed at increasing depths with their predictable high rock pressures and with large cross-sections in rooms where the limits of conventional steel arches are exceeded. Even thin shotcrete casing has a high support resistance. Where effects of other workings are present the NATM can be relied upon to have good stability over a long period and to be repair-friendly, as flaking off the casing can be made good by re-bolting and re-spraying. In contrast with the costly changing of entire support arches, partial surfaces can be repaired as required. The NATM is particularly cost-effective in the construction of drainage roads, which have to be lined against aggressive water, shaft porches, branch-offs, large rooms such as workshops, landings, belt drive rooms with internal cross-sections of 25 to 30 m/sup 2/ and shaft widening and traversing with irregular cross-sections. In geologically extremely difficult levels, such as those of the Laura and Zollverein 7/8 seams, the NATM has also been successfully used to construct drainage roads, branch-offs and shaft traverses. 30 refs., 8 figs., 6 tabs.

  15. Structures and perspectives of the Austrian energy system

    International Nuclear Information System (INIS)

    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 CO2-emissions according to the recommendations of the conference of Toronto

  16. Austrian results from Matroshka poncho and organ dose determination

    Science.gov (United States)

    Hajek, M.; Bergmann, R.; Fugger, M.; Vana, N.

    Cosmic rays in low-earth orbits LEO primarily consist of high-energy charged particles originating from galactic cosmic radiation GCR energetic solar particle events SPE and trapped radiation belts These radiations of high linear energy transfer LET generally inflict greater biological damage than that resulting from typical terrestrial radiation hazards Particle and energy spectra are attenuated in interaction processes within shielding structures and within the human body Reliable assessment of health risks to astronaut crews is pivotal in the design of future expeditions into interplanetary space and requires knowledge of absorbed radiation doses in critical radiosensitive organs and tissues The European Space Agency ESA Matroshka experiment---conducted under the aegis of the German Aerospace Center DLR ---is aimed at simulating an astronaut s body during extravehicular activities EVA Matroshka basically consists of a human phantom torso attached to a base structure and covered with a protective carbon-fibre container acting as a spacesuit model The phantom is divided into 33 tissue-equivalent polyurethane slices of specific density for tissue and organs Natural bones are embedded Channels and cut-outs enable accommodation of active and passive radiation monitors The torso is dressed by a skin-equivalent poncho which is also designed for dosimeter integration The phantom houses in total 7 active and more than 6000 passive radiation sensors Thereof the Atomic Institute of the Austrian Universities ATI provided more than

  17. France and the Austrian Empire 1815-1918

    Directory of Open Access Journals (Sweden)

    Horel Catherine

    2007-01-01

    Full Text Available Relations between France and the Habsburg Empire during the long nineteenth century went through several phases bounded by the events crucial not just to the two countries' mutual relations but to all of Europe. The Congress of Vienna defined their mutual relations for the next thirty years. The Habsburgs and their omnipresent minister Metternich were fearful of revolutionary and liberal movements traditionally having their origins in France. And it was the revolutionary events of 1848 that brought about a change in the balance of power and their mutual relations. Metternich's retirement and, more importantly, the arrival of the Russian armies in Central Europe and the subsequent strengthening of Prussia, conferred a new importance to the role of the Habsburg Monarchy as a bulwark against the advancement of Russia and a vital counterweight to Prussia. With the defeat of Napoleon III and the creation of Germany with Alsace and Lorraine Franco-Austrian relations entered a new phase. The destiny of the two provinces alienated the Habsburgs from the French Republic, especially after the reorganization of Europe into two confronting blocs. The logic of alliances led to their being adversaries in the world conflict, although Napoleon III's geo-strategic analyses remained present almost to its very end, when Clemenceau's government gave support to the nationality principle thereby crucially contributing to the collapse of the Habsburg Monarchy.

  18. 52. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    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)

  19. 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.

  20. Distribution of radiocaesium in an Austrian forest stand

    International Nuclear Information System (INIS)

    Within an Austrian spruce stand, vertical distribution of radiocaesium in soil as well as 137Cs concentration in different forest ecosystem compartments including spruce and surface water were investigated 10 years after the Chernobyl accident. The total 137Cs inventory in the forest was estimated to be 46 kBq m-2 (ref. date: 86-05-01). From the collected data annual input rates via litterfall of 0.48% per year and output rates through waterflows of only 0.02% per year were derived. The results identify the high importance of forest soils as a sink for radiocaesium. The estimated ecological residence half-times turned out to be highest in the organic soil horizons (1-3 years per cm), whereas in mineral horizons the values decrease significantly. As a consequence, soil inventory represents more than 95% of the total, whereas only approximately 3.3% of the 137Cs inventory is stored in the living biomass of spruce trees and a further 0.5% in the phytomass of understorey vegetation

  1. Assessment of radiocaesium behaviour in an Austrian forest ecosystem

    International Nuclear Information System (INIS)

    A monitoring program has been carried out since 1988 in Weinsberger Wald, an Austrian forest stand severely affected by the Chernobyl plume. Analyses of forest soils, understorey vegetation and mushrooms showed that 137Cs values decreased significantly between 1988 and 1993. In ferns, mosses and bilberry sprouts the concentrations did decrease to about 35% of the concentrations measured in 1988, however, seven years after the deposition event, the 137Cs contamination of edible forest products and game browse is still considerable. Derived ecological half-times are the longest in mushrooms (5.8 years), followed by values between 3.1-3.7 years in mosses, ferns and dwarf shrubs. Ecological half-times of 2.1 years were determined in grasses and the shortest values (1.9 years) were found in herbs (Oxalis acetosella). Annual measurements of 137Cs content in soil samples from different layers showed that the 137Cs values decreased in the litter layer, whereas they increased in mineral strata between 1988 and 1993. (author)

  2. Management of all sorts of radioactive wastes including those arising from decommissioning of research reactor

    International Nuclear Information System (INIS)

    Bangladesh has got a 3 MW TRIGA MARK-II research reactor installed in its Atomic Energy Research Establishment (AERE) at Savar, Dhaka. This report describes the plans and programmes envisaged to manage the radioactive wastes that may arise during decommissioning of this reactor. Plans and programmes have been made for the use of the space following decommissioning of the reactor because Bangladesh being a densely populated country has little scope to leave a piece of land fallow for long. The earth arising is planned to be used for filling low-lying areas. Radioactivity free metals, pipes, etc. and mildly contaminated materials are planned for reuse following suitable decontaminations. Liquid Radioactive Wastes (RW) containing various radionuclides such as Cs-137, Co-60, Sr-90, etc. will be concentrated by chemical precipitation, immobilized by cementation for ultimate disposal. Ion exchange method for decontamination of liquid LLWs have been initiated. A Central Waste Processing and Storage Facility (CWPSF) is fast nearing completion in the AERE campus at Savar. Bangladesh Atomic Energy Commission (BAEC) is implementing a long-term plan of Safe Management and Disposal of Radioactive Wastes with the technical collaboration and assistance of the IAEA and under the regulatory guidance of a National Regulatory and Control Authority for nuclear safety and radiation protection. A part of this program is concerned with the disposal of solid and solidified L/ILW. The currently preferred disposal option is engineered near-surface repository. With this end in view, geo-scientific investigations have been carried out in and a 25-km region around the campus of AERE. BAEC TRIGA facility has three Fuel Storage Pits located in the floor of the reactor hall. These pits are meant for temporary storage of spent fuel elements as well as radioactive samples. These storage pits are made of stainless steel having 10 inches diameter and 15 feet depth. Each pit is provided with a lock on

  3. Decommissioning of the Astra research reactor: Review and status on July 2003

    Directory of Open Access Journals (Sweden)

    Meyer Franz

    2003-01-01

    Full Text Available The paper describes work on the decommissioning of the ASTRA research reactor at the Austrian Research Centers Seibersdorf. Organizational, planning, and dismantling work done until July 2003 including radiation protection and waste management procedures as well as the current status of the project are presented. Completion of the decommissioning activities is planned for 2006.

  4. Climate Modeling at the Austrian Weather Service (ZAMG)

    Science.gov (United States)

    Matulla, C.; Anders, I.; Auer, I.

    2009-05-01

    In later 2007 the Austrian Weather Service (ZAMG) established a group that shall deal with climate change modeling. Two of the group's main goals are to provide climate change scenarios for the assessment of the impact on ecosystems and to reconstruct past climate states along with their change. The former aim is to derive estimates of might happen to our ecosystems under different emission-pathways, whilst the latter goal is to better understand what has caused characteristical changes, which are to be found in proxies. Both aims can be achieved by empirical or dynamical downscaling models, which are ultimately based on the reliability of the driving GCMs results. It is well known that empirical and dynamical downscaling models do have advantages and disadvantages, which are different. As such it appears reasonable to use the approach which is better adapted to the considered question. It may be meaningful to apply empirical downscaling if long periods of time (such as substantial parts of the Holocene) are in the center of attention, whereas dynamical downscaling may be better suited to address questions that are related to decades. Up to now we were more involved with empirical downscaling that helped us to work together with scientists assessing the impact on ecosystems, as for instance, fish in a river (Matulla et al. 2007), forests (Lexer et al. 2002) or phenological phases (Scheifinger et al. 2007). After catching a glimpse of those results, we will turn to dynamical modeling. Here we would like to present findings from case studies, which are related to the more recent past. Our next target is the modelling of possible future climate conditions within the Greater Alpine Region (GAR, see e.g. Auer et al. 2007) as well as some characteristical periods throughout the Holocene as for instance the 8.2k event. This event is to be found in a variety of proxies within and also outside GAR. Auer I., Boehm R., Jurkovic A., Lipa W., Orlik A., Potzmann R., Schoener W

  5. An inventory of glacial lakes in the Austrian Alps

    Science.gov (United States)

    Buckel, Johannes; Otto, Jan-Christoph; Keuschnig, Markus; Götz, Joachim

    2016-04-01

    The formation of lakes is one of the consequences of glacier retreat due to climate change in mountain areas. Numerous lakes have formed in the past few decades in many mountain regions around the globe. Some of these lakes came into focus due to catastrophic hazard events especially in the Himalayas and the Andes. Glacial lake development and lifetime is controlled by the complex interplay of glacier dynamics, geomorphological process activity and geological boundary conditions. Besides the hazard potential new lakes in formerly glaciated areas will significantly contribute to a new landscape setting and to changing geomorphologic, hydrologic and ecologic conditions at higher alpine altitudes. We present an inventory of high alpine lakes in the Austrian Alps located above an altitude of 1700 m asl. Most of these lakes are assumed to be of glacial origin, but other causes for development, like mass movements are considered as well. The inventory is a central part of the project FUTURELAKES that aims at modelling the potential development of glacial lakes in Austria (we refer to the presentation by Helfricht et al. during the conference for more details on the modelling part). Lake inventory data will serve as one basis for model validation since modelling is performed on different time steps using glacier inventory data. The purpose of the lake inventory is to get new insights into boundary conditions for lake formation and evolution by analysing existing lake settings. Based on these information the project seeks to establish a model of lake sedimentation after glacier retreat in order to assess the potential lifetime of the new lakes in Austria. Lakes with a minimum size of 1000 m² were mapped using multiple aerial imagery sources. The dataset contains information on location, geometry, dam type, and status of sedimentation for each lake. Additionally, various geologic, geomorphic and morphometric parameters describe the lake catchments. Lake data is related to

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

    International Nuclear Information System (INIS)

    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

  7. Occupational accidents with mowing machines in Austrian agriculture

    Directory of Open Access Journals (Sweden)

    Robert Kogler

    2015-02-01

    Full Text Available The number of recognized accidents during agricultural work is still very high in Austria. In the years 2008 to 2009, there occurred 84 approved work accidents with mowing machines. The main causes of accidents were the loss of control of machines, transportations or conveyances, hand tools, objects or animals. In the literature, numerous studies of general agricultural and forestry accident situations are available. Detailed studies on specific types of agricultural machines, which describe concrete circumstances and causes of accidents, are in limited numbers. The accident database from the General Accident Insurance Institution and the Austrian Social Insurance Institution of Farmers, with personal and accidental data information about mowing machine accidents, were analyzed. The results showed that most accidents occurred on mixed agricultural farms (68%. The majority of the injured persons were male (86%, over 40-years-old (86% with an agricultural or forestry education (91%. The most common accidents occurred in the summer months (69% and on afternoons during the working week (79%. The majority of accidents were caused by contact with the machine (55% and the loss of control (73% during their operation (60% and harvesting work (63%. The most frequently injuries were wounds, fractures and superficial injuries (81% to the upper and lower extremities (66%. The results of the chi-square test showed significant correlations between the specific task with the form of contact, the working process, the day and season. Results of the odds ratio determination showed an increased risk of suffering serious injury for men in the first half of the year and half of the day due to loss of control over the machine during agricultural harvesting work.

  8. 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'.

  9. No Austrians in South Tyrol? Why the German-speaking community in Italy’s South Tyrol (Alto Adige province is not usually called an Austrian minority

    Directory of Open Access Journals (Sweden)

    Michael Julian Emanuel Volkmer

    2016-08-01

    Full Text Available No Austrians in South Tyrol? Why the German-speaking community in Italy’s South Tyrol (Alto Adige province is not usually called an Austrian minority The article discusses the question why the German-speakers in Northern Italy’s South Tyrol province are only very rarely referred to as an Austrian minority, in spite of the fact that they were split off from Austria, and not Germany, in the aftermath of World War I. An analysis of the naming of German-speaking South Tyroleans in German, Austrian, Italian and English-speaking news media, which demonstrates a preference for terms such as “German-speaking minority” or “German minority” over “Austrian minority and equivalents, is followed by a discussion of three hypotheses to account for the situation. The author shows how the question of how to name the German-speaking South Tyroleans is closely intertwined with the issue of Austrian national identity and its re-orientation away from Germany in the aftermath of the Second World War. The author comes to the conclusion that the minority is not usually referred to as Austrian both due to the fact that it is difficult to include them in the young (civic Austrian nation in a logically consistent manner, and due to the German-speaking South Tyroleans’ own inconsistent self-identification as Austrians.   Nie ma Austriaków w Tyrolu Południowym? Dlaczego niemieckojęzyczna wspólnota we włoskiej prowincji Tyrol Południowy (Alto Adige zwykle nie jest nazywana mniejszością austriacką Artykuł podejmuje kwestię, dlaczego niemieckojęzyczna ludność północnowłoskiej prowincji Tyrol Południowy rzadko bywa nazywana mniejszością austriacką, pomimo tego że w efekcie I wojny światowej odłączona została ona od Austrii, a nie od Niemiec. Analiza nazewnictwa odnoszonego do niemieckojęzycznej ludności Tyrolu Południowego, które występuje w informacyjnych środkach przekazu: niemiecko-, austriacko-, włosko- i angloj

  10. Operation experience with the TRIGA Mainz and research activities at this station

    Energy Technology Data Exchange (ETDEWEB)

    Trautmann, N. (Mainz Univ. (Germany). Institut fuer Kernchemie)

    1999-12-15

    The TRIGA Mark II reactor Mainz has been in operation for more than 33 years. So far no serious problems occurred and there was only a seven months shut-down period in 1995 in order to replace the heat exchanger and to install a new primary, secondary and purification circuit. The experimental programme at the TRIGA Mainz covers a wide range of applications in nuclear chemistry, nuclear physics, neutron activation analysis and isotope production. The experimental facilities are mainly used for neutron activation analysis, for the development of fast chemical separation procedures using short lived fission products and for the production of polarized neutrons. (orig.)

  11. Density of radiolytic gas bubbles in polymethyl methacrylate

    Science.gov (United States)

    Makkonen, T.; Tiainen, O. J. A.; Valkiainen, M.; Winberg, M.

    The density of the radiolytic gas bubbles in irradiated polymethyl methacrylate was measured during subsequent heat treatment as a function of radiation dose. The samples were irradiated in the core of the Triga Mark II reactor in Otaniemi. After the irradiation periods the samples were heat treated at 393 K. The number of the bubbles could be explained by a thermal activation model. The bubbles are born in material inhomogeneities and the threshold dose for the bubble initiation was about 25 Mrad for the heat treatment at 393 K under the atmospheric pressure.

  12. Search for free neutron-antineutron oscillations

    Science.gov (United States)

    Bressi, G.; Calligarich, E.; Cambiaghi, M.; Dolfini, R.; Genoni, M.; Berzolari, A. Gigli; 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.

    1989-06-01

    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 3.2×1010 n/s. Possible antineutron annihilations are identified by a large track detector surrounding the target. A lower limit on the oscillation time of 4.7×105 s (90% C.L.) has been reached.

  13. On the way to an Austrian radon action plan; Auf dem Weg zum oesterreichischen Radonaktionsplan

    Energy Technology Data Exchange (ETDEWEB)

    Gruber, V.; Ringer, W.; Wurm, G. [Oesterreichische Agentur fuer Gesundheit und Ernaehrungssicherheit (AGES), Linz (Austria). Oesterreichische Fachstelle fuer Radon; Haider, W. [Bundesministerium fuer Land- und Forstwirtschaft, Umwelt und Wasserwirtschaft (BMLFUW), Wien (Austria). Abt. Strahlenschutz

    2013-07-01

    According to the draft of the new European Basic Safety Standards (EU-BSS) all member states are obliged to develop a national radon action plan, to control the long term risks from radon exposure in dwellings, public buildings and workplaces. The National Radon Centre, embedded in the Austrian Agency for Health and Food Safety (AGES), was assigned by the Ministry for Environment (BMLFUW) to develop this Austrian action plan and the strategy behind. This conference contribution discusses where we still have a need for actions and how the new BSS will influence the Austrian radon legislation (reference levels, responsibilities, standards, building law). Currently running and planned projects regarding the radon action plan like developing a national radon data base, definition of radon prone areas by improving the radon map and strategies to increase public radon awareness and involve the building sector are presented. (orig.)

  14. Management and Treatment for Decommissioned Combustible and Metallic Waste of Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Min, Byungyoun; Yun, Gyoungsu; Lee, Kiwon [Daedeok-daero, Daejeon (Korea, Republic of)

    2013-05-15

    Contaminated metallic waste represents a considerable storage volume as well as significant cost since it must be maintained and monitored indefinitely in secure storage. The high cost of either disposal or storage requires that the volume of material be minimized. In Korea, research reactors (TRIGA MARK II, III) have been decommissioned since 1997. A large amount of radioactively contaminated metal waste is currently produced, and will continue to be generated during decommissioning and available decontamination. The decommissioning project of the TRIGA MARK II and a uranium conversion plant (UCP) at KAERI has been completely finished. The decommission project of TRIGA MARK III has been under way. By the decommissioning of the TRIGA MARK II, radioactive metal waste of more than 200 tons was generated among the total 2,200 tons of waste, such as concrete waste, soil, combustible and non combustible waste. In the case of UCP radioactive metal waste, approximately 200 tons was generated during the decommissioning project. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. The combustible waste generated from UCP has been incineration by incinerator from last year. Decommissioned combustible waste generated from KRR will be incineration. In case of KRR metal waste, we just releasable metal waste will be melt for self-disposal and volume reduction by induction furnace. Combustible wastes were treated by incinerator and ash dispose permanently site. In case of metal wastes is treated by induction furnace and slag dispose permanently site and ingot will reuse.

  15. 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.

  16. Minority Schools in the South Tyrol and in the Austrian Burgenland: A Comparison of Two Models.

    Science.gov (United States)

    Rowley, A. R.

    1986-01-01

    Presents findings from an empirical study comparing the status of the German minority in the Italian South Tyrol and the Croatian minority in the Austrian Burgenland. The article analyzes observations of actual language use in schools and compares school authorities, curricula, and employment opportunities of the two minorities. (SED)

  17. Monitoring Language Skills in Austrian Primary (Elementary) Schools: A Case Study.

    Science.gov (United States)

    Zangl, Renate

    2000-01-01

    Provides an overview of how language skills in young learners have been assessed in two primary school contexts, carried out in a total of seven Austrian primary schools. The schools took part in an initiative where the integration of a foreign language was introduced when children entered primary school at the age of six. (Author/VWL)

  18. Progress Report 1985 of the Austrian Research Centre Seibersdorf. Abridged version

    International Nuclear Information System (INIS)

    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)

  19. 1983 Annual convention of the Austrian Physical Society, University of Linz, 28 - 30 September 1983

    International Nuclear Information System (INIS)

    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.)

  20. 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…

  1. Pragmatics of Content-Based Instruction: Teacher and Student Directives in Finnish and Austrian Classrooms

    Science.gov (United States)

    Dalton-Puffer, Christiane; Nikula, Tarja

    2006-01-01

    Using a pragmatic framework, this paper examines how directives are performed by teachers and students in Finnish and Austrian CLIL classrooms, that is settings where a foreign language (in this case English) is used as the medium of instruction in non-language subjects such as history or chemistry. We explore how interpersonal aspects of…

  2. 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…

  3. Progress Report 1984 of the Austrian Research Centre Seibersdorf. Abridged version

    International Nuclear Information System (INIS)

    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. 46th annual symposium of the Austrian Physical Society. Programme and abstracts

    International Nuclear Information System (INIS)

    This volume contains lectures (short communications) of the 46th 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)

  5. Overt and Disguised Discrimination against Women in Collective Agreements: Findings of an Austrian Survey.

    Science.gov (United States)

    Metzker, Maria

    1980-01-01

    An Austrian survey of discriminatory practices in the texts of all collective agreements in force in March 1978 (except those covering public employees) identified six main forms of potential discrimination. Examples found among white-collar workers in the private sector and among textile, clothing, and leather workers are cited. (CT)

  6. 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

  7. Bayesian Statistical Analysis Applied to NAA Data for Neutron Flux Spectrum Determination

    Science.gov (United States)

    Chiesa, D.; Previtali, E.; Sisti, M.

    2014-04-01

    In this paper, we present a statistical method, based on Bayesian statistics, to evaluate the neutron flux spectrum from the activation data of different isotopes. The experimental data were acquired during a neutron activation analysis (NAA) experiment [A. Borio di Tigliole et al., Absolute flux measurement by NAA at the Pavia University TRIGA Mark II reactor facilities, ENC 2012 - Transactions Research Reactors, ISBN 978-92-95064-14-0, 22 (2012)] performed at the TRIGA Mark II reactor of Pavia University (Italy). In order to evaluate the neutron flux spectrum, subdivided in energy groups, we must solve a system of linear equations containing the grouped cross sections and the activation rate data. We solve this problem with Bayesian statistical analysis, including 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, is used to define the problem statistical model and solve it. The energy group fluxes and their uncertainties are then determined with great accuracy and the correlations between the groups are analyzed. Finally, the dependence of the results on the prior distribution choice and on the group cross section data is investigated to confirm the reliability of the analysis.

  8. 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.

  9. Culture standards and their impact on teamwork: An empirical analysis of Austrian, German, Hungarian and Spanish culture differences

    OpenAIRE

    Dunkel, Amanda; Meierewert, Sylvia

    2004-01-01

    This article examines the impact of different cultural standards on the processes and performances of Austrian, Spanish, German and Hungarian task groups. We therefore analyzed 201 qualitative interviews with Austrians, Spaniards, Germans and Hungarians, which were conducted from 1996 to 2001. This paper uses the cultural standard framework as its theoretical background as well as the concepts of team development. The emphasis of our research is on those culture standards that have been ident...

  10. Praxeology and the firm: a contribution to the Austrian redefinition of the economic organization problem

    Directory of Open Access Journals (Sweden)

    Janković Ivan

    2006-01-01

    Full Text Available The aim of this paper is to syntetize theory of entrepreneurship of the Austrian School of economics with the contractual theory of the firm. Transaction cost theory of Ronald Coase and his followers holds that the firm is the organization with dominant component of ordering, while market is defined by competition and rivalry. But, market also includes interdependency and cooperation, such as in the case of cartel. Therefore non-competitive forms of economic coordination are not specificity for the firm, and can be observed in the open market as well. Agency theory rejects the notion of the firm as a hierarchy, and it is based on completeness of knowledge and contract. Theory of entrepreneurship and monetary calculation of Austrian School enables us to integrate contractual theory into the theoretical setting characterized by uncertainty, information asymmetry and positive transaction costs.

  11. 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)

  12. Out-of-pocket expenditures for pharmaceuticals: Lessons from the Austrian household budget survey

    OpenAIRE

    Sanwald, Alice; Theurl, Engelbert

    2015-01-01

    BACKGROUND: Paying pharmaceuticals out-of-pocket is an important source of financing pharmaceutical consumption. Only limited empirical knowledge is available on the determinants of these expenditures. OBJECTIVES: In this paper we analyze which characteristics of private households influence out-of-pocket pharmaceutical expenditure (OOPPE) in Austria. DESIGN & METHODS: We use cross-sectional information on OOPPE and on household characteristics provided by the Austrian household budget survey...

  13. Drugs from nature targeting inflammation (DNTI): a successful Austrian interdisciplinary network project

    OpenAIRE

    Waltenberger, Birgit; Atanasov, Atanas G.; Heiss, Elke H; Bernhard, David; Rollinger, Judith M.; Breuss, Johannes M.; Schuster, Daniela; Bauer, Rudolf; Kopp, Brigitte; Franz, Chlodwig; Bochkov, Valery; Marko D Mihovilovic; Dirsch, Verena M.; Stuppner, Hermann

    2016-01-01

    Abstract Inflammation is part of numerous pathological conditions, which are lacking satisfying treatment and effective concepts of prevention. A national research network project, DNTI, involving scientists from six Austrian universities as well as several external partners aimed to identify and characterize natural products capable of combating inflammatory processes specifically in the cardiovascular system. The combined use of computational techniques with traditional knowledge, high-tech...

  14. Integrating English as a Foreign Language in Austrian primary schools: contextual and participant perspectives

    OpenAIRE

    Millonig, Diana Jean

    2015-01-01

    Government guidelines in Austria specify that first and second year primary school pupils (age 6-8 years old) should receive their first teaching of a foreign language integrated into the syllabus subjects. The present study, embedded in the theoretical framework of social constructivist learning and socio-cultural language learning theories, investigated the actual classroom practices of Austrian primary school teachers during the integration of English into the lessons. The main research...

  15. Decision Criteria in Ethical Dilemma Situations: Empirical Examples from Austrian Managers

    OpenAIRE

    Litschka, Michael; Suske, Michaela; Brandtweiner, Roman

    2011-01-01

    This paper is the result of an empirical research project analysing the decision behaviour of Austrian managers in ethical dilemma situations. While neoclassical economic theory would suggest a pure economic rational basis for management decisions, the empirical study conducted by the authors put other concepts to a test, thereby analysing their importance for managerial decision making: specific notions of fairness, reciprocal altruism, and commitment. After reviewing some of ...

  16. Is Bitcoin money? An analysis from the Austrian school of economic thought

    OpenAIRE

    Ísak Andri Ólafsson 1989

    2014-01-01

    This thesis aims to explore whether digital crypto-currencies such as Bitcoin can be considered money from the perspective of the Austrian school of economics. It begins by describing the functions and design of the Bitcoin system in detail. Other innovations that either build on or improve Bitcoin will be explained as well. The functions of money are then defined from the origins of money, providing a categorical approach toward a comparison between Bitcoin and incumbent money. The risks and...

  17. Welcome address: Alois Posch on behalf of the Austrian presidency for the European Union (A)

    OpenAIRE

    Posch, Dipl.-Ing. Alois

    2006-01-01

    In Austria, organic farming has been playing an important role in the national agricultural policy. Thus, Austria has advocated to foster the development of organic farming also at the level of the EU. It is the aim of the Austrian Presidency to support the European Commission in its actions. Like other EU countries, Austria is trying to make use of the Action programme for organic farming in the best possible way for the further development of organic farming. The rural development p...

  18. Academic Anti-Semitism and the Austrian School: Vienna, 1918–1945

    OpenAIRE

    Hansjoerg Klausinger

    2013-01-01

    The theme of academic anti-Semitism has been much discussed recently in histories of the interwar period of the University of Vienna, in particular its Faculty of Law and Policy Sciences. This paper complements these studies by focusing in this regard on the economics chairs at this faculty and, more generally, on the fate of the younger generation of the Austrian school of economics. After some introductory remarks the paper concentrates on three case studies: the neglect of Mises in a...

  19. Financial and Economic Education Products and Services of Austrian Institutions and Enterprises

    OpenAIRE

    Sabine Schlögl

    2007-01-01

    Austrian institutions and enterprises offer a broad range of economic and financial literacy products and services, including online products, brochures, folders, economic simulation games, TV and radio programs, presentations, seminars, company visits and guided tours. On closer inspection, however, it turns out that some areas and target groups remain largely neglected: Education products and services for students attending primary and compulsory school are still scarce, while comprehensive...

  20. Sustainability Management with the Sustainability Balanced Scorecard in SMEs: Findings from an Austrian Case Study

    OpenAIRE

    Susanna Falle; Romana Rauter; Sabrina Engert; Rupert J. Baumgartner

    2016-01-01

    Given the economic importance of small and medium sized enterprises (SMEs) and their need for strategic sustainability management, this paper examines the concept of Sustainability Balanced Scorecard (SBSC) with respect to SMEs. This case study describes the development of an SBSC in a middle-sized Austrian brewery. The existing methods used in SBSC creation were adapted to suit the company’s specific needs. The findings show that when developing an SBSC it is important to take specific SME c...

  1. Revealed comparative advantage index: an analysis of export trade in the Austrian district of Burgerland

    OpenAIRE

    Granabetter, Doris

    2016-01-01

    The Austrian District of Burgenland is located in the eastern part of the country. In the last decade, the region has benefited from different subsidy programs from the European Union. The aim of this paper is to analyze and evaluate the export competitiveness of Burgenland in relation to the foreign trade of Austria as a whole from 2010 to 2014, which is the period showing the highest increase in exports since the Iron Curtain fell. The Revealed Comparative Advantage index (RCA) was used ...

  2. 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

    2011-04-01

    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.

  3. Towards a Dynamic Resource-Based View Insights from Austrian Capital and Entrepreneurship Theory

    OpenAIRE

    Nicolai J. Foss; Ishikawa, Ibuki

    2006-01-01

    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 orde...

  4. Negotiating Partnership: How Serbian Hauzmajstor Established a Business Relationship with Austrian Rustler

    OpenAIRE

    Vesna Vučinić-Nešković

    2016-01-01

    This study is an account of how Serbian Hauzmajstor negotiated and entered into partnership with the Austrian Rustler. The introduction is devoted to the development of Hauzmajstor, a small real estate maintenance firm, founded by a Serbian repatriate in 2004. Beginning with its start up as the first daughter firm of Komon sens, a consulting and project development firm, the study follows its adaptation to the local business environment, concentrating on its organizational and business cultur...

  5. Praxeology and the firm: a contribution to the Austrian redefinition of the economic organization problem

    OpenAIRE

    Janković Ivan

    2006-01-01

    The aim of this paper is to syntetize theory of entrepreneurship of the Austrian School of economics with the contractual theory of the firm. Transaction cost theory of Ronald Coase and his followers holds that the firm is the organization with dominant component of ordering, while market is defined by competition and rivalry. But, market also includes interdependency and cooperation, such as in the case of cartel. Therefore non-competitive forms of economic coordination are not specificity f...

  6. the term structure of interest rates: a first look at the austrian case

    OpenAIRE

    Jäger, Albert

    1985-01-01

    abstract: first, the basic idea of the expectations theory on the term structure of interest rates is sketched. a brief review of empirical evidence on the expectations theory is presented. the paper then derives and estimates a term structure equation for austrian interest rates. the empirical results for this equation seem not to be at variance with the basic idea of the expectations theory, i. e., representing the long term interest rates as a weighted average of expected short rates. a li...

  7. Bioactive Ingredients and Antioxidant Activity of Austrian Wine and Grape Juice

    OpenAIRE

    Pérez Navarro, Roser

    2008-01-01

    Wine has already been investigated for its potential nutritional quality, such as high amount of phenolic compounds. Phenolic compounds, well-known as natural antioxidants, are reported due their radical scavenging capacity. In the present work, the bioactive ingredients of nine Austrian wines (four red wines: Zweigelt, Blaufränkisch, Syrah and Cuvée; two white wines: Pinot Blanc and Chardonnay; one rosé Blaufränkisch; and two grape juice: red and white) have been quantified an...

  8. Edaphic characteristics of Austrian pine (Pinus nigra Arn. forests in the Višegrad area

    Directory of Open Access Journals (Sweden)

    Blagojević Velibor D.

    2016-01-01

    Full Text Available This paper presents the results of soil research in Austrian pine (Pinus nigra Arn. forest communities in the Višegrad area, carried out to determine the basic soil characteristics and eco-production potential of forest habitats as an important basis and framework for the successful management of these forests on the principles of sustainable development. Austrian pine forests in this region are an important and ecologically valuable community. The complexity of the geological structure and relief dynamics are dominant environmental factors that condition the expressed variability of soils in the study area. Forest communities of Austrian pine are formed on the peridotites and serpentinites, eutric ranker (haplic leptosol, eutric cambisol (haplic cambisols and pseudogley (haplic planosol, dense granular and marl limestones calcomelanosol (mollic leptosol, rendzina (rendzic leptosol and calcocambisol (leptic cambisol. The productivity of these soils is highly correlated with depth and texture composition, and the impact of these factors is linked with soil type, climate and other site conditions. In the research area, soil types with low production potential such as rankers, rendzinas, limestone and dolomite calcomelanosol are dominant. Deeper variants of eutric cambisol, pseudogley and calcocambisol can be classified as soils with moderate to high production potential.

  9. Effects of Renal Denervation Documented in the Austrian National Multicentre Renal Denervation Registry

    Science.gov (United States)

    Lambert, Thomas; Steinwender, Clemens; Weber, Thomas; Suppan, Markus; Brussee, Helmut; Koppelstätter, Christian; Kerschbaum, Julia; Watschinger, Bruno; Hohenstein-Scheibenecker, Katharina; Reindl-Schwaighofer, Roman; Sturmberger, Thomas; Kindslehner, Claudia; Weiss, Thomas Werner; Rohla, Miklos; Gruener, Peter; Maister, Petra; Auer, Johann; Dechant, Cornelia; Sykora, Josef; Krismer, Christoph; Glaser, Stefan; Zweiker, Robert

    2016-01-01

    Renal denervation (RDN) is a new procedure for treatment-resistant hypertensive patients. In order to monitor all procedures undergone in Austria, the Austrian Society of Hypertension established the investigator-initiated Austrian Transcatheter Renal Denervation (TREND) Registry. From April 2011 to September 2014, 407 procedures in 14 Austrian centres were recorded. At baseline, office and mean 24-h ambulatory blood pressure (ABP) were 171/94 and 151/89 mmHg, respectively, and patients were taking a median of 4 antihypertensive medications. Mean 24-h ABP changes after 2–6 weeks, 3, 6 and 12 months were -11/-6, -8/-4, -8/-5 and -10/-6 mmHg (p<0.05 at all measurements), respectively. The periprocedural complication rate was 2.5%. Incidence of long-term complications during follow-up (median 1 year) was 0.5%. Office BP and ABP responses showed only a weak correlation (Pearson coefficient 0.303). Based on the data from the TREND registry, ambulatory blood pressure monitoring in addition to office BP should be used for patient selection as well as for monitoring response to RDN. Furthermore, criteria for optimal patient selection are suggested. PMID:27529426

  10. 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.

  11. 54. Annual symposium of the Austrian Physical Society

    International Nuclear Information System (INIS)

    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)

  12. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  13. Evaluation of Effective Delayed Neutron Fraction of RTP using MCNP

    Energy Technology Data Exchange (ETDEWEB)

    Rabir, M. H.; Hah, C. J. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-05-15

    The prompt perturbation method needs huge computation time. Nevertheless this is not an important issue as the typical MNCP computation time is decreasing rapidly with the development of high speed computer system. The purpose of this paper is to systematically evaluate β{sub eff} for annular 1000 kW RTP TRIGA Mark II cores (Core-0 and Core-14) with different type of fuel loading, using MCNP code. The difference of β{sub eff} is 0.00019 for Core-0, 0.00009 for Core-14. The results shown in this paper are better than other papers results. In reference, β{sub eff} difference is 0.00080 for 250kW TRIGA Mark II in Ljubljana. In reference, the difference is 0.0007 for VR-1 training reactor in Prague using the same prompt perturbation method. Major part of error in prompt perturbation method originates from the exclusion of prompt neutron generated by delayed neutron. The second term in the parenthesis in equation accounts for prompt neutron source induced by delayed neutron and is always negative. Exact form of equation still has error resulting from the second order terms of the perturbation theory that should be included for exactness.

  14. The ACOnet (Austrian Academic Computer Network) is data carrier for teleradiological consultations; Das ACOnet (Austrian Academic Computer Network) als Datentraeger fuer teleradiologische Konsultationen

    Energy Technology Data Exchange (ETDEWEB)

    Giacomuzzi, S.M. [Universitaetsklinik fuer Radiodiagnostik, Innsbruck (Austria)]|[Universitaetsklinik Innsbruck (Austria). Inst. fuer Medizinische Physik; Springer, P.; Dessl, A.; Waldenberger, P.; Buchberger, W.; Bodner, G.; Bale, R.; Jaschke, W. [Universitaetsklinik fuer Radiodiagnostik, Innsbruck (Austria); Stoeger, A. [Universitaetsklinik Innsbruck (Austria). Inst. fuer MRI; Schreder, J.G. [Universitaetsklinik Innsbruck (Austria). Inst. fuer Medizinische Physik; Gell, G. [Universitaetsklinik Innsbruck (Austria). Inst. fuer Medizinische Informatik

    1998-04-01

    Purpose: To assess the feasibility of image transfer for teleradiologic consultations using the Austrian Academic Computer Network (ACOnet). The ACOnet corresponds between the main univerisities to a MAN (Metropolitan Area Network) with a transfer rate of 4 Mbps. Its use is free of charge for university institutions. Materials and methods: 1740 test image data sets and 620 image data sets for teleradiological consultations were exchanged without annotations between the Departments of Diagnostic Radiology of the universities of Innsbruck and Graz, using the ACOnet. Results: Data transmission was reliable and fast with an average transfer capacity of 170.2 kBytes/s (94-341 kBytes/s). There were no major problems with image transfer during the test phase. Conclusion: Due to its high transfer capacity, the ACOnet is considered a reasonable alternative to the ISDN service. (orig.) [Deutsch] Ziel: Radiologische Bilddatensaetze sollten fuer telemedizinische Konsultationen mittels des Austrian Academic Computer Network (ACOnet) zwischen den Universitaetskliniken Innsbruck und Graz ausgetauscht werden. Das ACOnet, dessen Benutzung fuer Universitaeten frei ist, entspricht zwischen den Landesuniversitaeten einem MAN (Metropolitan Area Network) mit einer Uebertragungsrate von 4 Mbps. Material und Methode: Die Uebertragung von 1740 Testbilddatensaetzen und 12 radiologischen Konsultationen (620 Bilddatensaetze), ohne Annotationen, zwischen den radiologischen Abteilungen der Universitaetskliniken Innsbruck und Graz zum Zwecke teleradiologischer Konsultationen mittels ACOnet. Ergebnisse: Die Uebertragungen ergaben eine hohe durchschnittliche Uebertragungskapazitaet von 170,2 kBytes/s (94-341 kBytes/s). Das ACOnet erwies sich waehrend der gesamten Testphase als zuverlaessig und praktikabel fuer die Uebertragung teleradiologischer Bilddatensaetze. Schlussfolgerungen: Durch die hohe Uebertragungskapazitaet stellt das ACOnet eine erfolgversprechende Alternative zum ISDN-Service dar

  15. The knowledge balance of the inter- and transdisciplinary Austrian Landscape Research programme

    Directory of Open Access Journals (Sweden)

    Karolina Begusch-Pfefferkorn

    2009-03-01

    Full Text Available Austrian Landscape Research, a programme of the Austrian Ministry of Science, has created scientific foundations for the sustainable development of Austrian landscapes and regions (plus bordering regions. Landscapes and regions were to be explored from different angles; implementing the research findings was to be part of the research work. The programme was designed to make room for science open to society, for unconventional ideas, methods, and courses of action. Programmatic targets and research principles supported this intent. The results of the programme met with national and international approval. The ALR knowledge balance is an attempt at presenting and assessing the achievements of this comprehensive contract research programme.Le programme du Ministère autrichien des Sciences, intitulé « Recherche sur le paysage autrichien », visait à construire les fondements scientifiques d’un développement durable des paysages et des régions de l’Autriche et des territoires limitrophes. Les paysages et les régions ont été étudiés selon différentes approches disciplinaires et la mise en pratique des résultats de cette étude était partie prenante du programme de recherche. La vocation de ce programme était de faire la place à une science ouverte sur la société, à des idées, méthodes et pratiques non conventionnelles. Les objectifs du programme et les principes de recherche vont dans le sens de ces exigences. Les résultats du programme ont été reconnus sur le plan national et international. Le bilan des connaissances du programme de recherche sur le paysage autrichien (KLF a pour but de présenter et d’évaluer les performances de ce vaste programme de recherche.

  16. Austrian dose measurements onboard space station MIR and the International Space Station--overview and comparison.

    Science.gov (United States)

    Berger, T; Hajek, M; Summerer, L; Vana, N; Akatov, Y; Shurshakov, V; Arkhangelsky, V

    2004-01-01

    The Atominstitute of the Austrian Universities has conducted various space research missions in the last 12 years in cooperation with the Institute for Biomedical Problems in Moscow. They dealt with the exact determination of the radiation hazards for cosmonauts and the development of precise measurement devices. Special emphasis will be laid on the last experiment on space station MIR the goal of which was the determination of the depth distribution of absorbed dose and dose equivalent in a water filled Phantom. The first results from dose measurements onboard the International Space Station (ISS) will also be discussed. The spherical Phantom with a diameter of 35 cm was developed at the Institute for Biomedical Problems and had 4 channels where dosimeters can be exposed in different depths. The exposure period covered the timeframe from May 1997 to February 1999. Thermoluminescent dosimeters (TLDs) were exposed inside the Phantom, either parallel or perpendicular to the hull of the spacecraft. For the evaluation of the linear energy transfer (LET), the high temperature ratio (HTR) method was applied. Based on this method a mean quality factor and, subsequently, the dose equivalent is calculated according to the Q(LET infinity) relationship proposed in ICRP 26. An increased contribution of neutrons could be detected inside the Phantom. However the total dose equivalent did not increase over the depth of the Phantom. As the first Austrian measurements on the ISS dosimeter packages were exposed for 248 days, starting in February 2001 at six different locations onboard the ISS. The Austrian dosimeter sets for this first exposure on the ISS contained five different kinds of passive thermoluminescent dosimeters. First results showed a position dependent absorbed dose rate at the ISS.

  17. Progress report 1980/81 of the Austrian Academy of Sciences

    International Nuclear Information System (INIS)

    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.)

  18. The most important parasitic and saprophytic fungi in Austrian pine and Scots pine plantations in Serbia

    Directory of Open Access Journals (Sweden)

    Karadžić Dragan

    2008-01-01

    Full Text Available In Austrian pine plantations in Serbia, the greatest damage is caused by the fungi Mycosphaerella pini, Sphaeropsis sapinea, Cenangium ferruginosum, Germmeniella abietina (in the mountain regions and occasionally Armillaria spp., Lophodermium spp. (seditiosum, conigenum, pinastri and Cyclaneusma niveum. In Scots pine plantations, the greatest damage is caused by the fungi Heterobasidion annosum (especially in plantations on sandy soils, Armillaria spp, Lophodermium seditiosum, L. pinastri, Cyclaneusma minus and Sphaeropsis sapinea. Damage caused by rust fungi (Coleosporium sennecionis, Melampsora pinitorqua and Cronartium flaccidum occurs less frequently. In mountainous regions in Scots pine plantations, great damage is caused by Phacidium infestans, Lophodermella sulcigena and Gremmeniella abietina.

  19. 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.

  20. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

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

  1. 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. Austrian's syndrome: The first described case of pneumococcal meningitis pneumonia and endocarditis in an injecting drug user.

    Science.gov (United States)

    Beadsworth, Mike B J; Wooton, Dan; Chenzbraun, Adrian; Beeching, Nick J

    2007-12-01

    We describe the first reported case of Austrian's syndrome in an injecting drug user (IDU). The triad of endocarditis, meningitis and pneumonia caused by invasive pneumococcal disease (IPD) is most commonly associated with excess alcohol. Injecting drug use is a recognised risk factor for IPD, whose prevalence and resistance continue to rise. We propose that injecting drug use is associated with Austrian's syndrome and that it should at least be considered in 'at risk' groups presenting with IPD. Furthermore, IDU presenting with IPD, meningitis and pneumonia should be considered for echocardiography.

  3. 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.

  4. Renal infarction as a presentation of Austrian syndrome: thromboembolic phenomenon of pneumococcal endocarditis.

    Science.gov (United States)

    Mankongpaisarnrung, Charoen; Soontrapa, Suthipong; Nantsupawat, Teerapat; Desai, Vipul; Nugent, Kenneth

    2012-09-01

    A 52-year-old unvaccinated and splenectomized man presented with fever, altered sensorium, bilateral flank pain and chest discomfort accompanied with paroxysmal atrial fibrillation with a rapid ventricular response. An abdominal computed tomography scan was performed, which revealed a right renal infarct and splenosis. Transthoracic echocardiography was performed, which demonstrated an echodense structure on the mitral valve with mitral regurgitation and a vegetation on the aortic valve with aortic regurgitation. Subsequently, he was found to have pneumococcal infective endocarditis, pneumococcal pneumonia and bacterial meningitis, namely Austrian syndrome. He underwent an early aortic valve and mitral valve repair but still had a poor clinical outcome. Renal infarction has a mortality of approximately 13.2%, which is strongly influenced by the underlying diseases and infectious complications. Medical and surgical treatment initiated in a timely manner is often inadequate. The authors report the first case of Austrian syndrome presenting with renal infarction as a clue to an embolic event associated with infective endocarditis in this study.

  5. High concentrations of anthocyanins in genuine cherry-juice of old local Austrian Prunus avium varieties.

    Science.gov (United States)

    Schüller, Elisabeth; Halbwirth, Heidi; Mikulic-Petkovsek, Maja; Slatnar, Ana; Veberic, Robert; Forneck, Astrid; Stich, Karl; Spornberger, Andreas

    2015-04-15

    Antioxidant activity and polyphenols were quantified in vapour-extracted juice of nine Austrian, partially endemic varieties of sweet cherry (Prunus avium): cv. 'Spätbraune von Purbach', cv. 'Early Rivers', cv. 'Joiser Einsiedekirsche', cv. 'Große Schwarze Knorpelkirsche' and four unidentified local varieties. Additionally the effect of storage was evaluated for six of the varieties. A variety showing the highest antioxidant capacity (9.64 μmol Trolox equivalents per mL), total polyphenols (2747 mg/L) and total cyanidins (1085 mg/L) was suitable for mechanical harvest and its juice did not show any losses of antioxidant capacity and total anthocyanin concentration during storage. The juice of cv. 'Große Schwarze Knorpelkirsche' had also high concentrations of total anthocyanins (873 mg/L), but showed substantial losses through storage. The local Austrian sweet cherry varieties from the Pannonian climate zone are particularly suitable for the production of processed products like cherry juice with high content of anthocyanins and polyphenols. PMID:25466109

  6. THE AUSTRIAN VACCINATION PARADOX: TICK-BORNE ENCEPHALITIS VACCINATION VERSUS INFLUENZA VACCINATION.

    Science.gov (United States)

    Kunze, Ursula; Kunze, Michael

    2015-09-01

    This paper describes a paradoxical situation in Austria. The vaccination rate against tick-borne encephalitis (TBE) in the general population is 82%, which is the highest worldwide, whereas the vaccination rate against influenza is about 8% and is among the lowest worldwide. A high awareness of TBE among the Austrian population achieved by an annual social marketing programme and the wide use of effective and well-tolerated vaccines have led to a successful containment of that disease. The vaccination coverage increased from 6% in 1980 to 82% in 2013 and exceeds 90% in some high-risk areas. This has led to a steady decline in the number of TBE cases from several hundred cases to 50 to 100 cases per year. The situation in regard to influenza vaccination is the opposite. Although Austria has issued one of the most extensive recommendations for influenza vaccination worldwide, the vaccination rate of the general population is extremely low. The possible reasons for the failure in the implementation of recommendations are ignorance, lack of social marketing and the predominance of a distinct discordance within the health system in general, and the Austrian medical fraternity in particular. PMID:26615654

  7. Integrated environmental protection obligations under European law, survey analysis of Austrian legislation

    International Nuclear Information System (INIS)

    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)

  8. The Austrian health reform 2013 is promising but requires continuous political ambition.

    Science.gov (United States)

    Hofmarcher, Maria M

    2014-10-01

    The Austrian health system is much more complex and fragmented than in other OECD countries. In 2013 legislation was adopted to enhance efficiency through better balancing care provision across providers by promoting new primary care models and better coordination of care. Reform objectives should be achieved by cooperative and unified decision making across key stakeholders and by adherence to a budget cap that prescribes fiscal containment on the order of 3.4 billion Euros until 2016. This is priced into the envisaged savings of the current consolidation program. Efforts have been made to bridge the accountability divide by establishing agreements and administrative layers to govern the health system by objectives. Yet, more could have been achieved. For example, cross-stakeholder pooling of funds for better contracting governance and effective purchasing across care settings could have been introduced. This would have required addressing over capacity and fragmentation within social security. At the same time, legal provisions for cooperative governance between Sickness Funds and the governments on the regional level should have been stipulated. The Austrian 2013 reform is interesting to other countries as it aims to ensure better-balanced care at a sustainable path by employing a public management approach to governance relations across key payers of care.

  9. 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

  10. Research reactors

    International Nuclear Information System (INIS)

    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)

  11. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    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

  12. Decommissioning of the ASTRA research reactor: Dismantling the auxiliary systems and clearance and reuse of the buildings

    Directory of Open Access Journals (Sweden)

    Meyer Franz

    2008-01-01

    Full Text Available The paper presents work performed in the last phase of the decommissioning of the ASTRA research reactor at the Austrian Research Centers Seibersdorf. Dismantling the pump room installations and the ventilation system, as well as the clearance of the buildings is described. Some conclusions and summary data regarding the timetable, material management, and the cost of the entire project are also presented.

  13. Austrian visit

    CERN Multimedia

    2003-01-01

    Hans Hoffmann, Director for Technology Transfer and Scientific Computing, and Maria Rauch-Kallat, Minister of Health and Women's Issues, Austria, signing the visitors' book.Maria Rauch-Kallat, Minister of Health and Women's Issues, Austria, was welcomed by Hans Hoffmann, Director for Technology Transfer and Scientific Computing, on her visit to CERN on 19 May 2003. The theme of the visit was Technology Transfer and spin-offs from CERN for medical applications. Maria Rauch-Kallat toured also the installations of ATLAS.

  14. 87. Austrian ratification of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency

    International Nuclear Information System (INIS)

    This is the notification of the Austrian ratification of the Convention, resulting in the entry into force of the Convention for Austria on 22 December 1989. The ratification included a declaration concerning Article 10 paragraph 5(b). The text of the Convention is reproduced in English, French and German. (NEA)

  15. 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…

  16. Combining IPPC and emission trading: An assessment of energy efficiency and CO2 reduction potentials in the Austrian paper industry

    International Nuclear Information System (INIS)

    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 CO2 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 CO2 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

  17. Assessment of climate change impact on SOM balance with the Austrian Carbon Calculator

    Science.gov (United States)

    Franko, Uwe; Gründling, Ralf; Sedy, Katrin; Zethner, Gerhard; Formayer, Herbert

    2015-04-01

    Soil organic matter (SOM) balance depends on climate and climate change due to the impact on SOM turnover conditions as well as on cropping and crop yields. The Austrian Carbon calculator (ACC) is a tool for the comparison of future land use scenarios with the current agriculture in order to identify opportunities to sustain the SOM balance. The ACC can be used in a regional mode as well as in local mode for the assessment of single farm fields. The assessment is based on the concept of Biologic Active Time (BAT). BAT is calculated based on soil data from the Austrian eBod map and climate data for past and future on a 1 km grid. The ACC was implemented for the regions Mühlviertel and Marchfeld. Crop yields are calculated based on statistics from the Austrian agricultural sub regions "Kleinproduktionsgebiet" for the most common crops. The regional scenarios consist of the abundance of crops, the part of nitrogen added as mineral fertilizer and the part of irrigation. The local soil management is calculated based on crop rotations with yields, organic amendments, irrigation and the tillage system (ploughed or not ploughed). The SOM balance is assessed with the reproduction index (REP_IX) that is calculated as the quotient from carbon reproduction (Carbon flux into SOM) and the BAT value. This way REP_IX includes the impact from management as well as from climate. If the future management will not change REP_IX the SOM balance will be the same as well. This methodology helps to adapt the management to future conditions to sustain the current SOM conditions without an absolute assessment if the current SOM state is optimal or not. The regional results of ACC will be made available as thematic maps on the project web site. For local applications farmer can use the tool to analyze their special site conditions and management plans to assess the management options under climate change conditions. The described concept can be improved if reliable information about the

  18. Projected Numbers of Ischemic Strokes Recorded in the Austrian Stroke-Unit Registry from 2012 to 2075

    Science.gov (United States)

    Trinka, Eugen; Seyfang, Leonard; Mutzenbach, Sebastian; Stadler, Katharina; Pikija, Slaven; Killer, Monika; Broussalis, Erasmia

    2016-01-01

    Background and Purpose This study analyzed the number of patients with ischemic strokes recorded in the Austrian Stroke-Unit Registry with the aim of projecting this number from 2012 to 2075 and to highlight that the Austrian health system will face a dramatic increase in older patients within the next few decades. Methods Current demographic information was obtained from EUROSTAT, and information on age- and sex-stratified 1-year incidence rates of ischemic stroke were obtained from the Austrian Stroke-Unit Registry. Sensitivity analysis was performed by analyzing the projections based on predicted ageing, main, and growth population scenarios, and with stratification by age and gender. Results The total number of ischemic strokes recorded in the Austrian Stroke-Unit Registry was 8,690 in 2012 and is expected to increase to 15,826, 15,626, or 18,134 in 2075 according to the ageing, main, and growth scenarios, respectively. The corresponding numbers of patients are projected to increase or decrease within different age strata as follows (100%=number of registered ischemic strokes in 2012): 0–40 years, 100%/99% (males/females); 40–50 years, 83%/83%; 50–60 years, 98%/97%; 60–70 years, 126%/119%; 70–80 years, 159%/139%; 80–90 years, 307%/199%; and 90+ years, 894%/413%. Conclusions The ageing population in Austria will result in the number of patients increasing considerably from 2012 to 2075, to 182%, 180%, or 208% (relative to 100% in 2012) according to the ageing, main, and growth scenarios, respectively; the corresponding value among those aged 80+ years is 315%, 290%, or 347%. These figures demonstrated the importance of improving primary preventive measures. The results of this study should provide a basis for discussions among health-care professionals and economists to face the future large financial burden of ischemic stroke on the Austrian health system.

  19. Dynamic characteristics determination using noise analysis

    International Nuclear Information System (INIS)

    Using noise analysis techniques dynamical reference properties of selected variables were investigated for 250 kW TRIGA Mark II reactor during normal operation. Reference power spectra of neutron noise of the percent power channel were computed in the frequency band from 0,01 Hz to 100 Hz and operational power dependence was determined. Detailed analyses of neutron noise at very low frequencies between 0,0004 Hz and 0,2 Hz led to the conclusion that using noise analyses characteristical time constants of TRIGA reactor operating at powers from 10 kW to 250 kW can be extracted. For interpreting the experimental results a new stochastical model was developed on the basis of a nonlinear model of the TRIGA reactor. The model enabled simulation of operation at powers from 10 kW to 250 kW during small reactivity insertions. (author)

  20. Development of a transport system for the copper source of the Texas Intense Positron Source facility

    Science.gov (United States)

    Doron, O.; Biegalski, S. R.; O'Kelly, S.; Hurst, B. J.

    2006-01-01

    The transport system design and construction for The Texas Intense Positron Source (TIPS) facility has been completed. This facility is located on beam port 1 of The University of Texas at Austin TRIGA Mark II 1.1 MW research reactor. The TIPS will provide a high intensity, variable energy positron beam for use in material studies. The natural copper source is transported into beam port 1 of the reactor where it is irradiated at close proximity to the reactor core. The transport system is an L-shaped aluminum channel that utilizes pulleys to drive a source cart. The copper source is transported on the cart into and out of the beam port for irradiation. After removal from the beam port, the activated copper positron source will be placed into a vacuum chamber where the positrons are moderated with annealed tungsten foil and electrostatically extracted.