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Sample records for budapest training reactor

  1. Experimental loop in the Nuclear Training Reactor Budapest

    Energy Technology Data Exchange (ETDEWEB)

    Csom, Gy.; Kocsis, E.; Zsolnay, E.M.; Szondi, E.J.; Szuecs, I. (Budapesti Mueszaki Egyetem (Hungary). Egyetemi Reaktor)

    1982-01-01

    The in-pile loop built into the Nuclear Training Reactor of the Technical University Budapest constructed jointly with the specialists of the Moscow Energetic Institute is used for thermoradiolitic investigations of irradiated solutions under conditions of 20-300 deg C temperature and max. 150 bar pressure. Therefore, the results of such experiments can provide valuable information on the kinetics and mechanisms of chemical processes occurring in the primary and secondary circuits of WWER-type power reactors. In order to obtain results applicable also to power plant conditions, the dose rate had to be increased. Therefore, some modifications of the reactor power were necessary. Preliminary test results are summarized.

  2. Instrumentation upgrade at the Training Reactor of Budapest University

    International Nuclear Information System (INIS)

    After more than 30 years of operation, parts of the instrumentation of the Training Reactor of Budapest University is still working with original circuit boards, components from the 70's. Nowadays, with the convenience of using integrated circuits and computers, it is expectable to change from the old technology to a newer, more up-to-date measurement system, with higher reliability and with services that cannot be made with current instrumentation. Our radiation control system will be soon upgraded to a new, self-developed hightech data acquisition system. Its heart is a microcontroller based, standalone circuit. With this change reliability will dramatically improve due to small number of components, to modular firmware witten in assembly, and to the simple power supply unit. We solved the problem of remote data access (data representation), data archivation, and on-line measurements using ethernet network connection, a linux based database system with automated data upload softwares, and common, off the shelf web browsers. Software reliability was maximized by using only commercial, proven software applications which was tested by million of people. Data security is made by storing collected data on more computers, in more formats (raw text file, database file), updating them minute by minute. Using only local network addresses, encrypted data transfers, and secure connections very good access security is achieved. This way of measurement system development helps us to save time, and to make cheap systems with high flexibility. In my presentation I will show these systems in detail, with all the novel and useful features we made and are using currently at our training reactor. (author)

  3. Advanced fuel in the Budapest research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hargitai, T.; Vidovsky, I. [KFKI Atomic Energy Research Inst., Budapest (Hungary)

    1997-07-01

    The Budapest Research Reactor, the first nuclear facility of Hungary, started to operate in 1959. The main goal of the reactor is to serve neutron research, but applications as neutron radiography, radioisotope production, pressure vessel surveillance test, etc. are important as well. The Budapest Research Reactor is a tank type reactor, moderated and cooled by light water. After a reconstruction and upgrading in 1967 the VVR-SM type fuel elements were used in it. These fuel elements provided a thermal power of 5 MW in the period 1967-1986 and 10 MW after the reconstruction from 1992. In the late eighties the Russian vendor changed the fuel elements slightly, i.e. the main parameters of the fuel remained unchanged, however a higher uranium content was reached. This new fuel is called VVR-M2. The geometry of VVR-SM and VVR-M2 are identical, allowing the use to load old and new fuel assemblies together to the active core. The first new type fuel assemblies were loaded to the Budapest Research Reactor in 1996. The present paper describes the operational experience with the new type of fuel elements in Hungary. (author)

  4. Upgrading of the Budapest reactor

    International Nuclear Information System (INIS)

    The increasing importance of neutron sources, high demand for irradiation and experimental facilities as well as improved safety requirements in the 'eighties, necessitate not only a technical modernization of the Reactor but an overall upgrade including instrumentation. Such a reconstruction was decided by the Hungarian governement in 1983

  5. Cold neutron source at the Budapest reactor

    International Nuclear Information System (INIS)

    The installation of a liquid hydrogen cold neutron source assembly with a single closed circuit feed by two cryogenerators and utilizing the thermosyphon principle is in progress at the reconstructed Budapest reactor. The end of the in-pile part is a nearly tangential horizontal channel with a moderator cell of 250 cm3 volume made of aluminium alloy located in a hole inside the Be-reflector. The cold neutrons will be directed to the user positions by three mirror guide tubes. (orig.)

  6. Refueling strategy at the Budapest research reactor

    International Nuclear Information System (INIS)

    Refueling strategy is very important for nuclear power plants and for highly utilized research reactors with power level in the megawatt range. New core design shall fulfill several demands and needs which can contradict each other sometimes. The loaded uranium quantity should assure the scheduled operation time (energy generation) and the maneuvering capability even at the end of the campaign. On the other hand the built in excess reactivity cannot be too high, because otherwise it would jeopardize the shutdown margin and reactor safety. Moreover the core arrangement should be optimum for in-core irradiation purposes and for the beam port experiments too. Sometimes this demand can be in contradiction with the desired burnup level. The achieved burnup level is very important from the fresh fuel consumption point of view, which has direct economic significance, however the generated spent fuel quantity is an important issue too. The refueling technique presented here allowed us at the Budapest Research Reactor to reach average burnup levels superseding 60%. (author)

  7. Liquid hydrogen cold moderator optimisation at the Budapest Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Grosz, T.; Rosta, L. [KFKI Research Inst. for Solid State Physics, Budapest (Hungary); Mityukhlyaev, V.A.; Serebrov, A.P.; Zaharov, A.A. [St. Petersburg Nuclear Physics Institute, 188350 Gatchina, Leningrad district (Russian Federation)

    1997-06-01

    At the Budapest Research Reactor (BRR) the main functional element of the planned cold neutron source (CNS) is a special moderator cell filled with liquid hydrogen and placed at the end of a horizontal beam channel in the Be reflector close to the maximum of thermal neutron distribution. The moderator cell is inside an explosion proof vacuum case preventing the reactor itself from any damage even in the worst possible accident. Two versions of the moderator cell both directly cooled with cold He gas are compared. (orig.).

  8. Liquid hydrogen cold moderator optimisation at the Budapest Research Reactor

    International Nuclear Information System (INIS)

    At the Budapest Research Reactor (BRR) the main functional element of the planned cold neutron source (CNS) is a special moderator cell filled with liquid hydrogen and placed at the end of a horizontal beam channel in the Be reflector close to the maximum of thermal neutron distribution. The moderator cell is inside an explosion proof vacuum case preventing the reactor itself from any damage even in the worst possible accident. Two versions of the moderator cell both directly cooled with cold He gas are compared. (orig.)

  9. New possibilities of the utilization of the Budapest Research Reactor

    International Nuclear Information System (INIS)

    The Budapest Research Reactor is the first nuclear facility of Hungary. It was put into operation in 1959. The main purpose of the reactor is to serve neutron research; anyhow the isotope production is important as well. The reactor was extended by a liquid hydrogen type cold neutron source in 2000. The research possibilities are much improved by the CNS both in neutron scattering and neutron activation. This research possibility was offered to the entire user community of Europe (scientists active in member states and associated states of European Community) within the 5th Framework Programme. Eight instruments for neutron scattering, radiography and activation analyses are offered. The majority of these instruments got a much-improved utilization with the cold neutrons. The CNS sponsored partially by the Copernicus project of the EU and by the IAEA was installed at a tangential beam port of the reactor and it extended the use of the reactor, especially in the scientific field. The paper will describe the improved utilization of the reactor. (author)

  10. The Budapest research reactor as an advanced research facility for the early 21st century

    International Nuclear Information System (INIS)

    The Budapest Research Reactor, Hungary's first nuclear facility was originally put into operation in 1959. The reactor serves for: basic and applied research, technological and commercial applications, education and training. The main goal of the reactor is to serve neutron research. This unique research possibility is used by a broad user community of Europe. Eight instruments for neutron scattering, radiography and activation analyses are already used, others (e.g. time of flight spectrometer, neutron reflectometer) are being installed. The majority of these instruments will get a much improved utilization when the cold neutron source is put into operation. In 1999 the Budapest Research Reactor was operated for 3129 full power hours in 14 periods. The normal operation period took 234 hours (starting Monday noon and finishing Thursday morning). The entire production for the year 1999 was 1302 MW days. This is a slightly reduced value, due to the installation of the cold neutron source. For the year 2000 a somewhat longer operation is foreseen (near to 4000 hours), as the cold neutron source will be operational. The operation of the reactor is foreseen at least up to the end of the first decade of the 21st century. (author)

  11. CERREX Software Application at Budapest Research Reactor (BRR). Appendix V

    International Nuclear Information System (INIS)

    The BRR is a Russian designed WWRS-M10 reactor. It is a tank type, light water cooled and moderated research reactor. Its main goal is radioisotope production and neutron physics research. The BRR went critical in 1959 and during 52 years of operation, two modernizations and one partial decommissioning were carried out. After the second modernization, the reactor restarted in 1993. The planned lifetime is 30 years, and final shutdown will be in 2023. After the final shutdown, there will be a 2 year transition period and then partial decommissioning. The final goal is to dismantle the reactor system, most of the auxiliary systems and subsystems and hand the reactor building over to the Hungarian Academy of Sciences as an unrestricted site. The organization operating BRR has, since 2004, participated in the IAEA regional TC project RER/3/009 on Support in Planning for the Decommissioning of Nuclear Power Plants and Research Reactors. The first Preliminary Decommissioning Plan (PDP) was developed in 2005 and followed IAEA recommendations. A revised PDP utilized IAEA guidance given. The IAEA Expert Mission to discuss the decommissioning planning of the BRR was organized in 2010. The PDP database and the study of earlier decommissioning is the basis of CERREX software 'Inventory' and 'ISDC' work-sheets, despite the fact that the PDP structure is different from the CERREX structure

  12. Cold neutron source at the Budapest WWR-SM reactor

    International Nuclear Information System (INIS)

    Upgrading and complete reconstruction of the KFKI WWR-SM reactor includes the installation of a cold neutron source in order to improve neutron scattering facilities for condensed matter research. The principles of cold neutron moderators are given, and the operation as well as the main elements of a small size cell liquid hydrogen cold source planned to be installed are presented describing also the installation and testing procedures. The most important hazard factors and safety problems are analyzed. (author) 24 refs.; 8 figs.; 1 tab

  13. Neutron guide system at the Budapest Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Rosta, L.; Cser, L.; Grosz, T.; Toeroek, G. [Research Inst. for Solid State Physics, Budapest (Hungary); Belgya, T.; Molnar, G.; Revai, Z. [Institute of Isotopes, 1525 Budapest, KFKI, Pf. 49 (Hungary); Kaszas, G. [MIRROTRON Co. 1025 Budapest, Ozgida ut 19/3 (Hungary)

    1997-06-01

    The 10 MW research reactor was restarted after a full-scale refurbishment in 1993. An important task of the upgrading was the construction of a new experimental hall and three neutron guides have been installed for the instruments located in this area. The in-pile plug contains 25 x 100 mm{sup 2} section float glass optical elements coated with {sup 58}Ni. The guides of the same cross section have the following destination: NV1 has an interruption for the monochromator of a three-axis spectrometer and the prompt gamma activation analysis station is installed in end position. The second guide serves only for the small-angle scattering device and the third one for a reflectometer being constructed. (orig.).

  14. A new PGAI-NT setup at the NIPS facility of the Budapest Research Reactor

    International Nuclear Information System (INIS)

    Prompt gamma activation analysis (PGAA) is a well known tool for non-destructive bulk elemental analysis of objects. The measured concentrations are only representative of the whole sample if it is homogenous; otherwise it provides only a sort of average composition of the irradiated part. In this latter case one has to scan the sample to obtain the spatial distribution of the elements. To test this idea we have constructed a prompt gamma activation imaging - neutron tomograph (PGAI-NT) setup at the NIPS station of the Budapest Research Reactor, consisting of a high-resolution neutron tomograph and a germanium gamma-spectrometer. The samples are positioned relative to the intersection of the collimated neutron beam and the projection of the gamma-collimator (isocenter) by using an xyzω-moving table. (author)

  15. The small angle neutron scattering spectrometer at the Budapest research reactor

    International Nuclear Information System (INIS)

    The reinstallation of the Small Angle Neutron Scattering spectrometer (named 'Yellow Submarine') at the Budapest Research Reactor has been finished in winter 2001. Parallel to the installation of a liquid hydrogen cold source, the guide system of the spectrometer was also rebuilt to a more optimized geometry. The old natural Ni-coated guide sections of 2.5x10 cm2 after the velocity selector have been replaced by a new supermirror coated curved neutron guide with 4x4 cm2 cross section. The neutron flux of the upgraded spectrometer is much higher. The beam is formed by a fixed length collimator tube and monitored by a fission chamber. (R.P.)

  16. The new cold neutron research facility at the Budapest Research Reactor

    International Nuclear Information System (INIS)

    The new cold neutron research facility is routinely operated at the Budapest Neutron Centre since February 2001. At the 10 MW research reactor a liquid hydrogen cold neutron source (CNS) has been installed. The commissioning of the CNS has been followed by the replacement of the old neutron guides by a new supermirror guide system both for the in-pile and out-of pile part. The ensemble of the CNS and new guides provides an intensity gain of the order of 30-60. The cold neutron channel has a take-off for three beams. The first guide serves for a triple axis spectrometer and a prompt gamma activation analysis station. A small angle scattering spectrometer is installed on the middle guide, and a reflectometer is operated on the third one. (author)

  17. Foil activity measurements for testing transport calculations in the Budapest Research Reactor

    International Nuclear Information System (INIS)

    The upgraded VVR-SM type (Russian design) Budapest Research Reactor serves both research and practical applications. As a by-product of the experimental methods used in the field of the neutron activation analysis a unique opportunity arose for benchmarking the neutron physical algorithms against measurements. As the original aim of the measurements was the determination of the concentrations and the necessary neutron flux characteristics, the measured primary data had to be reevaluated to verity the neutron physical calculations. The reaction rates of the following measured reactions were selected for the comparison: 94Zr(n,γ)95Zr, 96Zr(n,γ)97Zr/97mNb, 58Ni(n,p)58Co, 176Lu(n,γ)177Lu and 197Au(n,γ)198Au. For the sake of comparison, the multigroup cross section library of the MULTICELL code had been supplemented with the data of the above reactions by using the NJOY code. As the reaction rates are measured at the same positions (practically without shielding effects), the measured and calculated reaction rate ratios were compared on the level of the multigroup MULTICELL calculations. The accuracy of the MULTICELL code for the research reactor has been tested by comparative MCNP calculations. (author)

  18. Neutron-, gamma- and X-ray three-dimensional computed tomography at the Budapest research reactor site

    Energy Technology Data Exchange (ETDEWEB)

    Balasko, Marton [KFKI Atomic Energy Research Institute H-1525 Budapest P.O. Box 49 (Hungary)]. E-mail: balasko@sunserv.kfki.hu; Kuba, Attila [Department of Image Processing and Computer Graphics, University of Szeged, Arpad ter 2, Szeged, H-6720 (Hungary); Nagy, Antal [Department of Image Processing and Computer Graphics, University of Szeged, Arpad ter 2, Szeged, H-6720 (Hungary); Kiss, Zoltan [Department of Image Processing and Computer Graphics, University of Szeged, Arpad ter 2, Szeged, H-6720 (Hungary); Rodek, Lajos [Department of Image Processing and Computer Graphics, University of Szeged, Arpad ter 2, Szeged, H-6720 (Hungary); Rusko, Laszlo [Department of Image Processing and Computer Graphics, University of Szeged, Arpad ter 2, Szeged, H-6720 (Hungary)

    2005-04-21

    A new complex, neutron-, gamma- and X-ray three-dimensional computer tomography system suitable for experimental and industrial applications has been built at the 10-MW Budapest research reactor site. After the system was installed, a number of objects were investigated and tomographic projections were made. The evaluation relied on two reconstruction approaches. One of these is the classical, filtered back-projection method using 180 projected pictures, while the other is based on discrete tomography optimization algorithms where fewer projections were needed.

  19. Reactor Physics Training

    International Nuclear Information System (INIS)

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

  20. Thermo-hydraulic test of the moderator cell of liquid hydrogen cold neutron source for the Budapest research reactor

    International Nuclear Information System (INIS)

    Thermo-hydraulic experiment was carried out in order to test performance of the direct cooled liquid hydrogen moderator cell to be installed at the research reactor of the Budapest Neutron Center. Two electric hearers up to 300 W each imitated the nuclear heat release in the liquid hydrogen as well as in construction material. The test moderator cell was also equipped with temperature gauges to measure the hydrogen temperature at different positions as well as the inlet and outlet temperature of cooling he gas. The hydrogen pressure in the connected buffer volume was also controlled. At 140 w expected total heat load the moderator cell was filled with liquid hydrogen within 4 hours. The heat load and hydrogen pressure characteristics of the moderator cell are also presented. (author)

  1. Encapsulation of nuclear spent fuel for semi-dry storage at the Budapest research reactor

    International Nuclear Information System (INIS)

    In order to change the temporary underwater storage mode of nuclear spent fuel (NSF) from wet to semi-dry as a means of slowing down or even stopping the corrosion effects of the cladding and thereby ensuring safe storage conditions for further temporary storage, AEKI's experts elaborated a canning technology and canning equipment. Manufacturing of the canning equipment and the installation work at the AFR (away from reactor) pond of the Budapest Research Reactor (BRR) were completed, and the regulatory licence for NSF encapsulation was granted in March 2002. The canning technology uses a tube-type capsule as shown. The capsule is made of aluminium alloy, with a wall thickness of 3 mm. A bottom weight, consisting of an aluminium-clad iron disk is screwed to the bottom of the capsule to ensure sinking of the encapsulated NSF assembly as well as to provide sub-criticality. The capsule is capable of accommodating one EK-10 or one triple VVR type assembly or three single VVR assemblies. The EK- 10 assemblies are packaged 'as they are', apart from a small part of the aluminium leg of a VVR assembly (∼73 mm) being cropped off before canning. The overall dimensions of the canning tube are indicated in the drawing. Encapsulation utilizes a closed technology during which the capsule undergoes a powerful drying procedure (heated by an eddy current) and it is then filled with 2.5 bar nitrogen gas (the over-pressure is needed for leak detection purposes) after which it closed by a capsule head with shrink and welded sealing. Regarding the canning equipment, its operational part is a steal structure canning cask supplied with a revolver head having 5 operating positions and a vertical transfer pipe for sucking up and floating down the capsule. The inner cavity of the cask (operator cylinder) can be closed by vacuum-tight sealing and valves. The canning steps are controlled by a PLC system. The technology includes a cropping machine for cutting the fuel legs and in case of

  2. International round table meeting of the Nuclear Technology Dept. of the Economy Management Society (ETE). [Training course on the utilization of research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Szondi, E.J. (Budapesti Mueszaki Egyetem (Hungary). Egyetemi Reaktor)

    1984-09-01

    Experiences with the utilization possibilities of training reactors were discussed by the participants of an advanced training course organized by the IAEA at the Technical University, Budapest. Fields of activities of the Nuclear Technology Dept. of Energy Management Society of Hungary, and the national nuclear power programs of the Republic of Korea, Spain, Iran and Jamaica were reviewed in the course of short lectures.

  3. Research reactor education and training

    International Nuclear Information System (INIS)

    CORYS T.E.S.S. and TECHNICATOME present in this document some of the questions that can be rightfully raised concerning education and training of nuclear facilities' staffs. At first, some answers illustrate the tackled generic topics: importance of training, building of a training program, usable tools for training purposes. Afterwards, this paper deals more specifically with research reactors as an actual training tool. The pedagogical advantages they can bring are illustrated through an example consisting in the description of the AZUR facility training capabilities followed by the detailed experiences CORYS T.E.S.S. and TECHNICATOME have both gathered and keeps on gaining using research reactors for training means. The experience shows that this incomparable training material is not necessarily reserved to huge companies or organisations' numerous personnel. It offers enough flexibility to be adapted to the specific needs of a thinner audience. Thus research reactor staffs can also take advantages of this training method. (author)

  4. Reactor neutron activation analysis of geological samples in the Training Reactor of Budapest Technical University

    International Nuclear Information System (INIS)

    A neutron activation analytical method has been elaborated for solving geochemical problems. The method is able to make serial tests. A flux of about 2.4x1011cm-2s-1 has been used. The spectrum has been detected by a Princeton Gamma-Tech type semi-conductor detector (25 cm3) and a NTA 512 B type analyser of 1024 channel. The spectrum has been evaluated by a computer. There has been a resolution of about 2 keV/channel at the 1332/4 keV peak of 60Co. 21 elements have been determined by non-destructive analysis in silicates (those which are in parenthesis only from given matrix materials). By short-time irradiation (about 10 minutes) and cooling time of 2-3 minutes Al, (V); 1-2 hours: Mn, (Ni), (Ga); of 24 hours: Na, K, (La), (Zr) have been determined. By long time irradiation (6-12

  5. Dark Tourism in Budapest

    OpenAIRE

    Shen, Cen; Li, Jin

    2011-01-01

    A new trend is developing in the tourism market nowadays – dark tourism. The main purpose of the study was to explore the marketing strategies of dark tourism sites in Budapest based on the theoretical overview of dark tourism and data gathering of quantitative research. The study started with a theoretical overview of dark tourism in Budapest. Then, the authors focused on the case study of House of Terror, one of the most important dark tourism sites in Budapest. Last, the research has ...

  6. OPAL reactor training simulator

    International Nuclear Information System (INIS)

    Full text: Full text: The OPAL Reactor Training Simulator (RTS) is a full-scope and partial replica simulator. Its functionality and development procedure follows the applicable sections of the ANSI-ANS 3.5 norm for nuclear power plant full scope simulators for operator training and examination. Its scope includes a complete set of plant normal evolutions and malfunctions obtained from the plant design basis accidents list. All the systems necessary to implement the operating procedures associated to these transients are included. Within these systems both the variables connected to the plant SCAD A and the local variables associated to field actions are modeled, leading to several thousands input-output variables in the plant mathematical model (PMM). The trainee interacts with the same plant SCADA, a Foxboro I/A Series system. Control room hardware consoles are emulated through graphical displays with touch-screen. The main system models are tested against RELAP outputs. The RTS includes several modules: a model manager (MM) that encapsulates the plant mathematical model; a simulator human machine interface, where the trainee interacts with the plant SCADA; and an instructor console (IC), where the instructor commands the simulation. The IC incorporates functionality that provides flexibility for the definition of events during a simulation; ranging from plant design basis accidents to normal plant failures, such as a sensor drift or a contact failure. These events can include actions over all plant variables. The PMM is built using Matlab-Simulink with specific libraries of components designed to facilitate the development and maintenance of the nuclear, hydraulic, ventilation and electrical plant systems models. In this paper the main features of the simulator, the tools and procedures used for its development are presented

  7. Training and Certification of Research Reactor Personnel

    International Nuclear Information System (INIS)

    The safe operation of a research reactor requires that reactor personnel be fully trained and certified by the relevant authorities. Reactor operators at PUSPATI TRIGA Reactor underwent extensive training and are certified, ever since the reactor first started its operation in 1982. With the emphasis on enhancing reactor safety in recent years, reactor operator training and certification have also evolved. This paper discusses the changes that have to be implemented and the challenges encountered in developing a new training programme to be in line with the national standards. (author)

  8. Utilization of the VR-1 training reactor

    International Nuclear Information System (INIS)

    The Paper presents basic information about utilization of the VR-1 Training Reactor at FNSPE, CTU in Prague. The reactor has been used very efficiently especially for education of university students and specialists in favour of the Czech nuclear programme for more than 15 years. It is the only reactor of this type in the Czech Republic. Therefore, students from several Czech technical universities and also from universities in Central Europe participate on its use. The VR-1 Reactor is well equipped for education and training not only by the experimental facility itself but also by carefully developed training methods. The education experiments can be combined into training courses attended by students according to their study specialization. The training programme covers overall information on nuclear safety, radiation protection, emergency preparedness, and physical protection principles. Every year, approximately 250 university students undergo training at VR-1 Reactor. Their stay at reactor site means an enormous benefit for their study process. (author)

  9. Safety operation of training reactor VR-1

    International Nuclear Information System (INIS)

    There are three nuclear research reactors in the Czech Republic in operation now: light water reactor LVR-15, maximum reactor power 10 MWt, owner and operator Nuclear Research Institute Rez; light water zero power reactor LR-0, maximum reactor power 5 kWt, owner and operator Nuclear Research Institute Rez and training reactor VR-1 Sparrow, maximum reactor power 5 kWt, owner and operate Faculty of Nuclear Sciences and Physical Engineering, CTU in Prague. The training reactor VR-1 Vrabec 'Sparrow', operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly it is designed for training the students of Czech universities, preparing the experts for the Czech nuclear programme, as well as for certain research work, and for information programmes in the nuclear programme, as well as for certain research work, and for information programmes in sphere of using the nuclear energy (public relations). (author)

  10. A central European training course on reactor physics and kinetics - The 'Eugene Wigner Course' - Organisers view

    International Nuclear Information System (INIS)

    Full text: Initiated by the 5th Framework Programme of the European Commission, the European Nuclear Engineering Network (ENEN) is preparing the future European Nuclear Education schemes, degrees and requirements. To fully utilise the benefits of international co-operation and to promote the knowledge of students in nuclear engineering a 2,5 weeks course has been organised starting in spring 2003 and 2004. The main emphasis of the course is to perform reactor physics and kinetics experiments on three different research- and training reactors in three different locations (Vienna, Prague, Budapest). The experimental work is preceded by theoretical lectures aiming to prepare the students for the experiments (Bratislava). The students' work will be evaluated, and upon success the students will get a certificate. The finally accepted credit (ECTS) value will be determined by the students' home university. The ENEN-recommended value is between 6 and 8 ECTS. The more detailed description of the course will be given in the full paper. These courses are an upgraded result of a long-standing similar cooperation between the above-mentioned four institutions in Vienna, Prague, Bratislava and Budapest. The participation was opened to students of any European university, however, basic knowledge of reactor physics theory is requested, and this knowledge has to be attested by a professor of the student's home university. The number of participants is limited to 20. The application is subject of a selection procedure, and may be refused, if the course is already fully booked, or if the selection committee decides so, due to any reason. The quality control and accreditation of ENEN assures that the acquired knowledge of the participants will fulfil the requirements of the European Nuclear Education and fits in the European ECTS system. The cost of the 18 days course is in the range of 2000 Euros, which includes the tuition fee (utilization of 3 research reactors), textbooks, the

  11. ISIS Training Reactor: A Reactor Dedicated to Education and Training for Students and Professionals

    International Nuclear Information System (INIS)

    Conclusion: • INSTN strategy: complete theoretical courses by practical courses on the ISIS research reactor. • Training courses integrated both in Academic degree programs and continuing education. • 27 hours of training courses have been developed focusing on the practical and safety aspects of reactor operation. • The Education and Training activity became the main activity of ISIS reactor: 400 trainees/year; 360 hours/year; 40% in English. • Remote access to the Training courses: Internet Reactor Laboratory under development to be started from 2014 to broadcast training courses from ISIS reactor to guest institutions

  12. A central European training course on reactor physics and kinetics - the 'Eugene Wigner Course' - Organisers view

    International Nuclear Information System (INIS)

    Initiated by the 5th Framework Program of the European Commission, the European Nuclear Engineering Network (ENEN) is preparing the future European Nuclear Education schemes, degrees and requirements. To fully utilize the benefits of international cooperation and to promote the knowledge of students in nuclear engineering a 2.5 weeks course has been held, both in spring 2003 and 2004. The main emphasis of the course is to perform reactor physics and kinetics experiments on three different research- and training reactors in three different locations (Vienna, Prague, Budapest). The experimental work is preceded by theoretical lectures aiming to prepare the students for the experiments (Bratislava). The students' work will be evaluated, and upon success the students will get a certificate. The finally accepted credit (ECTS) value will be determined by the students' home university. The ENEN-recommended value is between 6 and 8 ECTS. The more detailed description of the course will be given in the full paper. (author)

  13. Training courses at VR-1 reactor

    International Nuclear Information System (INIS)

    This paper describes one of the main purposes of the VR-1 training reactor utilization - i.e. extensive educational program. The educational program is intended for the training of university students and selected nuclear power plant personnel. The training courses provide them experience in reactor and neutron physics, dosimetry, nuclear safety and operation of nuclear facilities. At present, the training course participants can go through more than 20 standard experimental exercises; particular exercises for special training can be prepared. Approximately 200 university students become familiar with the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. The VR-1 reactor takes also part in Eugene Wigner Course on Reactor Physics Experiments in the framework of European Nuclear Educational Network (ENEN) association. Recently, training courses for Bulgarian research reactor specialists supported by IAEA were carried out. An attractive program including demonstration of reactor operation is prepared also for high school students. Every year, more than 1500 high school students come to visit the reactor, as do many foreigner visitors. (author)

  14. Experiments with the SUR 100 training reactor

    International Nuclear Information System (INIS)

    This paper contains a compilation of various experiments using the SUR - 100 reactor for training purposes, which have been widly proved in practical work at the School for Nuclear Technology of the Karlsruhe Research Center. (orig.)

  15. Education and Training on ISIS Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Foulon, F.; Badeau, G.; Lescop, B.; Wohleber, X. [French Atomic Energy and Alternative Energies Commission, Paris (France)

    2013-07-01

    In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions.

  16. Education and Training on ISIS Research Reactor

    International Nuclear Information System (INIS)

    In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions

  17. An innovative approach to reactor operator training

    International Nuclear Information System (INIS)

    As with any approach, the goals or terminal objectives must be clearly set before beginning. Just like the electric utilities, whose training programs are structured around the Institute of Nuclear Power Operations guidelines, (INPO), the Department of Energy, (DOE), has now imposed its own accreditation order. The High Flux Beam Reactor (HFBR), Reactor Operator Training Program must conform with DOE Order 548.18A, which specifies accreditation criteria. In short, the existing training program had to be upgraded to demonstrate the systematic approach to analysis, design, development, implementation and evaluation per adopted Performance-Based Training (PBT) guidelines. The expense of manpower, facilities and equipment demands an optimal return by improving not only the training program, but also the methods employed in this Training Plan Model rely on the evaluation of both the trainees' and the training system's performance. The results of these evaluations are immediately used to revise the program design, keeping the evaluation instruments up-to-date. Necessary revisions to training materials are completed before the next scheduled presentation or planned used by trainers and trainees in self-study

  18. Extensive utilization of training reactor VR-1

    International Nuclear Information System (INIS)

    Full text: The training reactor VR-1 Vrabec ('Sparrow'), operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly, it is designed and operated for training of students from Czech universities, preparing of experts for the Czech nuclear programme, as well as for certain research and development work, and for information programmes in the sphere of non-military nuclear energy use (public relation). The VR-1 training reactor is a pool-type light-water reactor based on enriched uranium with maximum thermal power 1kWth and short time period up to 5kWth. The moderator of neutrons is light demineralized water (H2O) that is also used as a reflector, a biological shielding, and a coolant. Heat is removed from the core with natural convection. The reactor core contains 14 to 18 fuel assemblies IRT-3M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The core is accommodated in a cylindrical stainless steel vessel - pool, which is filled with water. UR-70 control rods serve the reactor control and safe shutdown. Training of the VR-1 reactor provides students with experience in reactor and neutron physics, dosimetry, nuclear safety, and nuclear installation operation. Students from technical universities and from natural sciences universities come to the reactor for training. Approximately 200 university students are introduced to the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. Practical Course on Reactor Physics in Framework of European Nuclear Engineering Network has been newly introduced. Currently, students can try out more than 20 experimental exercises. Further training courses have been included to

  19. University of Florida training reactor. Annual progress report, September 1, 1984-August 31, 1985

    International Nuclear Information System (INIS)

    This annual progress report of the University of Florida Training Reactor discusses: reactor operation; personnel; modifications made to the reactors; reactor maintenance; and testing of reactor systems

  20. Experience in using a research reactor for the training of power reactor operators

    International Nuclear Information System (INIS)

    A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

  1. A high resolution X-ray fluorescence facility and its use at the training reactor of the Budapest Polytechnical University

    International Nuclear Information System (INIS)

    The X-ray emission spectrometer is equipped with a Si(Li) detector and a special pre-amplifier of reduced noise. The signals are processed by amplifier, a ground-level recondition unit, a bias amplifier and a 1024 channel analyzer. β-radiation, which would increase background noise is eliminated by the application of a magnetic field. In the spectrum of a neutron-activated distillate, lubricating oil elements which cannot be indentified even in γ-spectrums, are recognized. (V.N.)

  2. Development of Education and Training Programs Using ISIS Research Reactor

    International Nuclear Information System (INIS)

    As a part of the French Alternative Energies and Atomic Energy Commission (CEA), the National Institute for Nuclear Science and Technology (INSTN) carries out various education and training programs on nuclear reactor theory and operation. These programs take advantage of the use of an extensive range of training tools that includes software applications, simulators, as well as the use of research reactors. After a presentation of ISIS reactor, we present the training courses that have been developed on ISIS reactor and their use in education and training programs developed by INSTN. We report on how the training courses carried out on ISIS research reactor ensure a practical and comprehensive understanding of the reactor principle and operation, bringing tremendous benefit to the trainees. We also discuss the future development of education and training programs using the ISIS research reactor as a very powerful tool for the development of the human resources needed by the nuclear industry and the nuclear programs. (author)

  3. New studies of the natural convection around a fuel rod of the BME training reactor with PIV/LIF technique

    International Nuclear Information System (INIS)

    In this paper the model of a fuel pin of the Training Reactor of Budapest University of Technology and Economics was investigated with Particle Image Velocimetry and Laser Induced Fluorescence measurement methods. An experimental setup was designed, built and optimized to investigate the natural convection around a model of a fuel pin of the Training Reactor. The processes were analysed using an electrically heated rod, which models the geometry of the fuel rods in the Training Reactor. The heated length of the model is the same as the active length of the real fuel rods. The rod is placed in a glass tank with a shape of a square-based prism. An additional cooling system ensures constant flow conditions around the rod. The setup consists of an additional flow channel box, the equivalent diameter of which is equal to the equivalent diameter of the real fuel assembly. Simultaneous measurements of velocity and temperature fields were performed in different vertical positions for both cases of natural convection with and without the flow channel box. The effect of the presence of the channel was analyzed, and a laminarizating influence was observed. The local heat transfer coefficient was calculated for every measurement. The two dimensional measurement techniques gave extensive results, the structure of the hydraulic and thermal boundary layer were fully analyzed. (Authors)

  4. Development of the HANARO research reactor simulator for operator training

    International Nuclear Information System (INIS)

    HANARO (High flux Advanced Neutron Application ReactOr) is multi purpose research reactor in Korea Atomic Energy research Institute, and is operating since 1995. It is needed that training and retraining programs for the operating staff, including: reactor manager, shift supervisors, reactor operators, and others working at the research reactor facility. Recently, we developed HANARO research reactor real time simulator for operating staff training to satisfy these programs. The development of computer based training simulator have provided an easy understanding of reactor physics, operation, and control. Real time simulator is recognized as the ultimate training tool because they allow experiencing, in a dynamic mode, every type of operational condition which can be encountered including: start up, variation of power, shut down, operation during accidents, etc. Also, the simulator will be used as a dynamic test-bed for the reactor regulating system control algorithm

  5. Development of the HANARO research reactor simulator for operator training

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Kim, Jang Yeol; Park, Jae Chang; Lee, Seung Wook; Hwang, In Ah; Lee, Dong Young [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    HANARO (High flux Advanced Neutron Application ReactOr) is multi purpose research reactor in Korea Atomic Energy research Institute, and is operating since 1995. It is needed that training and retraining programs for the operating staff, including: reactor manager, shift supervisors, reactor operators, and others working at the research reactor facility. Recently, we developed HANARO research reactor real time simulator for operating staff training to satisfy these programs. The development of computer based training simulator have provided an easy understanding of reactor physics, operation, and control. Real time simulator is recognized as the ultimate training tool because they allow experiencing, in a dynamic mode, every type of operational condition which can be encountered including: start up, variation of power, shut down, operation during accidents, etc. Also, the simulator will be used as a dynamic test-bed for the reactor regulating system control algorithm.

  6. Education and Training Programme at the Research Reactor TRIGA Mainz

    Energy Technology Data Exchange (ETDEWEB)

    Hampel, Gabriele; Eberhardt, Klaus [University of Mainz, Institute for Nuclear Chemistry, D-55099 Mainz (Germany)

    2011-07-01

    Education and training are important elements for the future of nuclear science, technology and safety. Fields of interest include high- technology applications in nuclear techniques and neutron sources, advances in the areas of power reactor safety, establishing the scientific basis of new reactors, training of personnel needed to operate, maintain, regulate and improve reactors or other facilities associated with nuclear power. Also, creating a knowledgeable public through education usually means less opposition and more support. Education and training for safeguards, operators, researchers and quality programmes (calibration services, etc.) are one of the main utilisations of TRIGA research reactors. Use of a reactor as a training tool for university students studying nuclear engineering and/or physics, where there is a growing demand at European Universities, is of vital importance. In particular, the TRIGA Mark II reactor, located at the University of Mainz, one of the largest universities in Germany, offers a broad range of nuclear-related courses for training and education. (author)

  7. Education and Training Programme at the Research Reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Education and training are important elements for the future of nuclear science, technology and safety. Fields of interest include high- technology applications in nuclear techniques and neutron sources, advances in the areas of power reactor safety, establishing the scientific basis of new reactors, training of personnel needed to operate, maintain, regulate and improve reactors or other facilities associated with nuclear power. Also, creating a knowledgeable public through education usually means less opposition and more support. Education and training for safeguards, operators, researchers and quality programmes (calibration services, etc.) are one of the main utilisations of TRIGA research reactors. Use of a reactor as a training tool for university students studying nuclear engineering and/or physics, where there is a growing demand at European Universities, is of vital importance. In particular, the TRIGA Mark II reactor, located at the University of Mainz, one of the largest universities in Germany, offers a broad range of nuclear-related courses for training and education. (author)

  8. Role of research reactors in training of NPP personnel with special focus on training reactor VR-1

    International Nuclear Information System (INIS)

    Research reactors play an important role in providing key personnel of nuclear power plants a hands-on experience from operation and experiments at nuclear facilities. Training of NPP (Nuclear Power Plant) staff is usually deeply theoretical with an extensive utilisation of simulators and computer visualisation. But a direct sensing of the reactor response to various actions can only improve the personnel awareness of important aspects of reactor operation. Training Reactor VR-1 and its utilization for training of NPP operators and other professionals from Czech Republic and Slovakia is described. Typical experimental exercises and good practices in organization of a training program are demonstrated. (authors)

  9. Reactor training simulator for the Replacement Research Reactor (RRR)

    International Nuclear Information System (INIS)

    The main features of the ANSTO Replacement Research Reactor (RRR) Reactor Training Simulator (RTS) are presented.The RTS is a full-scope and partial replica simulator.Its scope includes a complete set of plant normal evolutions and malfunctions obtained from the plant design basis accidents list.All the systems necessary to implement the operating procedures associated to these transients are included.Within these systems both the variables connected to the plant SCADA and the local variables are modelled, leading to several thousands input-output variables in the plant mathematical model (PMM).The trainee interacts with the same plant SCADA, a Foxboro I/A Series system.Control room hardware is emulated through graphical displays with touch-screen.The main system models were tested against RELAP outputs.The RTS includes several modules: a model manager (MM) that encapsulates the plant mathematical model; a simulator human machine interface, where the trainee interacts with the plant SCADA; and an instructor console (IC), where the instructor commands the simulation.The PMM is built using Matlab-Simulink with specific libraries of components designed to facilitate the development of the nuclear, hydraulic, ventilation and electrical plant systems models

  10. SIMULATE-3 core model for nuclear reactor training simulators

    International Nuclear Information System (INIS)

    This paper describes the adaptation of the Studsvik nuclear reactor analysis code, SIMULATE-3, to nuclear reactor training simulation. This adaption to real-time applications permits training simulation to be performed using the same 'engineering grade' core model used for core design, loading optimisation, safety analysis, and plant technical support. Use of SIMULATE-3R in training simulation permits simple initialisation of simulator core-models (without need for tuning) and facilitates application of cycle-specific core models. SIMULATE-3R permits training simulation of reactor cores with the accuracy normally associated with engineering analysis and enhances the simulator's 'plant analyser' functions. (author)

  11. Use of the VR-1 ''Vrabec'' training reactor

    International Nuclear Information System (INIS)

    An overview is presented of the extent and ways of using the VR-1 training reactor, which is operated by the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. A list and the characteristics of 16 problems developed for teaching purposes is given, and the 14 faculties and 2 research institutes participating in the teaching activities are listed. The reactor is used in the education and training of nuclear scientists and engineers. The instrumentation, experimental, handling and operating tools, as well as documentation and texts relating to the reactor are described. The following examples of the teaching activities are included: a guided visit to the operating reactor site, reactor dynamics study and delayed neutron measurement, training course, and the basic criticality experiment. Nuclear safety aspects (hypothetical accidents, quality control and system qualification demonstration, safety culture) are stressed during the education. The reactor department is involved in international cooperation projects. (J.B.). 3 refs

  12. Boiling water reactor operator training and qualification in Japan

    International Nuclear Information System (INIS)

    Nuclear power plant operators in Japan are individuals employed by each electric power company. A recruit goes through his company's training; afterwards, he is given a qualification rating and is assigned to practical duty. The only formal qualification authorized by the Japanese government is the full-fledged shift supervisor. Other classifications such as assistant shift supervisor, shift foreman, reactor operator, and subreactor operator are all designated and appointed by each company's in-house regulations. As a part of the training system, power companies that require the use of a full-scope simulator in their training programs utilize the boiling water reactor (BWR) and pressurized water reactor operator training centers. Both were set up independently of the power companies. A synopsis of the BWR Operator Training Center Corp. (BTC ) and its training systems, features, performance evaluation, curriculum improvement, and related items is presented

  13. Investigation of neutron distribution in training reactor VR-1

    International Nuclear Information System (INIS)

    The VR-1 training reactor is a pool-type light-water reactor with the low-enriched uranium and maximum thermal power of 1 kW. The reactor is mainly used for students' training. The training is aimed to areas such as the reactor physics, neutronics, dosimetry, nuclear safety and I and C systems. Since neutron flux in the VR-1 core is well measured, this work focuses on one part of the reactor - its Radial experimental Channel (RC). This paper deals with the measurement of the neutron distribution by means of gold-foil neutron-activation technique and continual measurement with 3He-filled detector. Obtained experimental results were verified with the simulation in the Monte-Carlo N-Particle Transport Code. Results and conclusions from this paper will be used for further investigation of neutrons and their spatial distribution inside the low-power training reactor. Also, the data obtained in this paper can be used as a basis for future detailed measurements of neutron flux and its distribution in other hard accessible areas inside the reactor. The paper gives a simple theoretical introduction concerning neutron measurement procedures and available techniques in this field, which is particularly important for improving training courses and a content of offered experiments in the VR-1 reactor. (author)

  14. IAEA Activities supporting education and training at research reactors

    International Nuclear Information System (INIS)

    Full-text: Through the provision of neutrons for experiments and their historical association with universities, research reactors have played a prominent role in nuclear education and training of students, scientists and radiation workers. Today education and training remains the foremost application of research reactors, involving close to 160 facilities out of 246 operational. As part of its mandate to facilitate and expand the contribution of atomic energy to peace, health and prosperity throughout the world, the IAEA administers a number of activities intended to promote nuclear research and enable access to nuclear technology for peaceful purposes, one of which is the support of various education and training measures involving research reactors. In the last 5 years, education and training has formed one pillar for the creation of research reactor coalitions and networks to pool their resources and offer joint programmes, such as the on-going Group Fellowship Training Course. Conducted mainly through the Eastern European Research Reactor Initiative, this programme is a periodic sic week course for young scientists and engineers on nuclear techniques and administration jointly conducted at several member research reactor institutes. Organization of similar courses is under consideration in Latin America and the Asia-Pacific Region, also with support from the IAEA. Additionally, four research reactor institutes have begun offering practical education courses through virtual reactor experiments and operation known as the Internet Reactor Laboratory. Through little more than an internet connection and projection screens, university science departments can be connected regionally or bilaterally with the control room o a research reactor for various training activities. Finally, two publications are being prepared, namely Hands-On Training Courses Using Research Reactors and Accelerators, and Compendium on Education and training Based on Research Reactors. These

  15. Education of students and experts and personnel preparation on training reactor VR-1

    International Nuclear Information System (INIS)

    The paper describes main purposes in the training reactor VR-1 operation. It also gives a typical schedule for one week training course in reactor physics and kinetics, which is organised at the VR-1 reactor

  16. Approach to training the operators of WWER-440 reactors

    International Nuclear Information System (INIS)

    The paper has three parts. (1) Personnel Training and Qualifications (2) Description of Kozloduy NPP Training and Qualification System (TQS) built in the last 7 years and its interfaces with the Certification System and (3) Application of the TQS for the Senior Reactor Operator (SRO). (author)

  17. Jordan Research and Training Reactor (JRTR) Utilization Facilities

    International Nuclear Information System (INIS)

    Jordan Research and Training Reactor (JRTR) is a 5 MW light water open pool multipurpose reactor that serves as the focal point for Jordan National Nuclear Centre, and is designed to be utilized in three main areas: Education and training, nuclear research, and radioisotopes production and other commercial and industrial services. The reactor core is composed of 18 fuel assemblies, MTR plate type 19.75% enriched uranium silicide (U3Si2) in aluminium matrix, and is reflected on all sides by beryllium and graphite. The reactor power is upgradable to 10 MW with a maximum thermal flux of 1.45×1014 cm-2s-1, and is controlled by a Hafnium control absorber rod and B4C shutdown rod. The reactor is designed to include laboratories and classrooms that will support the establishment of a nuclear reactor school for educating and training students in disciplines like nuclear engineering, reactor physics, radiochemistry, nuclear technology, radiation protection, and other related scientific fields where classroom instruction and laboratory experiments will be related in a very practical and realistic manner to the actual operation of the reactor. JRTR is designed to support advanced nuclear research as well as commercial and industrial services, which can be preformed utilizing any of its 35 experimental facilities. (author)

  18. Training and qualification of reactor operating personnel in Indonesia

    International Nuclear Information System (INIS)

    Full text: For operating nuclear reactor is needed reactor personnel. Nuclear installation operating organization should ensure that reactor personnel in charge have fulfilled the requirement to operate nuclear reactor. The personnel who operates or supervise the process of reactor operation or personnel who concern directly related safety should have license. Any employee who operates a nuclear reactor and any special employee in other nuclear installation and in the installations that use ionising radiation sources shall possess a license. This working license is issued by Nuclear Energy Control Board - Bapeten in accordance with the Act No. 10 year 1997 on Nuclear Energy in article 19 clause. To implement the Act Bo. 10/1997 especially relating to the personnel who operates a nuclear reactor in Indonesia has enacted the guidance which is required by operator/supervisor to fulfil the requirement for receiving license to nuclear installation and ionization radiation utilization installation in decree of Bapeten Chairman No. 17/Ka-Bapeten/IX-99. For proving his qualification, the operator/supervisor should take the training and testing/examination. The Decree of Bapeten Chairman No. 04P/Ka-Bapeten/I-03 can be concluded that reactor personnel should follows training and qualification is arranged by accredited training course organization. After passing the training course, he can flow the examination which is arranged by Bapeten to receive the working license issued by Bapeten suitable his profession. This paper discuss about the provision in guidance of training and qualification of reactor operation personnel and the requirement of the exam participant for receiving of working license of nuclear installation in Indonesia. (author)

  19. A three-dimensional neutronics model for reactor training simulators

    International Nuclear Information System (INIS)

    A training simulator that duplicates a Savannah River Plant (SRP) reactor control room is currently under construction. Because of the complexity of the SRP reactor control and instrumentation systems, a multinode neutronics model is necessary in order to simulate the reactor core behavior. A 240-node core model, using a semi-implicit (SI) solution technique, has been developed to fill that need. The SI model has been tested with a range of transients and is found to provide an accurate simulation with the potential of running significantly faster than real time on the reactor simulator minicomputer complex

  20. Status of Jordan Research and Training Reactor Project

    International Nuclear Information System (INIS)

    The Jordan Atomic Energy Commission launched a construction project of Jordan's first nuclear reactor in 2010, following a contract with the consortium of Korea Atomic Energy Research Institute and Daewoo E and C. The Jordan Research and Training Reactor (JRTR), a 5 MW multipurpose research reactor, will serve as the focal point for a national nuclear technology center. This article presents the status of the JRTR Project and future plan as well. With the Construction Permit issued by the Jordan Nuclear Regulatory Commission, the construction work of reactor building and service building is underway, while over 95% of design work has been finished

  1. RELAP/SCDAPSIM Reactor System Simulator Development and Training for University and Reactor Applications

    International Nuclear Information System (INIS)

    The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of an international nuclear technology development program called SDTP (SCDAP Development and Training Program). SDTP involves more than 60 organizations in 28 countries. One of the important applications of the code is for simulator training of university faculty and students, reactor analysts, and reactor operations and technical support staff. Examples of RELAP/SCDAPSIM-based system thermal hydraulic and severe accident simulator packages include the SAFSIM simulator developed by NECSA for the SAFARI research reactor in South Africa, university-developed simulators at the University of Mexico and Shanghai Jiao Tong University in China, and commercial VISA and RELSIM packages used for analyst and reactor operations staff training. This paper will briefly describe the different packages/facilities. (authors)

  2. New human machine interface for VR-1 training reactor

    International Nuclear Information System (INIS)

    The contribution describes a new human machine interface that was installed at the VR-1 training reactor. The human machine interface update was completed in the summer 2001. The human machine interface enables to operate the training reactor. The interface was designed with respect to functional, ergonomic and aesthetic requirements. The interface is based on a personal computer equipped with two displays. One display enables alphanumeric communication between a reactor operator and the control and safety system of the nuclear reactor. Messages appear from the control system, the operator can write commands and send them there. The second display is a graphical one. It is possible to represent there the status of the reactor, principle parameters (as power, period), control rods' positions, the course of the reactor power. Furthermore, it is possible to set parameters, to show the active core configuration, to perform reactivity calculations, etc. The software for the new human machine interface was produced in the InTouch developing environment of the WonderWare Company. It is possible to switch the language of the interface between Czech and English because of many foreign students and visitors at the reactor. The former operator's desk was completely removed and superseded with a new one. Besides of the computer and the two displays, there are control buttons, indicators and individual numerical displays of instrumentation there. Utilised components guarantee high quality of the new equipment. Microcomputer based communication units with proper software were developed to connect the contemporary control and safety system with the personal computer of the human machine interface and the individual displays. New human machine interface at the VR-1 training reactor improves the safety and comfort of the reactor utilisation, facilitates experiments and training, and provides better support of foreign visitors.(author)

  3. Recent trends in urban renewal in Budapest

    Directory of Open Access Journals (Sweden)

    Gábor Csanádi

    2010-01-01

    Full Text Available This article outlines recent social processes in central Budapest, focusing on social sustainability and gentrification, and presents the potential social conflicts emerging in this area. We examine the recent history of the housing market and areas of gentrification in the city centre. The second part of the article presents the trends and possible long-term effects of real-estate development in the research area. The article concludes that the gentrification events in central Budapest could be a warning signal of future social displacement and social exclusion.

  4. Mitigating reactor incidents through performance-based training

    International Nuclear Information System (INIS)

    The Advanced Test Reactor (ATR), located at the Idaho National Engineering Laboratory, is operated for the Department of Energy by EG and G Idaho, Inc. The ATR is a 250 MW research reactor. Its primary mission is to support DOE research on fuel and material irradiation. In addition, limited space at the ATR is available to industry for materials irradiation and radioactive isotopes production. The training of operating personnel is as important as any other component of reactor safety. The question of what exactly these operators need to know in order to accurately and quickly recognize and respond to system malfunctions is extremely important and sometimes difficult to specifically identify. The use of a performance based training system combined with learning from the past experiences are currently the best tools available. The purpose of this paper is to present ATR's approach to performance based training

  5. Nuclear renaissance in the reactor training of Areva

    International Nuclear Information System (INIS)

    Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPRTM, giving a detailed presentation of the EPRTM reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported effectively by tools

  6. Nuclear renaissance in the reactor training of Areva

    Energy Technology Data Exchange (ETDEWEB)

    De Braquilanges, Bertrand [Reactor Training Center/France Manager, La Tour Areva - 1, place Jean Millier - 92084 Paris - La Defense (France); Napior, Amy [Reactor Training Center/USA Manager, 1300 Old Graves Mill Road - Lynchburg VA, 2450 (United States); Schoenfelder, Christian [Reactor Training Center/Germany Manager, Kaiserleistrasse 29 - 63067 Offenbach (Germany)

    2010-07-01

    Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPR{sup TM}, giving a detailed presentation of the EPR{sup TM} reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported

  7. Utilization of research and training reactors in the study program of students at Slovak University of Technology

    International Nuclear Information System (INIS)

    technologies, but also to travel to perform practical exercises at foreign training or experimental reactors as: TRIGA II Reactor in Atomic Institute of the Austrian Universities, Vienna, Austria (3 practical exercises per study for about 10 students yearly since 1990); School Reactor of the Technical University of Budapest, Hungary (one week per study, about 10 students yearly since 1983); Training Reactor of the CVUT, Prague, Czech Republic (3 days per study, about 10 students yearly since 1998); Experimental reactor ASTRA in Austrian Research Center Seibersdorf (1999-2000) A 4 weeks' IAEA Regional Training Course 'Safety management and utilisation of research reactors' on Safety, Management and Utilization of Research Reactors was held in Bratislava (Slovakia) and Vienna (Austria) during March 05-30th 2001. IAEA in co-operation with the Department of Nuclear Physics and Technology of the Slovak University of Technology and the Atominstitut of Austrian Universities Vienna prepared and realized this training course with the aim to train junior staff from research reactors in various aspects of safety, management and utilization of research reactors. All participants had to have at least 4 years experiences in operation, management, utilization or regulation of research reactors. Lectures covered the topics in nuclear design and operation, neutron physics, reactor physics, health physics, dosimetry, reactor instrumentation, fuel management decontamination procedures, preparation of experiments at research reactors and others. Beside theoretical part of the course, the practical exercises at TRIGA II reactor in Vienna constituted an important part of training. ENEN - European Nuclear Education Network: Feasibility Study for Central-European Region. In frame of this project, prepared for the Central-European region, students participating in nuclear engineering education will visit participating institute to carry out laboratory practices and student as well as diploma work. We

  8. Use of research reactors for training and teaching nuclear sciences

    International Nuclear Information System (INIS)

    Training activities on reactors are organized by Cea on 2 specially dedicated reactors Ulysse (Saclay) and Siloette (Grenoble) and 2 research reactors Minerve (Cadarache) and Azur (Cadarache, facility managed by Technicatome). About 4000 students have been trained on Ulysse since its commissioning more than 40 years ago. The concept that led to the design of Ulysse was to build a true reactor dedicated to teaching and training activities and that was able to operate with great flexibility and under high conditions of safety, this reactor is inspired from the Argonaut-type reactor. The main specificities of Ulysse are: a nominal power of 100 kW, a maximal thermal neutron flux of 1.4 1012 n.cm-2.s-1, a 90 % enriched fuel, a graphite reflector, the use of water as coolant and moderator, and 6 cadmium plates as control rods. Ulysse allows students to get practical experience on a large range of topics: approach to criticality, effect of the starting neutron source, calibration of control rods, distribution of the neutron flux in the thermal column, temperature coefficient, radiation detectors, neutron activation analysis, and radioprotection. (A.C.)

  9. U.S. NRC training for research and training reactor inspectors

    International Nuclear Information System (INIS)

    Currently, a large number of license activities (Early Site Permits, Combined Operating License, reactor certifications, etc.), are pending for review before the United States Nuclear Regulatory Commission (US NRC). Much of the senior staff at the NRC is now committed to these review and licensing actions. To address this additional workload, the NRC has recruited a large number of new Regulatory Staff for dealing with these and other regulatory actions such as the US Fleet of Research and Test Reactors (RTRs). These reactors pose unusual demands on Regulatory Staff since the US Fleet of RTRs, although few (32 Licensed RTRs as of 2010), they represent a broad range of reactor types, operations, and research and training aspects that nuclear reactor power plants (such as the 104 LWRs) do not pose. The US NRC must inspect and regulate all these entities. This paper addresses selected training topics and regulatory activities provided US NRC Inspectors for US RTRs. (author)

  10. Teaching and training at the RA-6 reactor

    International Nuclear Information System (INIS)

    The RA-6 research reactor is owned and operated by the National Atomic Energy Commission (CNEA) of Argentina. It is located at the Bariloche Atomic Center, Bariloche (Argentina). The reactor was entirely designed and built in Argentina and it has operated since October 1982. The main design goal was for a training reactor to support nuclear engineering education. Moreover, CNEA wanted to own a plant suitable for nuclear experiments to be performed for its Nuclear Engineering Department. To further support the role of the RA-6 as a plant comprehensively providing facilities for training and education and for experimental work, the irradiation facilities initially included in the reactor design were improved, focusing on specific interests. The appropriate personnel involvement together with student's cooperation allowed different grades of development and improvement to be achieved. Facilities involved in that process were: - Neutron Activation Analysis Laboratory (LAAN); - Boron neutron capture therapy (BNCT) facility; - Neutron radiography facility, which was designed as an academic tool mainly for teaching and training purposes, but also for industrial services; - Prompt gamma neutron activation analysis (PGNAA), designed for academic purposes and being upgraded in the framework of the current IAEA project 'New Applications on PGNAA'. The RA-6 will remain a plant capable of providing excellent capabilities and facilities for education and training

  11. Argonaut type reactor for the best possible Phase Ia training of nuclear plant operators

    International Nuclear Information System (INIS)

    The Argonaut type reactor is an excellent training tool for the training of Electric Utility Nuclear Plant Operators. The training advantages of this type of reactor can best be seen by comparing its design characteristics to a typical large pressurized water reactor and other research/training reactors not necessary for reactor operator training are explained. Some minor modifications of the Argonaut at UCLA would prove valuable and are under consideration. A complete one week Phase Ia training program proposal has been made by UCLA to selected utilities and a summary of this program is presented

  12. Lessons learned from the spent fuel shipment Budapest - Mayak

    International Nuclear Information System (INIS)

    The largest shipment yet of Russian-origin spent nuclear fuel (about 130 kgs HEU and 100 kgs LEU) arrived to the Mayak facility on October 22, 2008. All 16 available Skoda VPVR/M type casks were used, in 8 20 feet ISO containers. The containers were transported on trucks, on rail and on sea. The nuclear fuel was used in the Budapest Research Reactor between 1959 and 2005. The preparations of the shipment started in 2004. Technical works progressed well all the time, the administrative part caused much more difficulties. The paper gives an overview of the activities and tries to find the points where more attention could be necessary. Future shipments can be prepared and performed easier based on the lessons learned. The paper is illustrated by pictures, the authors have taken during the events. (author)

  13. Radiation protection personnel training in Research Reactors; Capacitacion en proteccion radiologica para reactores de investigacion

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, Carlos Dario; Lorenzo, Nestor Pedro de [Comision Nacional de Energia Atomica, Rio Negro (Argentina). Centro Atomico Bariloche. Instituto Balseiro

    1996-07-01

    The RA-6 research reactor is considering the main laboratory in the training of different groups related with radiological protection. The methodology applied to several courses over 15 years of experience is shown in this work. The reactor is also involved in the construction, design, start-up and sell of different installation outside Argentina for this reason several theoretical and practical courses had been developed. The acquired experience obtained is shown in this paper and the main purpose is to show the requirements to be taken into account for every group (subjects, goals, on-job training, etc) (author)

  14. Training reactor deployment. Advanced experimental course on designing new reactor cores

    International Nuclear Information System (INIS)

    Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

  15. Operation characteristics and conditions of training reactor VR-1

    International Nuclear Information System (INIS)

    The first 3 years of operation of the VR-1 training reactor are reviewed. This period includes its physical start-up (preparation, implementation, results) and operation development as far as the current operating configuration of the reactor core. The physical start-up was commenced using a reactor core referred to as AZ A1, whose physical parameters had been verified by calculation and whose configuration was based on data tested experimentally on the SR-0 reactor at Vochov. The next operating core, labelled AZ A2, was already prepared during the test operation of the VR-1 reactor. Its configuration was such that both of the main horizontal channels, radial and tangential, could be employed. The configuration that followed, AZ A3, was an intermediate step before testing the graphite side reflector. The current reactor core, labelled AZ A3 G, was obtained by supplementing the previous core with a one-sided graphite side reflector. (Z.S.). 2 tabs., 11 figs., 2 refs

  16. Hands-on Training Courses Using Research Reactors and Accelerators

    International Nuclear Information System (INIS)

    The enhancement of nuclear science education and training in all Member States is of interest to the IAEA since many of these countries, particularly in the developing world, are building up and expanding their scientific and technological infrastructures. Unfortunately, most of these countries still lack sufficient numbers of well-educated and qualified nuclear specialists and technologists. This may arise from, amongst other things: a lack of candidates with sufficient educational background in nuclear science who would qualify to receive specialized training; a lack of institutions available for training nuclear science specialists; a lack of lecturers in nuclear related fields; and a lack of suitable educational and teaching materials. A related concern is the potential loss of valuable knowledge accumulated over many decades due to the ageing workforce. An imperative for Member States is to develop and offer suitable graduate and postgraduate academic programmes which combine study and project work so that students can attain a prerequisite level of knowledge, abilities and skills in their chosen subject area. In nearly all academic programmes, experimental work forms an essential and integral component of study to help students develop general and subject specific skills. Experimental laboratory courses and exercises can mean practical work in a conventional laboratory or an advanced facility with an operational particle accelerator or research reactor often accompanied by computer simulations and theoretical exercises. In this context, available or newly planned research reactors and particle accelerators should be seen as extremely important and indispensable components of nuclear science and technology curricula. Research reactors can demonstrate nuclear science and technology based on nuclear fission and the interaction of neutrons and photons with matter, while particle accelerators can demonstrate nuclear science and technology based on charged particle

  17. El turismo oscuro. Estudio de caso: Budapest

    OpenAIRE

    Rodríguez Cifuentes, Sara

    2016-01-01

    Este trabajo fin de grado trata de explicar que es el turismo oscuro y que engloba. Para ello, en primer lugar, se da una definición de turismo cultural y una razón de porqué el turismo oscuro pertenece al turismo cultural. Después, se centra en un periodo de la historia muy significativo: la segunda guerra mundial. A partir de ahí, se relaciona el turismo oscuro con el holocausto. Para finalizar el trabajo, se investigan todos los incentivos turísticos acerca del tema principal en Budapest (...

  18. Reactor Simulator Development Facility for Operating Personnel Training

    International Nuclear Information System (INIS)

    A reactor simulator development facility (FARSim) for operator training is presented. This facility is a software product that can be divided into four main modules: the model manager (MM), the simulator human machine interface (SHMI), the instructor station (IS) and the simulation manager (SM). It is designed as a distributed system where each module takes charge of a specific simulator task that could run in the same computer or distributed in a computer network. The main module is the SM which is responsible for routing the messages between the other modules and managing the simulation. The MM interfaces to the plant mathematical model (PMM). The IS is the process where the instructor commands the simulation, performing tasks such as start, pause and stop the simulation. The SHMI is the interface with the simulator SCADA (which can be identical to the plant SCADA) and is used by the trainee to observe the simulated plant output and to act upon it. The PMM is built using Matlab-Simulink simulation engine and graphical design user interface, for which specific libraries have been developed with a comprehensive set of nuclear and thermohydraulic plant components. This simulator development facility is being used to develop the ANSTO replacement research reactor full-scope and partial replica reactor training simulator (RTS). (author)

  19. Training of operators in the Portuguese Research Reactor

    International Nuclear Information System (INIS)

    Full text: The Portuguese Research Reactor (RPI) is a pool-type 1 MW reactor designed by AMF Atomics and built during the period of 1959/61. Like in many other small and medium power research reactors, the continuation of its operation depends on four factors: active users, ageing of the installation, availability of fuel and, last but not least, ageing of the operating staff. Back in 1997 the RPI had only four licensed operators, with two of them close to retirement age. A new two-year training course was started in October 1997 with 13 candidates. Funding was granted from the Portuguese Science and Technology Foundation for the duration of the course. The trainees were selected among people with at least 12 years of school (high school diploma) and with technical courses in the areas of chemistry, mechanics or electronics. In addition to standard selection procedures, all candidates were subjected to psychological tests. It was decided from the beginning that the new operators would have a broader training than previously. On one hand the decrease in the number of support technicians has made it necessary for the operators to perform tasks which were not traditionally theirs and required specific training - e.g., preparation of samples to irradiate, maintenance of the control system, control of activity of water samples. On the other hand, the presence of an initially large number of trainees made it necessary to have a large number of well defined chores or guided work for small groups - this led to a 'natural' distribution and rotation of the trainees through all the activities in the reactor, including research activities. The course comprised a 1st semester of class lectures, followed by a written exam. In the 2nd semester there were several facility-walk through to specific systems - e.g. ventilation, control system, followed by specific chores or guided work in the systems. All trainees participated in the annual maintenance, which was longer than usual to

  20. Proceedings of the Budapest workshop on relativistic heavy ion collisions

    International Nuclear Information System (INIS)

    This volume is the Proceedings of the Budapest workshop on relativistic heavy ion collisions held in Budapest, 10-13 Aug, 1992. The topics include experimental heavy ion physics, Bose-Einstein correlations, intermittency, relativistic transport theory, Quark-Gluon Plasma rehadronization, astronuclear physics and cosmology. All contributions were indexed and abstracted. (author)

  1. Major Refurbishment of the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time

  2. Pilot program: NRC severe reactor accident incident response training manual: Severe reactor accident overview

    International Nuclear Information System (INIS)

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Severe Reactor Accident Overview is the second in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assesment. Each volume serves, respectively, as the text for a course of instruction in a series of courses. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  3. A small-scale experimental reactor combined with a simulator for training purposes

    International Nuclear Information System (INIS)

    The authors discuss how a small-scale reactor combined to a training simulator can be a valuable aid in all forms of training. They describe the CEN-based SILOETTE reactor in Grenoble and its combined simulator. They also take a look at prospects for the future of the system in the light of experience acquired with the ARIANE reactor and the trends for the development of simulators for training purposes

  4. ELECTRA: A European Lead-bismuth Cooled Training Reactor

    International Nuclear Information System (INIS)

    The lack of low power liquid metal cooled reactors has meant that few engineers within the nuclear power industry and research community are familiar with operational procedures of this family of coolants, expected to be used for Generation IV fast neutron systems. The reasons for this lack may include safety issues related to use of Mercury, NaK or sodium as applied in early low power reactors. Especially in western Europe, no low power liquid metal cooled reactor was ever in operation. Here, we present the design of a 2 MWth lead-bismuth cooled reactor with (Pu,Zr)N fuel, relying on natural convection for full power operation. The combination of low power density with natural convection for heat removal makes the reactor ideal for training purposes. The large thermal expansion of heavy liquid metals makes is possible to design low power fast neutron reactors relying on natural convection. Since at present, there exists no suitable material for pumps operating at high velocity in lead alloy environments, the only possible short term solution for constructing such a reactor is anyway to design for 100% natural circulation of the coolant. For this purpose, a small core height, a large difference between coolant inlet and outlet temperatures and a low coolant velocity is desired. By application of (Pu,Zr)N fuel, criticality can be achieved with a fissile inventory of 100 kg LWR grade plutonium. Monte Carlo simulations show that 19 hexagonal fuel assemblies, each with 91 fuel pins having an outer diameter of 1.1 cm, and an active height of 15 cm is sufficient to obtain a critical core. Including end pellets, gas plenum and end caps, the total core height is limited to 30 cm. Adopting P/D = 1.25 and a heat exchanger elevation of 4 m, it is found that 2 MW of thermal power may be removed by a natural circulation velocity of 0.4 m/s. This corresponds to a linear rating of 8 kW/m and a temperature increase of the coolant equal to 240 degrees. Limiting the clad temperature

  5. Equipment for neutron measurements at VR-1 Sparrow training reactor

    International Nuclear Information System (INIS)

    Full text: The VR-1 Sparrow training reactor is the experimental nuclear facility especially employed for education and teaching of students from different technical universities in the Czech Republic and other countries. Since 2005 the uniform all-purpose devices EMK310 have been used for measurement at reactor laboratory with different type of gas filled neutron detectors. The neutron detection system are employed for reactivity measurement, control rod calibration, critical experiment, study of delayed neutrons, study of nuclear reactor dynamics and study of detection systems dead time. The small dimension isotropic detectors are especially used for measurement of thermal neutron flux distribution inside the reactor core. The EMK-310 is a high performance, portable, three-channel fast amplitude analyzer designed for counting applications. It was developed for nuclear applications and made in close co-operation with firm TEMA Ltd. The precise rack eliminates electromagnetic disturbance and contains the control unit and four modules. The modules of high voltage supply and amplifier for gas filled detectors or scintillation probes are used in basic configuration. Software is tailored specifically to the reactor measurement and allows full online control. For applications involving the study of signals that may vary with the time, example study of delayed neutrons or nuclear reactor dynamics, the EMK-310 provides a Multichannel Scaling (MCS) acquisition mode. MCS dwell time can be set from 2 ms. Now, the new generation of digital multichannel analyzers DA310 is introduced. They have similarly attributes as EMK310 but the output information of unipolar signals from detector is more complete. The pipeline A/D converter with field programmable gate array (FPGA) is the hearth of the DA310 device. The resolution is 12 bits (4096 channels); the sample frequency is 80 MHz. The application for the neutron noise analysis is supposed. The correction method for non linearity

  6. A research reactor simulator for operators training and teaching

    International Nuclear Information System (INIS)

    This work describes a training simulator of Research Reactors (RR). The simulator is an interactive tool for teaching and operator training of the bases of the RR operation, reactor physics and thermal hydraulics. The Brazilian IEA-R1 RR was taken as the reference (default configuration). The implementation of the simulator consists of the modeling of the process and system (neutronics, thermal hydraulics), its numerical solution, and the implementation of the man-machine interface through visual interactive screens. The point kinetics model was used for the nuclear process and the heat and mass conservation models were used for the thermal hydraulic feed back in the average core channel. The heat exchanger and cooling tower were also modeled. The main systems were: the reactivity control system, including the automatic control, and the primary and secondary coolant systems. The Visual C++ was used to codes and graphics lay-outs. The simulator is to be used in a PC with Windows XP system. The simulator allows simulation in real time of start up, power maneuver, and shut down. (authors)

  7. Upgrade of VR-1 training reactor I and C

    International Nuclear Information System (INIS)

    The contribution describes the upgrade of the VR-1 training reactor I and C (Instrumentation and Control). The reactor was put into operation in the 1990, and its I and C seems to be obsolete now. The new I and C utilises the same digital technology as the old one. The upgrade has been done gradually during holidays in order not to disturb the reactor utilisation during teaching and training. The first stage consisted in the human-machine interface and the control room upgrade in 2001. A new operator's desk, displays, indicators and buttons were installed. Completely new software and communication interface to the present I and C were developed. During the second stage in 2002, new control rod drivers and safety circuits were installed. The rod motors were replaced and necessary mechanical changes on the control rod mechanism, induced by the utilisation of the new motor, were done. The new safety circuits utilise high quality relays with forced contacts to guarantee high reliability of their operation. The third stage, the control system upgrade is being carried out now. The new control system is based on an industrial PC mounted in a 19 inch crate. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. A large amount of work has been devoted to the software requirements to specify all dependencies, modes and permitted actions, safety measures, etc. The Department took an active part in the setting of software requirements and later in verification and validation of the software and the whole control system. Finally, a new protection system consisting of power measuring and power protection channels will be installed in 2004 or 2005. (author)

  8. Eastern Europe Research Reactor Initiative nuclear education and training courses - Current activities and future challenges

    International Nuclear Information System (INIS)

    The Eastern Europe Research Reactor Initiative was established in January 2008 to enhance cooperation between the Research Reactors in Eastern Europe. It covers three areas of research reactor utilisation: irradiation of materials and fuel, radioisotope production, neutron beam experiments, education and training. In the field of education and training an EERRI training course was developed. The training programme has been elaborated with the purpose to assist IAEA Member States, which consider building a research reactor (RR) as a first step to develop nuclear competence and infrastructure in the Country. The major strength of the reactor is utilisation of three different research reactors and a lot of practical exercises. Due to high level of adaptability, the course can be tailored to specific needs of institutions with limited or no access to research reactors. (authors)

  9. Recent developments of prompt gamma activation analysis at Budapest

    International Nuclear Information System (INIS)

    The PGAA facility at the Budapest Research Reactor has been continually upgraded and developed since its start-up in 1996, as a result of which its performance has improved considerably. The installation of the cold neutron source, the partial change to supermirror neutron guides and their realignment increased the flux by almost two orders of magnitude. The data acquisition has been modernized as well; digital spectrometers were tested and implemented in novel forms of gamma-ray spectrum collection. This year a higher-efficiency HPGe detector and a new data acquisition module were put into operation. Most recently all the neutron guides were changed to supermirror-coated ones to further increase the neutron flux. The improved evaluation software makes possible a more reliable elemental analysis of the samples. In this progress report these developments are critically reviewed. The characteristics of the latest system are also described. It is the first time that a set of new partial gamma-ray production cross sections are presented, which are based on the new intensity values of 14N(n,γ)15N calibration standard. (author)

  10. Simulation of severe accident in reactor core for training and accident management

    International Nuclear Information System (INIS)

    An Advanced Real-time Severe Accident Simulation (ARTSAS) train reactor operators and accident management teams for scenarios simulating severe accidents in nuclear reactors. The code has been integrated with the real-time tools and the RAINBO graphic package to provide training and analysis tools on workstations as well as on full-scope simulators. (orig.) (4 refs., 1 fig.)

  11. Education and research at the VR-1 Vrabec training reactor facility

    International Nuclear Information System (INIS)

    The results of 12 years' efforts devoted to the construction of the VR-1 ''Vrabec'' training reactor at the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague and to establishing the training reactor department, as well as the contribution of the training reactor facility to the teaching and scientific activities of the Faculty are presented in a comprehensive manner. The thesis is divided into 2 parts: (i) preconditions, reactor construction and commissioning, and constituting the reactor department, and (ii) basic and comprehensive information concerning the current utilization of the reactor for the benefit of students from various university level institutions. The prospects of scientific activities of the department are also outlined. Attention is paid to selected nuclear safety aspects of the reactor during operation and teaching of students, as well as to its innovated digital control system whose implementation is planned. The results achieved are compared with the initial goals and with similar experience abroad. (P.A.)

  12. The design and use of proficiency based BWR reactor maintenance and refuelling training mockups

    International Nuclear Information System (INIS)

    The purpose of this paper is to describe the ABB experience with the design and use of boiling water reactor training facilities. The training programs were developed and implemented in cooperation with the nuclear utilities. ABB operates two facilities, the ABB ATOM Light Water Reactor Service Center located in Vasteras, Sweden, and the ABB Combustion Engineering Nuclear Operations BWR Training Center located in Chattanooga, Tennessee, USA. The focus of the training centers are reactor maintenance and refueling activities plus the capability to develop and qualify tools, procedures and repair techniques

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

    International Nuclear Information System (INIS)

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

  14. Experiences on Jordan Research and Training Reactor Licensing

    International Nuclear Information System (INIS)

    The Jordan Atomic Energy Commission (JAEC) commenced the Jordan Research and Training Reactor Project (tentatively called JRTR Project hereinafter) in January 2009. The Korea Atomic Energy Research Institute (KAERI) and Daewoo Engineering and Construction Co. established the KAERI/Daewoo Consortium (KDC) and signed a contract on March 30, 2010 with Jordan to build the Middle Eastern country's first nuclear research reactor. Owing to an insufficient regulatory infrastructure in Jordan, the JNRC (Jordan Nuclear Regulatory Commission) determined to cooperate with Korea Institute of Nuclear Safety (KINS) to support the regulation on the construction and operation of the JRTR. On Aug. 15, 2013, the JNRC issued a Construction Permit (CP) for the JRTR and at the end of this year, KDC will apply for an Operating License (OL). In this paper, the Jordanian regulatory framework and the experiences on the JRTR CP licensing will be discussed. The cooperation between the JNRC and KINS on the JRTR CP review process is a good model of international cooperation on nuclear regulations. Moreover, the experiences on the JRTR licensing will be a good lesson to those countries that plan to introduce a nuclear program, but do not have a sufficient regulatory infrastructure. Additionally, the understandings on the differences and resemblances between the US and European regulatory philosophies on nuclear safety are needed for countries that plan to introduce a nuclear program. These understandings are also needed for the nuclear facility suppliers. The licensing process, applicable regulatory standards and guidelines shall be clearly stated in written form under the contract conditions. If not, unpredictable variables from the difference between US and European regulatory standards may cause a delay in the project schedule. In the case of the JRTR project, clearly-stated licensing process, applicable regulatory standards and guidelines on the contract conditions minimized the delay

  15. Experiences on Jordan Research and Training Reactor Licensing

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Yong Se; Lee, Hyun do; Choi, Min Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The Jordan Atomic Energy Commission (JAEC) commenced the Jordan Research and Training Reactor Project (tentatively called JRTR Project hereinafter) in January 2009. The Korea Atomic Energy Research Institute (KAERI) and Daewoo Engineering and Construction Co. established the KAERI/Daewoo Consortium (KDC) and signed a contract on March 30, 2010 with Jordan to build the Middle Eastern country's first nuclear research reactor. Owing to an insufficient regulatory infrastructure in Jordan, the JNRC (Jordan Nuclear Regulatory Commission) determined to cooperate with Korea Institute of Nuclear Safety (KINS) to support the regulation on the construction and operation of the JRTR. On Aug. 15, 2013, the JNRC issued a Construction Permit (CP) for the JRTR and at the end of this year, KDC will apply for an Operating License (OL). In this paper, the Jordanian regulatory framework and the experiences on the JRTR CP licensing will be discussed. The cooperation between the JNRC and KINS on the JRTR CP review process is a good model of international cooperation on nuclear regulations. Moreover, the experiences on the JRTR licensing will be a good lesson to those countries that plan to introduce a nuclear program, but do not have a sufficient regulatory infrastructure. Additionally, the understandings on the differences and resemblances between the US and European regulatory philosophies on nuclear safety are needed for countries that plan to introduce a nuclear program. These understandings are also needed for the nuclear facility suppliers. The licensing process, applicable regulatory standards and guidelines shall be clearly stated in written form under the contract conditions. If not, unpredictable variables from the difference between US and European regulatory standards may cause a delay in the project schedule. In the case of the JRTR project, clearly-stated licensing process, applicable regulatory standards and guidelines on the contract conditions minimized the delay

  16. Training and teaching with SILOETTE reactor and associated simulators at the Nuclear Research Centre of Grenoble

    International Nuclear Information System (INIS)

    Thanks to its three reactors SILOE (35 MW), MELUSINE (8 MW) and SILOETTE (100 KW), the Reactor Department of the Nuclear Research Centre of Grenoble has gained a considerable experience in the operation and utilization of research and material testing reactors. Inside of this general framework, the Reactor Department of Grenoble has built up a training and teaching centre that has been permanently active since 1975, with the aim of satisfying the considerable needs arising from the development of electro-nuclear power stations. The course is mainly intended for engineers and technicians who will be responsible for running power stations. A thorough series of practical exercices, carried out in the SILOETTE training reactor and in a PWR or in a Gas Cooled Reactor Simulator, desmonstrates the application of the theorical courses and familiarises the trainees with the behaviour of reactors and power stations

  17. Training methods and facilities on reactor and simulators at the Grenoble Nuclear Research Centre

    International Nuclear Information System (INIS)

    Siloette is a CEA unit with a threshold vocation: operation of the Siloette 100 KW pool-type research reactor; basic training in reactor physics for nuclear power plant operators; and production of nuclear power plant simulators: PWR, GCR and more generally of all types of industrial unit simulators, thermal power plant, network, chemical plant, etc. From this experience, they would emphasize in particular the synergy arising from these complementary activities, the essential role of training in basic principles as a complement to operation training, and the ever-increasing importance of design ergonomics of the training means

  18. The Zittau Training and Research Reactor (ZLFR): Aachen students have eastalgic feelings

    International Nuclear Information System (INIS)

    The Zittau Training and Research Reactor (ZLFR) is a thermal zero power reactor of the vessel type whose design concept is based on that of the Russian VVER pressurized water reactors. It was built by the Zittau Technical University with the assistance of the then Central Institute for Nuclear Research at Rossendorf and commissioned in 1979. Among other things, the ZLFR enabled students, in a unique practical training exercise, to run the reactor and study reactivity effects. From the nineties on, it was also possible to conduct research work with the reactor. A group of Aachen students recently completed a practical training course at the ZLFR. In accordance with the provisions of the Unification Treaty, the operating permit for the ZLFR has now expired. The plant is to be converted into a museum. (orig.)

  19. Utilization of the Dalat Research Reactor for Radioisotope Production, Neutron Activation Analysis, Research and Training

    International Nuclear Information System (INIS)

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool type reactor loaded with a mixed core of HEU (36% enrichment) and LEU (19.75% enrichment) fuel assemblies. The reactor is used as a neutron source for the purposes of radioisotopes production, neutron activation analysis, basic and applied research and training. The reactor is operated mainly in continuous runs of 108 hours for cycles of 3–4 weeks for the above mentioned purposes. The current status of safety, operation and utilization of the reactor is given and some aspects for improvement of commercial products and services of the DNRR are also discussed in this paper. (author)

  20. SILOETTE, a training centre for reactor physics at the Nuclear Research Centre of Grenoble

    International Nuclear Information System (INIS)

    The Reactor Department of Grenoble has created, based on Siloette, an activity of training in reactor physics, wich is running since 1975 to meet the important needs generated by the development of electronuclear power stations. Its essential goal is to provide an initiation to the basic physical phenomena which determine the operation of the reactors. For that purpose, a rather comprehensive program of practical works on reactor (SILOETTE) and on nuclear power station simulators (PWR, UNGG) is proposed besides lectures and conferences, general and specialized teaching on the reactor operation principle, kinetics, dynamics and thermics

  1. Reactor simulator development facility for operating personnel training

    International Nuclear Information System (INIS)

    Full text: A development facility of reactor simulators (FARSim) for operator training is presented. The simulator development facility can be divided into four main modules: the model manager (MM), the simulator human machine interface (SHMI), the instructor station (IS) and the simulation manager (SM). It is designed as a distributed system where each module takes charge of an specific simulator task that could run in the same computer or distributed in a computer network. Only the SHMI runs in a remote computer (specific hardware). The process distribution is configurable at the start of the simulation session. This type of process distribution makes it scalable. The main module is the Simulation Manager (SM) which is responsible of routing the messages between the other modules and managing the simulation. The Model Manager (MM) interfaces to the plant mathematical model (PMM). The Data Base Manager (DBM) handles the data base, in order to access and save necessary information during the simulation. The timing of the simulation is accomplished by the Clock Manager (CM) and the error and system messages are handled by the Logger. The Instructor Console (IC) is the process where the instructor commands the simulation. The SHMI is a process interface with the simulator SCADA (which can be identical to the plant SCADA) and is used by the trainee to observe the simulated plant output and to act upon it. The PMM source code, together with the necessary libraries is encapsulated into the MM to implement the model initialisation and the one-step simulation. The MM provides the initial conditions (ICs), and the model input, the PMM provides the plant output. Depending on the complexity of the model, it can be divided and the calculations can be distributed among different CPUs. The PMM source code generation is based on the Matlab-Simulink-Real Time Workshop simulation development environment. The models are developed on graphical windows interfaces based on component

  2. Extensive utilisation of VR-1 reactor for nuclear education and training

    International Nuclear Information System (INIS)

    The paper presents utilisation of the VR-1 reactor for nuclear education and training at national and international level. VR-1 reactor has been operating by the Czech Technical University since December 1990. The reactor is a pool-type light water reactor based on enriched uranium (19.7% 235U) with maximum thermal power 1kW and for short time period up to 5kW. The moderator of neutrons is light water, which is also used as a reflector, a biological shielding and a coolant. Heat is removed from the core by natural convection. The pool disposition of the reactor facilitates access to the core, setting and removing of various experimental samples and detectors, easy and safe handling of fuel assemblies. The reactor core can contain from 17 to 21 fuel assemblies IRT-4M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The reactor is equipped with several experimental devices; e.g. horizontal, radial and tangential channels used to take out a neutron beam, reactivity oscillator for dynamics study and bubble boiling simulator. The reactor has been used very efficiently especially for education and training of university students and NPP's specialists for more than 18 years. The VR-1 reactor is utilised within various national and international activities such as Czech Nuclear Education Network (CENEN), European Nuclear Education Network and also Eastern European Research Reactor Initiative (EERRI). The reactor is well equipped for education and training not only by the experimental facility itself but also by incessant development of training methods and improvement of education experiments. The education experiments can be combined into training courses attended by students according to their study specialization and knowledge level. The training programme is aimed to the reactor and neutron physics, dosimetry, nuclear safety, and control of nuclear installations. Every year, approximately 250 university students undergo

  3. The operating organization and the recruitment, training and qualification of personnel for research reactors. Safety guide

    International Nuclear Information System (INIS)

    This Safety Guide provides recommendations on meeting the requirements on the operating organization and on personnel for research reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization

  4. Realistic neutron spectra for radiation protection and other applications at AERI, Budapest

    CERN Document Server

    Pálfalvi, J; Sajo-Bohus, L

    2002-01-01

    The reconstruction of the Budapest Research Reactor (BRR) gave a good possibility to develop mixed neutron-gamma radiation fields for different applications like: simulation of operational spectra at power reactors, dosimeter development, neutron radiography, biological experiments. Recently, there are 3 horizontal channels available. In addition, isotopic neutron sources are in use in a separate laboratory. In a rotatable holder 4 different sources can be stored and automatically moved into irradiation position. There are changeable collimators and absorbers to modify the spectrum. In the large hall there are possibilities to study the room scatter, angular dependence of detectors, phantom albedo effect etc. Recently available sources are different Pu-Be (from 10 sup 5 -10 sup 7 n/s yield), Ra-Be and Cf. 76.

  5. WWER-1000 reactor simulator. Material for training courses and workshops. 2. ed

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No.12, Reactor Simulator Development (2001). Course material for workshops using a pressurized water reactor (PWR) simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication, Training Course Series No. 22, 2nd edition, Pressurized Water Reactor Simulator (2005) and Training Course Series No.23, 2nd edition, Boiling Water Reactor Simulator (2005). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation

  6. Use of training reactor VR-1 Vrabec in training specialists for nuclear power facilities at Czech universities

    International Nuclear Information System (INIS)

    Training reactor VR-1 VRABEC is being built at the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. It is a pool type reactor with enriched uranium (36% 235U); demineralized light water serves as the moderator and reflector, the reactor core is cooled by natural convection. The rated output is 100 W, short-term operation at 1 kW being possible. The neutron flux density is 1 to 3 x 1014 m-2 s-1. The reactor will find application in education (75% time) in the courses: heat and nuclear engines and equipment, electricity generation, nuclear engineering, and nuclear chemical engineering. The reactor workshop is equipped with ample instrumentation such as multichannel analyzers, dosimetric instruments, activity meters and state-of-the-art computers. (Z.M.)

  7. Training new operators for the SLOWPOKE reactor at Ecole Polytechnique: theory and practice

    International Nuclear Information System (INIS)

    In the last two years we trained two new operators for the SLOWPOKE reactor at Ecole Polytechnique. In this paper we describe how the training program for these operators was designed. We also discuss the shortcomings that were identified in the program and the modifications it required when being put in use.

  8. On the design of the PEC reactor training simulator

    International Nuclear Information System (INIS)

    A summarized description of the PEC simulator, designed for operators' training and operational support, is given. The design choices as a result of the training and operational support requirements are discussed. (orig.)

  9. Application of MCNP for neutronic calculations at VR-1 training reactor

    International Nuclear Information System (INIS)

    The paper presents the utilization of the Monte Carlo MCNP transport code for neutronic calculations of the VR-1 training reactor. Zero power light water reactor VR-1 is used mainly for training and partially for research. The reactor core consists of IRT-4M fuel elements with enrichment below 20 % of 235U and other components (e.g. control rods, fuel dummies, dry channels etc.). The reactor offers large variety of the core configurations and every year at least one critical experiment with new original core configuration is performed. The results of the calculations are compared with measured data collected during the last critical experiments performed with various reactor core configurations. A very good agreement between calculations and measurements is observed

  10. Artificial intelligence and training of nuclear reactor personnel

    International Nuclear Information System (INIS)

    Expert computer systems offer an excellent and effective means to reduce the potential for operator error, and improve plant safety and reliability. For the training field the benefits are twofold. First, the inclusion of advisory expert systems in the control environments (the physical control room and its simulator) offer a continuous source of on-the-job diagnostic training. Second, expert systems specifically designed for training are feasible for specialized license/requalification training in higher order analytical skills. This paper consists of two parts. In the first section, the improvements for on-the-job training are examined. In the second section, the benefits for the overall training program are explored in terms of technical and educational rationales

  11. The role of a small teaching reactor in education and training

    International Nuclear Information System (INIS)

    It cannot be simply concluded that because an undergraduate nuclear engineering program has access to a higher power research reactor that the number of BS graduates will be proportionately larger than a program whose reactor operates at a much lower power level. What can be concluded is that although smaller in size and capability, low-power research reactors and the nuclear engineering programs they serve provide an important role in producing much-needed nuclear engineers and scientists at the undergraduate level. Designed and built by General Electric primarily as a teaching tool for nuclear engineering education, the nuclear reactor at Worcester Polytechnic Institute (WPI) first began operation in 1959. The reactor power level was upgraded from 1 to 10 kW in 1969, and its 20-yr operating license was renewed in 1983. With the support of DOE funds, the reactor was converted to low-enriched fuel in 1988. Under partial funding from the DOE University Reactor Instrumentation Program, the reactor control console will soon be replaced. Since a small research reactor is an ideal tool for providing basic and intermediate nuclear training, the incorporation of nuclear subjects into traditional disciplines will consequently enhance reactor facility usage. With its continued modernization, the WPI nuclear reactor facility will play a key role in meeting nuclear manpower needs while providing excellent and rewarding career opportunities for students in all disciplines for many years to come

  12. Practical nuclear power training for overseas trainees using reactor facilities and radiation handling facilities

    International Nuclear Information System (INIS)

    The research reactor of Tokyo City University Atomic Energy Research Laboratory (Musashi Institute of Technology reactor) is zirconium-moderated water-cooled solid homogeneous type (TRIGA-II type), and its maximum heat output is 100 kW. It got into the first critical state in January 1963, and since then, it has achieved success in many researches. Although its decommissioning was decided in 2013, the existing facilities are used in education, and the research related to the decommissioning of research reactor facilities is carried out. Radiation handling facilities are in place, and they are widely used in education and research activities. Atomic Energy Research Laboratory, as a place for education, is conducting education and research activities such as the education using radiation handling facilities, development of an actual feeling type reactor operation simulator using the control panel of Musashi Institute of Technology reactor and operation performance data. This paper reports the practical nuclear power training for overseas trainees using the reactor facilities and radiation handling facilities. It also reports training implementation plan, acceptance preparation, contents of training, and the results of training. (A.O.)

  13. Training simulator for nuclear power plant reactor monitoring

    International Nuclear Information System (INIS)

    A description is given of a method and apparatus for the real-time dynamic simulation of a nuclear power plant that includes a control and nuclear instrumentation console for operating the reactor and monitoring three-dimensional physical values in the reactor core. A digital computer is connected to the console to calculate physical values such as nuclear flux, power, and temperature including the distribution thereof throughout the core with such calculations including the effect of full length, part length, and malfunctioned reactor control rods, as well as xenon, decay heat and boron, for example, on the output and distribution of power within the core. The simulation also includes instrumentation that responds to the calculated physical values by recording a continuous trace of the flux value in the reactor core from the top to the bottom

  14. Practice of Reactivity Measurement at Central Research Institute for Physics, Budapest

    International Nuclear Information System (INIS)

    At the Central Research Institute for Physics, Budapest /CRIP/ a series of critical assemblies has been built and investigated since 1960, namely: - ZR-1 and ZR-2 critical assemblies fueled by 10% enriched fuel pins /EK-lo type/ moderated and reflected by light water. Both assemblies had a highly variable lattice pitch. - ZE-3 system fueled by 36% enriched hexagonal-tubular fuel-assemblies /WWR-M type/ moderated by light water and reflected by Be. - ZR-4 solid homogeneous zero-power reactor fueled by 20 % enriched U3O8 dispersed in polyethylene/ and reflected by graphite. When investigating these systems the following methods have been chosen and applied routine for reactivity measurements

  15. Gain factors with the new supermirror guide system at the Budapest Neutron Centre

    CERN Document Server

    Rosta, L; Revay, Z

    2002-01-01

    In parallel with the installation of a cold-neutron source (CNS) at the 10-MW Budapest Research Reactor, the neutron-guide system has been redesigned and replaced by state of art neutron optical elements. Monte Carlo calculations have been used to determine the optimal conditions for the guide parameters. For the three cold-neutron beams nearly 100 m of new guides were installed; a great part is made of supermirrors. The new in-pile guide system and the individual shutters enable minimal losses at the starting sections. The out-of-pile part was optimized for the experimental stations. The neutron-flux measurements were compared with the simulated values. The combined effect of the CNS and the guide system yields a gain factor in the flux as high as 30-60. (orig.)

  16. Gain factors with the new supermirror guide system at the Budapest Neutron Centre

    Energy Technology Data Exchange (ETDEWEB)

    Rosta, L.; Cser, L. [Research Institute for Solid State Physics and Optics, 1525, P.O.B. 49, Budapest (Hungary); Budapest Neutron Centre, 1525, P.O.B. 49, Budapest (Hungary); Revay, Z. [CRC Institute of Isotope and Surface Chemistry, 1525, P.O.B. 49, Budapest (Hungary)

    2002-07-01

    In parallel with the installation of a cold-neutron source (CNS) at the 10-MW Budapest Research Reactor, the neutron-guide system has been redesigned and replaced by state of art neutron optical elements. Monte Carlo calculations have been used to determine the optimal conditions for the guide parameters. For the three cold-neutron beams nearly 100 m of new guides were installed; a great part is made of supermirrors. The new in-pile guide system and the individual shutters enable minimal losses at the starting sections. The out-of-pile part was optimized for the experimental stations. The neutron-flux measurements were compared with the simulated values. The combined effect of the CNS and the guide system yields a gain factor in the flux as high as 30-60. (orig.)

  17. Gain factors with the new supermirror guide system at the Budapest Neutron Centre

    International Nuclear Information System (INIS)

    In parallel with the installation of a cold-neutron source (CNS) at the 10-MW Budapest Research Reactor, the neutron-guide system has been redesigned and replaced by state of art neutron optical elements. Monte Carlo calculations have been used to determine the optimal conditions for the guide parameters. For the three cold-neutron beams nearly 100 m of new guides were installed; a great part is made of supermirrors. The new in-pile guide system and the individual shutters enable minimal losses at the starting sections. The out-of-pile part was optimized for the experimental stations. The neutron-flux measurements were compared with the simulated values. The combined effect of the CNS and the guide system yields a gain factor in the flux as high as 30-60. (orig.)

  18. Multimedia Course on Nuclear Reactors Physics, Application to a Tailored On the Job Training Course

    International Nuclear Information System (INIS)

    In order to improve education and training quality, a Multimedia on Nuclear Reactor Physics has been developed. In some institutions, this course is called Fundamentals of Nuclear Reactor Operation. Nowadays, this multimedia has about 800 slides and the text is in Spanish, English, French and Russian. Until now about 126 institutions from 53 countries have applied for the multimedia. The teacher uses the multimedia during his lectures. Students use it at home to study this course

  19. 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

  20. IAEA Workshop (Training Course) on Codes and Standards for Sodium Cooled Fast Reactors. Working Material

    International Nuclear Information System (INIS)

    The training course consisted of lectures and Q&A sessions. The lectures dealt with the history of the development of Design Codes and Standards for Sodium Cooled Fast Reactors (SFRs) in the respective country, the detailed description of the current design Codes and Standards for SFRs and their application to ongoing Fast Reactor design projects, as well as the ongoing development work and plans for the future in this area. Annex 1 contains the detailed Workshop program

  1. University of Florida Training Reactor: Annual progress, September 1, 1985-August 31, 1986

    International Nuclear Information System (INIS)

    Information is presented concerning: University of Florida personnel associated with the reactor; Facility operation; Modifications to the operating characteristics or capabilities of the UFTR facility; Significant maintenance, tests and survelliances of UFTR reactor systems and facilities; Changes to technical specifications, standard operating prceedures and other documents; Radioactive releases and environmental surveillance; Education, research and training utilization; and Theses, publications, reports and oral presentations of work related to the use and operation of the UFTR

  2. Neutron Based Imaging and Element-mapping at the Budapest Neutron Centre

    Science.gov (United States)

    Kis, Z.; Szentmiklósi, L.; Belgya, T.; Balaskó, M.; Horváth, L. Z.; Maróti, B.

    The Budapest Neutron Centre (BNC) is a consortium of institutes to co-ordinate research activities carried out at the Budapest Research Reactor. It hosts two neutron imaging facilities (RAD and NORMA) operated by the Centre for Energy Research, Hungarian Academy of Sciences and offers access to this scientific infrastructure for the domestic and international users. The radiography station (RAD) at the thermal neutron beamline of the reactor gives a possibility to study relatively large objects by thermal neutron-, gamma- and X-ray radiography, and to benefit from the complementary features of the different radiations. RAD is being extended in 2014 with digital imaging and tomographic capabilities. The image detection is based on suitable converter screens. The static radiography and tomography images are acquired by a new, large area sCMOS camera, whereas the dynamic radiography is accomplished by a low-light-level TV camera and a frame grabber card. The NORMA facility is designed to perform neutron radiography and tomography on small samples using guided cold neutrons. Here two non-destructive techniques are coupled to determine the chemical composition and to visualize the internal structure of heterogeneous objects. The position-sensitive element analysis with prompt-gamma activation analysis (PGAA) and the imaging with neutron radiography/tomography (NR/NT) are integrated into a unique facility called NIPS-NORMA. The goal of such a combination of these methods is to save substantial beam time in the so-called NR/NT-driven PGAI (Prompt Gamma Activation Imaging) mode, in which the interesting regions are first visualized and located, and subsequently the time-consuming prompt-gamma measurements are made only where it is really needed. The paper will give an overview about the technical details of the facilities, and the latest results of selected applications from the fields of archaeometry, engineering and material science.

  3. Innovations and Enhancements for a Consortium of Big-10 University Research and Training Reactors. Final Report

    International Nuclear Information System (INIS)

    The Consortium of Big-10 University Research and Training Reactors was by design a strategic partnership of seven leading institutions. We received the support of both our industry and DOE laboratory partners. Investments in reactor, laboratory and program infrastructure, allowed us to lead the national effort to expand and improve the education of engineers in nuclear science and engineering, to provide outreach and education to pre-college educators and students and to become a key resource of ideas and trained personnel for our U.S. industrial and DOE laboratory collaborators.

  4. Training and retraining of personnel working at experimental reactors in compliance with quality assurance obligations

    International Nuclear Information System (INIS)

    At the Saclay site near Paris the Commissariat a l'Energie Atomique is operating three experimental reactors - OSIRIS (70 MW), ORPHEE (14 MW) and ISIS (700 kW). These reactors are run by operators and maintenance personnel under the direction of specialized engineers. Operation is regulated by an official text which specifies that any facility head must have available the resources to ensure training of future staff before they are authorized to take up their posts, having first undergone a test of their behaviour and knowledge. The Saclay Reactor Service instituted procedures four years ago which defined the rules concerning recruitment, training, retraining, and authorization of various staff members, placing particular emphasis on permanent staff. Training and retraining of personnel is done in collaboration with the National Institute for Nuclear Science and Technology at Saclay, which awards an official diploma for a course on nuclear reactor control and instrumentation, with the Grenoble Technological Simulation and Training Centre, and with the Training Service of the Saclay Nuclear Centre

  5. A imagem do hiato: Budapeste* e a fotografia

    Directory of Open Access Journals (Sweden)

    Renato Cury Tardivo

    2010-12-01

    Full Text Available Este artigo propõe uma análise comparativa entre o romance Budapeste, de Chico Buarque, e a linguagem da fotografia. Inserido no âmbito interdisciplinar da psicologia da arte, vale-se de referenciais de crítica literária, estética, fenomenologia e psicanálise, a fim de analisar em que medida Budapeste e a fotografia correspondem-se. A partir da leitura do romance, levantamos algumas questões que, em seguida, procuramos problematizar e ampliar, articulando-as a elementos pertencentes à linguagem fotográfica. Tanto no romance analisado quanto na linguagem da fotografia, parece haver uma espécie de duplo movimento segundo o qual a realidade revela e é revelada

  6. Discrete level schemes sublibrary. Progress report by Budapest group

    International Nuclear Information System (INIS)

    An entirely new discrete levels file has been created by the Budapest group according to the recommended principles, using the Evaluated Nuclear Structure Data File, ENSDF as a source. The resulting library contains 96,834 levels and 105,423 gamma rays for 2,585 nuclei, with their characteristics such as energy, spin, parity, half-life as well gamma-ray energy and branching percentage

  7. The Budapest Reference Connectome Server v2.0

    OpenAIRE

    Szalkai, Balazs; Kerepesi, Csaba; Varga, Balint; Grolmusz, Vince

    2014-01-01

    The connectomes of different human brains are pairwise distinct: we cannot talk about an abstract "graph of the brain". Two typical connectomes, however, have quite a few common graph edges that may describe the same connections between the same cortical areas. The Budapest Reference Connectome Server Ver. 2.0 (http://connectome.pitgroup.org) generates the common edges of the connectomes of 96 distinct cortexes, each with 1015 vertices, computed from 96 MRI data sets of the Human Connectome P...

  8. BUDAPEST, BRATISLAVA AND VIENNA CONFERENCE FACILITIES, COMPARATIVE ANALYSIS

    OpenAIRE

    Endre György Bártfai

    2011-01-01

    The aim of this study is to give an overview of conference facilities in three capital cities in the Central European area, along the Danube, analyse and compare their possibilities and venues. The utilized data within the study was collected from different sources, like websites of the Hungarian, Slovakian and Austrian Convention Bureaus, books dealing with convention and event management and statistics, ICCA publications. Budapest is highly ranked between cities transacting conferences for ...

  9. Modeling and Simulation of Operator Training Simulator for Prototype Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Often the challenge faced by the Nuclear Power Industry is the availability of well trained human resource for efficient power plant monitoring and control. Safety of the plant purely depends upon the plant knowledge acquired, understanding of plant dynamics and the skills possessed by the operators through systematic training. Generally the operators are given class room and field training before deploying them in the operation crew. But, for handling emergency and abnormal conditions, the formal class room training and field training have proved to be inadequate according to the expert estimates. The state- of- art computer based operator training simulators covering the full spectrum of the plant have become an essential element in bridging the gap between the inadequacy and efficiency. Gradually the training simulators are getting embedded in the operator training programme and started playing a crucial role in enhancing the ability of the operators.This paper discusses about the operator training simulator called KALBR- SIM i.e. Kalpakkam Breeder Simulator that has been built at IGCAR for training the Prototype Fast Breeder Reactor (PFBR) operators. It is a Full Scope Replica Operator Training Simulator built to replicate PFBR. The scope of the paper covers the basic modules necessary for building each process model of the simulator, design and development of the reactor sub systems like Neutronics, Primary Sodium, Secondary Sodium, Decay Heat Removal, Steam Water, Electrical systems and the associated logics and controls. It is followed by a detailed discussion on replication aspects of Simulator Control Room and its advantages, the Hardware Architecture, Instruction Station facility and loading of scenarios. It further elaborates on Steady State and Bench Mark Transients tests conducted on the Operator Training Simulator like One primary sodium pump trip, one primary pump seizure, Primary pipe rupture, one boiler feed pump trip and Station Black Out. (author)

  10. Estimation of Siphon Breakers for Jordan Research and Training Reactor

    International Nuclear Information System (INIS)

    The pool water itself is the ultimate heat sink of the residual heat. Thus, it is very important to guarantee that the pool water level be higher than the minimum level from a safety point of view. The JRTR is an open pool-type research reactor and has a downward core flow. To meet the required net positive suction head (NPSHr) of the PCPs, some components of the Primary Cooling System (PCS) are installed below the core level. When a postulated pipe break occurs at below the reactor core position, the pool water can be drained below the core by siphon phenomena, and the core cannot be cooled by natural circulation. Therefore, siphon breakers are installed in the PCS to limit the pool water drain during and after all postulated initiating events. Because the open-type reactor is operating at low pressure and low temperature conditions, guillotine break LOCA (Loss of Coolant Accident) is almost impossible. However, for a design purpose, a pump casing rupture by a failure of moving part has been considered in this study. An estimation of the siphon breakers was performed with the analytical undershooting prediction model. 2.5-inch siphon break lines with siphon break valves were selected as siphon breakers for the JRTR

  11. Estimation of Siphon Breakers for Jordan Research and Training Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwon-Yeong; Seo, Kyoungwoo; Chi, Dae Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The pool water itself is the ultimate heat sink of the residual heat. Thus, it is very important to guarantee that the pool water level be higher than the minimum level from a safety point of view. The JRTR is an open pool-type research reactor and has a downward core flow. To meet the required net positive suction head (NPSHr) of the PCPs, some components of the Primary Cooling System (PCS) are installed below the core level. When a postulated pipe break occurs at below the reactor core position, the pool water can be drained below the core by siphon phenomena, and the core cannot be cooled by natural circulation. Therefore, siphon breakers are installed in the PCS to limit the pool water drain during and after all postulated initiating events. Because the open-type reactor is operating at low pressure and low temperature conditions, guillotine break LOCA (Loss of Coolant Accident) is almost impossible. However, for a design purpose, a pump casing rupture by a failure of moving part has been considered in this study. An estimation of the siphon breakers was performed with the analytical undershooting prediction model. 2.5-inch siphon break lines with siphon break valves were selected as siphon breakers for the JRTR.

  12. Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

    International Nuclear Information System (INIS)

    Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor

  13. Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin [University of Illinois, Urbana (United States)

    2014-08-15

    Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor.

  14. The application of MVC design pattern in Daya bay reactor neutrino experiments online safety training system

    International Nuclear Information System (INIS)

    The article made an introduction to MVC, which is an architectural pattern used in software engineering. It specified the advantages and disadvantages of MVC and also the application of MVC in Daya Bay nuclear reactor neutrino experiment online safety training system. (authors)

  15. Generic Procedures for Response to a Nuclear or Radiological Emergency at Research Reactors - Training Materials

    International Nuclear Information System (INIS)

    Emergencies can occur at a research reactor at any time, even with the best preventative measures in place. Experience shows that even relatively minor reactor emergencies can have a severe social, economic and psychological impact nationally and internationally. In order to minimize these impacts, effective action by the reactor facility personnel and close coordination with local and national officials is essential. This response may include local emergency services (e.g. local medical, law enforcement, and fire brigades). Within hours, national officials may also have an important role to play in supporting the response at the local level. Since reactor emergencies are rare, local responders have little or no experience in dealing with this type of emergency and inexperience often leads to an inadequate response. The IAEA publication 'Generic Procedures for Response to a Nuclear or Radiological Emergency at Research Reactors (EPR-RESEARCH REACTOR, 2011)' guides States in their response to a research reactor emergency. The information within includes action guides for the facility emergency response team, instructions, practical procedures and tools and can be easily adapted by a State to build a basic capability to respond to a research reactor emergency. The materials on this CD are designed to train the reactor facility responders on how to apply 'Generic Procedures for Response to a Nuclear or Radiological Emergency at Research Reactors (EPR-RESEARCH REACTOR, 2011)' in order to effectively respond to a research reactor emergency. Structure. These materials are designed for use at a standard training course on response to research reactor emergencies. They contain information on: Emergencies at Research Reactors and Lessons Learned; Objectives, Concepts and Basic Principles of Emergency Response; Concepts of Operations and Responsibilities; Accident Management vs Emergency Management; Emergency Classification; Urgent Protective Actions; Instructing, Warning

  16. Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

    2009-10-09

    The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

  17. Neutron field for activation experiments in horizontal channel of training reactor VR-1

    International Nuclear Information System (INIS)

    The experimental channels of nuclear reactors often serve for nuclear data measurement and validation. The dosimetry-foils activation technique was employed to measure neutron field parameters in the horizontal radial channel of the training reactor VR-1, and to test the possibility of using the reactor for scientific purposes. The reaction rates, energy spectral indexes, and neutron spectrum at several irradiation positions of the experimental channel were determined. The experimental results show the feasibility of the radial channel for irradiating experiments and open new possibilities for data validation by using this nuclear facility. - Highlights: • Neutron activation analysis of various samples. • Neutron spectrometry and gamma-spectrometry. • Study of keff for various types of reactor core

  18. Education and Training in Support of Sodium Cooled Fast Reactors Around the World

    International Nuclear Information System (INIS)

    The Generation IV Technology Roadmap has identified six systems for their potential to meet the new technology goals to improve safety, sustainability, economic competitiveness and proliferation resistance. Among these systems, three are fast neutron reactors: two cooled by liquid metal, the sodium cooled fast reactor (SFR) and the lead cooled fast reactor, and one cooled by gas, the gas cooled fast reactor. The SFR has the most comprehensive technological basis as a result of the experience gained from worldwide operation of several experimental, prototype and commercial size reactors from the 1940s. In order to support the operation of existing reactors, design activities for new projects and decommissioning of old reactors, it is mandatory to maintain and develop skills, particularly among the young generation. This paper presents the current strategies developed at the national level, or within a multilateral framework such as the EU or the IAEA, to support the development of SFRs, with particular focus on education and training initiatives dedicated to students, researchers, designers and operators involved in the development of SFRs. (author)

  19. Computer modeling of the dynamic processes in the Maryland University Training Reactor - (MUTR)

    International Nuclear Information System (INIS)

    The simulator described in this paper models the behaviour of the Maryland University Training Reactor (MUTR). The reactor is a 250 kW, TRIGA reactor. The computer model is based on a system of five primary equations and eight auxiliary equations. The primary equations consist of the prompt jump approximation, a heat balance equation for the fuel and the moderator, and iodine and xenon buildup equations. For the comparison with the computer program, data from the reactor was acquired by using a personal computer (pc) which contained a Strawberry Tree data acquisition Card, connected to the reactor. The systems monitored by the pc were: two neutron detectors, fuel temperature, water temperature, three control rod positions and the period meter. The time differenced equations were programmed in the basic language. It has been shown by this paper, that the MUTR power rise from low power critical to high power, can be modelled by a relatively simple computer program. The program yields accurate agreement considering the simplicity of the program. The steady state error between the reactor and computer power is 4.4%. The difference in steady state temperatures, 112 deg. C and 117 deg. C, of the reactor and computer program, respectively, also yields a 4.5% error. Further fine tuning of the coefficients will yield higher accuracies

  20. Training reactor VR 1 at the Czech Technical University in Prague is operational

    International Nuclear Information System (INIS)

    Detailed information on the construction work of the VR 1 VRABEC training reactor is presented (building and assembling work, inactive tests) and its technical description is given, with emphasis on the conception of the device and the crucial parts of its technology. The basic parameters of the reactor are as follows: rated power output 1 kW(thermal); fuel of the IRT-2M type (36% 235U enrichment, imported from the former USSR); reactor vessels (pools) made of stainless steel, 2300 mm in diameter, 4720 mm high, wall thickness 15 mm, bottom thickness 20 mm; reactor shielding: 3000 mm water layer above the reactor core, lateral shielding: about 850 mm of water plus a 950 mm layer of special heavy concrete; working temperature inside the reactor, which is affected by the ambient temperature, is about 20 degC; reactor core cooling proceeds by natural convection; pressure is atmospheric; control system consists of 5 to 7 UR-70 type control rods distributed as follows: 3 scram rods, 2 control rods, 0 to 2 experimental rods; neutron source: Am-Be, 185 GBq. (Z.S.). 10 figs

  1. Education and training activities at North Carolina State University's PULSTAR reactor

    International Nuclear Information System (INIS)

    Research reactor utilization has been an integral part of the North Carolina State University's (NCSU's) nuclear engineering program since its inception. The undergraduate curriculum has a strong teaching laboratory component. Graduate classes use the reactor for selected demonstrations, experiments, and projects. The reactor is also used for commercial power reactor operator training programs, neutron radiography, neutron activation analysis (NAA), and sample and tracer activation for industrial short courses and services as part of the university's land grant mission. The PULSTAR reactor is a 1-MW pool-type reactor that uses 4% enriched UO2 pellet fuel in Zircaloy II cladding. Standard irradiation facilities include wet exposure ports, a graphite thermal column, and a pneumatic transfer system. In the near term, general facility upgrades include the installation of signal isolation and computer data acquisition and display functions to improve the teaching and research interface with the reactor. In the longer term, the authors foresee studies of new core designs and the development of beam experiment design tools. These would be used to study modifications that may be desired at the end of the current core life and to undertake the development of new research instruments

  2. Contribution of a small university reactor to nuclear research in education and training

    International Nuclear Information System (INIS)

    The Triga Mark II reactor in Vienna, operated by the Vienna University of Technology, is the research reactor facility closest to the IAEA. 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 fields mentioned. The students are coordinated and supervised by about 70 staff members with the aim of a Master's Degree or PhD in one of the areas mentioned. In addition, the Atomic Institute of the Austrian Universities cooperates closely with the IAEA, located nearby, in research projects, coordinated research projects (CRPs) and in supplying expert services. Regular training courses are performed for the IAEA for safeguard trainees. Moreover, fellowship places are offered for scientists from developing countries and staff members carry out expert missions to research centres in Africa, Asia and South America. Special nuclear material (SNM) belonging to the IAEA is stored for calibration purposes at the Atomic Institute. A summary follows of how and to what extent low power research reactors can efficiently be used to serve university education and training, cooperation with international and national networks, as well as for the IAEA in various fields, such as nuclear safeguards and participation in international coordinated projects

  3. Education and training at the Rensselaer Polytechnic Institute reactor critical facility

    International Nuclear Information System (INIS)

    The Rensselaer Polytechnic Institute (RPI) Reactor Critical Facility (RCF) has provided hands-on education and training for RPI and other students for almost a quarter of a century. The RCF was built in the 1950s by the American Locomotive Company (ALCO) as a critical facility in which to carry out experiments in support of the Army Package power Reactor (APPR) program. A number of APPRs were built and operated. In the middle 1960s, ALCO went out of business and provided the facility to RPI. Since that time, RPI has operated the RCF primarily in a teaching mode in the nuclear engineering department, although limited amounts of reactor research, activation analysis, and reactivity assays have been carried out as well. Recently, a U.S. Department of Energy (DOE) upgrade program supported refueling the RCF with 4.81 wt% enriched UO2 high-density pellets clad in stainless steel rods. The use of these SPERT (F1) fuel rods in the RCF provided a cost-effective approach to conversion from high-enrichment bombgrade fuel to low-enrichment fuel. More important, however, is the fact that the new fuel is of current interest for light water power reactors with extended lifetime fuel. Thus, not only are critical reactor experiments being carried out on the fuel but, more importantly, the quality of the education and training has been enhanced

  4. Neighbourhood dynamics and socio-spatial change in Budapest

    OpenAIRE

    Földi, Zsuzsa; Kovács, Zoltán

    2014-01-01

    In this paper the socio-spatial differentiation that has taken place in the metropolitan region of Budapest since the change of regime is analysed. It is intended to show how local underlying structures and new regulatory contexts (e.g. free market, local urban policies) as well as legacies of the past work together in setting a diverse path of development within the city. In line with the objective in the analytical part of the paper the overall pattern of socio-spatial change in the metropo...

  5. Training tolls for nuclear education at INSTN: software applications, research reactor and simulators

    Energy Technology Data Exchange (ETDEWEB)

    Foulon, F.; Jedrzejewski, F. [Atomic Energy Commission, Saclay Research Centre, 91191 - Gif Sur Yvette (France)

    2010-07-01

    As a part of the French Atomic Energy Commission (CEA), the National Institute for Nuclear Science and Technology (INSTN) is a higher education institution. Its objective is to provide to engineers and researchers a high level of scientific and technological qualification in all disciplines related to nuclear science. This includes the organisation of international courses in nuclear engineering. In order to complete and to illustrate the theoretical courses on reactor physics, an extensive range of training tolls are used. These tolls that include software applications, the use of research reactors and simulators are presented. (authors)

  6. Training tolls for nuclear education at INSTN: software applications, research reactor and simulators

    International Nuclear Information System (INIS)

    As a part of the French Atomic Energy Commission (CEA), the National Institute for Nuclear Science and Technology (INSTN) is a higher education institution. Its objective is to provide to engineers and researchers a high level of scientific and technological qualification in all disciplines related to nuclear science. This includes the organisation of international courses in nuclear engineering. In order to complete and to illustrate the theoretical courses on reactor physics, an extensive range of training tolls are used. These tolls that include software applications, the use of research reactors and simulators are presented. (authors)

  7. Modern design and safety analysis of the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    Highlights: • A new safety analysis of the University of Florida Training Reactor is presented. • This analysis uses modern codes and replaces the NRC approved analysis from 1982. • Reduction in engineering margin confirms that the UFTR is a negligible risk reactor. • Safety systems are not required to ensure that safety limits are not breached. • Negligible risk reactors are ideal for testing digital I&C equipment. - Abstract: A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2 °C, which is significantly below the failure limit of 530 °C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed

  8. Modern design and safety analysis of the University of Florida Training Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, K.A., E-mail: kjordan@ufl.edu [University of Florida, 106 UFTR Bldg., PO Box 116400, Gainesville, FL 32611-6400 (United States); Springfels, D., E-mail: dspringfels@ufl.edu [University of Florida, 106 UFTR Bldg., PO Box 116400, Gainesville, FL 32611-6400 (United States); Schubring, D., E-mail: dlschubring@ufl.edu [University of Florida, 202 Nuclear Science Building, PO Box 118300, Gainesville, FL 32611-8300 (United States)

    2015-05-15

    Highlights: • A new safety analysis of the University of Florida Training Reactor is presented. • This analysis uses modern codes and replaces the NRC approved analysis from 1982. • Reduction in engineering margin confirms that the UFTR is a negligible risk reactor. • Safety systems are not required to ensure that safety limits are not breached. • Negligible risk reactors are ideal for testing digital I&C equipment. - Abstract: A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2 °C, which is significantly below the failure limit of 530 °C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed.

  9. Assessment of the effectiveness of training technology transfer activities at soviet-designed reactors

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) has been working with personnel at Soviet-Designed Reactors (SDRs) to enhance management and operational safety by upgrading many areas of plant operations to levels that meet established international standards. Since 1992 this work has included activities related to training. The work initially focussed on the establishment of nuclear training centers in Russia and Ukraine and the transfer of U.S. training methodologies but has since expanded to include all Russian and Ukrainian nuclear power stations and training centers as well as SDRs within other countries. A key component to the work has been the determination of programmatic effectiveness. Of specific interest has been the success of the transfer of U.S. training methodologies to SDRs so the capability exists for independent expansion of training efforts. Of equal importance has been the question of whether the training programs being developed are having the desired impact on facility safety performance. While progress has been made in the evaluation of the impact of training on facility safety performance, the question has not yet been fully answered. The issue has been further confounded due to wide-ranging and concurrent changes being made beyond training to many aspects of facility operations and maintenance. This paper focuses on the selection of a strategy to upgrade and, as necessary, develop training programs to assist in the improvement of SDR safety. Difficulties encountered in the development of assessment strategies across all SDRs that are being worked with are discussed. In addition, measures collected related to the success of the overall program efforts and data indicating the success of the DOE efforts in the transfer and adoption by SDRs of an effective training methodology are outlined. (author)

  10. Annual progress report of the University of Florida Training Reactor, September 1, 1981-August 31, 1982

    International Nuclear Information System (INIS)

    The University of Florida Training Reactor's overall utilization for the past reporting year has decreased by about 50% compared to the previous year, approaching the low levels of utilization characteristic of the previous two reporting years ending in August 1979 and August 1980 respectively. The energy generation also continues to be far below average historical levels and represents a drop of nearly 50% from the improved level of the previous year. The UFTR continues to operate with an outstanding safety record and in full compliance with regulatory requirements. The reactor and associated facilities continue to maintain a high in-state visibility and strong industry relationship. It is hoped that more indirect industry training will be accomplished in the upcoming year

  11. Student Training Course Using the Experimental Fast Reactor JOYO and Related Facilities

    International Nuclear Information System (INIS)

    University level training courses have been initiated and implemented using the Experimental Fast Reactor Joyo and related facilities of the Japan Atomic Energy Agency (JAEA). These courses offer nuclear facility on-site education and experience in conjunction with a highly experienced engineering staff. University Nuclear Engineering Department faculty members have strongly supported and collaborated in the development of this program. The program covers reactor core physics analysis plus experiments using full-scope training simulator and performing neutron dosimetry, isotopic analysis of noble gases, chemical analysis of sodium, etc. This program is also anticipated to promote the human resource development in the younger generation for the nuclear industry, and to strengthen the relation between JAEA and University research programs. (author)

  12. Combined use of the RPI [Rensselaer Polytechnic Institute] reactor for training and critical experiments

    International Nuclear Information System (INIS)

    The Rensselaer Polytechnic Institute (RPI) reactor critical facility (RCF) has provided educational and research opportunities for RPI and other students for >25 yr. The RCF was built by the American Locomotive Company (ALCO) in the 1950s as a critical facility in support of the army package power reactor program, and, when ALCO went out of business in 1964, the RCF was acquired by RPI. Since that time, RPI has operated the RCF primarily in a teaching mode in the nuclear engineering department, although reactor research, activation analyses, and reactivity assays have been carried out as well. Until recently, the RCF was fueled by plates containing highly enriched uranium as a cermet in stainless steel. This highly enriched uranium (HEU) fuel was replaced recently by 4.81 wt% enriched UO2 high-density pellets clad in stainless steel rods. The use of these SPERT (F1) fuel rods in the RCF provided a cost-effective method for conversion of the core from HEU to low-enriched uranium and for enhancement of the RCF training and research program. The RCF is the only facility in the United States that provides reactor training on a core containing fuel that is similar to that used in power industry light water reactors (LWRs). Moreover, the RCF is the only facility in the United States currently available for supplying critical experimental data in support of the LWR power industry. Thus, the RCF is in a unique position to carry out important training and research services consistent with RPI's nuclear engineering objectives

  13. SARIE upgrade: Nuclear reactor and water systems 'engineering and training' simulator

    International Nuclear Information System (INIS)

    Confronted as of its origins with the on-board layout constraints of the French Navy ships, TECHNICATOME integrates, as of the design, the ergonomics and the risks control related to the human factors. During more than 30 years, TECHNICATOME demonstrated a one of a kind know-how from the design to the execution of powerful, flexible and highly available nuclear compact reactors. A total control which includes up to the supervision and monitoring systems, the acoustic discreetly of the systems and its components, implemented on on-board reactors, testing reactors as well as experimental reactors. The functionalities of simulation were right from the start used by TECHNICATOME during the design phase of these installations to carry out operation engineering analyses on the thermal hydraulic and neutron aspects, to validate the principles of operation of the supervision systems like by the use of digital models in 3D CAD to validate the kinematics of operation or the interactions between systems. More recently, and starting from the end of the Nineties, a thought needs was launched to determine the interests related to the development of a training simulator associated with these installations with objectives, among others, to ensure the phase of initial training of the new operators, to widen the field of the training to the accidental situations, the management of crisis and crews behaviour supervision, the possibilities of replay which support the consolidation of the acquired knowledge(debriefing) with situation resume, and to increase the overall training capacity. An upgrade and modernisation project of these various simulation means was thus launched since 2001 with the objective to optimize the whole of the tasks supported by these means. (author)

  14. Setting-up of remote reactor LAB and tapping into CARRN for distance education and training in nuclear field

    International Nuclear Information System (INIS)

    For a developing country embarking on a research reactor project, building adequate human resource capacity is one of the biggest challenges. Tanzania has been considering a research reactor for some time. The success of future research reactor project impinges on vigorous education and training of necessary personnel to operate and fully utilize the facility. In Africa, underutilization of research reactors is a chronic issue. It is not only misuse of valuable resources but also poses potential safety and security concerns. To mitigate such concerns and to promote education and training, Central African Research Reactor Network (CARRN) was formed in June of 2011. Borrowing from Jordan's success, this paper presents customised curricula to take advantage of CARRN for distance education and training in nuclear field

  15. Teaching and training at RA-6 reactor and their contribution to the research facilities development

    International Nuclear Information System (INIS)

    Full text: The RA-6 is a pool type 500 KW reactor, with U 90% enriched fuel. It is located at Bariloche Atomic Centre (Argentina) and it was designed for teaching, training and research purposes. It has been strongly involved in the Nuclear Engineer career of the Balseiro Institute through grade and post grade courses and master and PHD thesis during the last 20 years in topics like: reactor physics, radiation protection, activation analysis, fuel cycle, radiation dosimetry, BNCT, neutron radiography, beam physics and medical isotopes production. It has also provided training for the exploration teams of the NUR (Algeria) and MPRR (Egypt) reactors commissioned in the last decade and for the personnel involved in the development and operation of its facilities. Operators of the Argentinean Nuclear Power Plant Atucha I and Embalse received specific training in reactor physics and more than 10 world wide professionals were trained, supported by IAEA fellowships. The irradiation facilities initially included in the reactor design were improved focusing in specific interests with an appropriate personnel management, and student's co-operation that allowed achieving different grades of development: The Neutronic Activation Analysis Laboratory (LAAN) has been widely used not only for standard applications but also to water contamination and forensic studies. The Boron Neutron Capture Therapy (BNCT) facility has been completed, with an hyperthermal beam which will be soon used for the treatment of human malignant melanomas; but it has been already been used for 'in vivo' and 'in vitro' experiments in hamsters and mousses which contributed to the development of new applications of BNCT. Beam characterization was included in the Dosimetry Exchange project involving the intercomparison of results with other existing facilities in the world. The Prompt Gamma Neutron Activation Analysis (PGNAA) is being upgraded in the frame of the IAEA project 'New Applications on PGNAA'. It

  16. Training courses on the use of neutron detection systems carried out on the ISIS research reactor

    International Nuclear Information System (INIS)

    Training courses on the use of the neutron detection systems for the control of the nuclear reactors are carried out by the National Institute for Nuclear Science using the ISIS research reactor. The study and the comprehension of the operation of these systems are facilitated by the use a research reactor in order to observe the electronic signals in real conditions. Thus, ISIS reactor offers a wide range of neutron fluxes and the level of power can be easily set to any value from zero to nominal power (700 kW). Different kinds of detectors (counters, ionization chambers), which operate in the different modes of detection (pulse, current and Campbelling) can be placed in the periphery of the core for the courses. The electronic signal can be analyzed at each step of the detection process. One goal of the courses is to understand the role of each component of the detection system: detector, cable and each electronic module. A comparison with the nuclear instrumentation used by the instrumentation and control of ISIS reactor is also made. This comparison is very useful to understand the role of the neutron instrumentation in terms of safety, availability, reliability and maintainability. (authors)

  17. Development of a training simulator to operators of the IEA-R1 research reactor

    International Nuclear Information System (INIS)

    This work reports the development of a Simulator for the IEA-R1 Research Reactor. The Simulator was developed with Visual C++ in two stages: construction of the mathematics models and development and configuration of graphics interfaces in a Windows XP executable. A simplified modeling was used for main physics phenomena, using a point kinetics model for the nuclear process and the energy and mass conservation laws in the average channel of the reactor for the thermal hydraulic process. The dynamics differential equations were solved by using finite differences through the 4th order Runge- Kutta method. The reactivity control, reactor cooling, and reactor protection systems were also modeled. The process variables are stored in ASCII files. The Simulator allows navigating by screens of the systems and monitoring tendencies of the operational transients, being an interactive tool for teaching and training of IEA-R1 operators. It also can be used by students, professors, and researchers in teaching activities in reactor and thermal hydraulics theory. The Simulator allows simulations of operations of start up, power maneuver, and shut down. (author)

  18. Utilization of nuclear research reactors

    International Nuclear Information System (INIS)

    Full text: Report on an IAEA interregional training course, Budapest, Hungary, 5-30 November 1979. The course was attended by 19 participants from 16 Member States. Among the 28 training courses which the International Atomic Energy Agency organized within its 1979 programme of technical assistance was the Interregional Training Course on the Utilization of Nuclear Research Reactors. This course was held at the Nuclear Training Reactor (a low-power pool-type reactor) of the Technical University, Budapest, Hungary, from 5 to 30 November 1979 and it was complemented by a one-week Study Tour to the Nuclear Research Centre in Rossendorf near Dresden, German Democratic Republic. The training course was very successful, with 19 participants attending from 16 Member States - Bangladesh, Bolivia, Czechoslovakia, Ecuador, Egypt, India, Iraq, Korean Democratic People's Republic, Morocco, Peru, Philippines, Spain, Thailand, Turkey, Vietnam and Yugoslavia. Selected invited lecturers were recruited from the USA and Finland, as well as local scientists from Hungarian institutions. During the past two decades or so, many research reactors have been put into operation around the world, and the demand for well qualified personnel to run and fully utilize these facilities has increased accordingly. Several developing countries have already acquired small- and medium-size research reactors mainly for isotope production, research in various fields, and training, while others are presently at different stages of planning and installation. Through different sources of information, such as requests to the IAEA for fellowship awards and experts, it became apparent that many research reactors and their associated facilities are not being utilized to their full potential in many of the developing countries. One reason for this is the lack of a sufficient number of trained professionals who are well acquainted with all the capabilities that a research reactor can offer, both in research and

  19. International Project on Innovative Nuclear Reactors and Fuel Cycles: Introduction and Education and Training Activity

    International Nuclear Information System (INIS)

    The IAEA’s International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 through IAEA General Conference resolution with aim to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21st century. INPRO seeks to bring together technology holders, users and newcomers to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, with a particular focus on sustainability and needs of developing countries. It is a mechanism for INPRO Members to collaborate on topics of joint interest. INPRO activities are undertaken in close cooperation with Member States in the following main areas: Global Scenarios, Innovations, Sustainability Assessment and Strategies, Policy and Dialogue. The paper presents short introduction in INPRO and specifically the distant Education and Training INPRO activity on important topics of nuclear energy sustainability to audiences in different Member States. These activities can support capacity building and national human resource development in the nuclear energy sector. The main benefit of such training courses and workshops is that it is not only targeted to students, but also to lecturers of technical and nuclear universities. Moreover, young professionals working at nuclear energy departments, electric utilities, energy ministries and R&D institutions can participate in such training and benefit from it. (authors)

  20. International Project on Innovative Nuclear Reactors and Fuel Cycles: Introduction and Education and Training Activity

    International Nuclear Information System (INIS)

    The IAEA’s International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 through IAEA General Conference resolution with aim to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21st century. INPRO seeks to bring together technology holders, users and newcomers to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, with a particular focus on sustainability and needs of developing countries. It is a mechanism for INPRO Members to collaborate on topics of joint interest. INPRO activities are undertaken in close cooperation with Member States in the following main areas: Global Scenarios, Innovations, Sustainability Assessment and Strategies, Policy and Dialogue. The paper presents short introduction in INPRO and specifically the distant Education and Training INPRO activity on important topics of nuclear energy sustainability to audiences in different Member States. These activities can support capacity building and national human resource development in the nuclear energy sector. The main benefit of such training courses and workshops is that it is not only targeted to students, but also to lecturers of technical and nuclear universities. Moreover, young professionals working at nuclear energy departments, electric utilities, energy ministries and R&D institutions can participate in such training and benefit from it. (authors) Keywords: nuclear energy sustainability, nuclear education, distant learning, nuclear energy system assessment, educational resources

  1. New digital control and power protection system of VR 1 training reactor

    International Nuclear Information System (INIS)

    The contribution describes the new VR-1 training reactor control and power protection system at the Czech Technical University in Prague. The control system provides safety and control functions, calculates average values of the important variables and sends data and system status to the human-machine interface. The upgraded control system is based on a high quality industrial PC. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. The software was developed according to requirements in MS Visual C. The independent power protection system is a component of the reactor safety (protection) system with high quality and reliability requirements. The digital system is redundant; each channel evaluates the reactor power and the velocity of power changes and provides safety functions. The digital part of the channel is multiprocessor-based. The software was developed with respect to nuclear standards. The software design was coded in the C language regarding the NRC restrictions. Configuration management, verification and validation accompanied the software development. Both systems were thoroughly tested. Firstly, the non active tests were carried out. During these tests, the active core of the reactor was subcritical; the input signals were generated from HPIB and VXI controlled instruments to simulate different operational and safety events. The software for instruments control and tests evaluation utilized Agilent VEE development system. After the successful non active checking, the active tests followed. (author)

  2. Teaching and Training at RA-6 Reactor and their Contribution to the Research Facilities Development

    International Nuclear Information System (INIS)

    The RA-6 reactor at the Bariloche Atomic Centre was designed mainly as a teaching tool. During its almost 21 years, after the first criticality, it was used as a support for several graduate and post graduate careers at the Balseiro Institute, depending on the Argentine National Atomic Energy Commission and the Cuyo National University. Besides these tasks, a big work was done in research and development using the synergy produced by the close relationship between the students and researchers. Main characteristics of the reactor are described. An outline of use for teaching and training is given. Research activities resulting from appropriate personnel management and students' cooperation that allowed achieving different grades of development are described. (author)

  3. Decommissioning Small Research and Training Reactors; Experience on Three Recent University Projects - 12455

    International Nuclear Information System (INIS)

    Decommissioning small reactors within the confines of an active University environment presents unique challenges. These range from the radiological protection of the nearby University population and grounds, to the logistical challenges of working in limited space without benefit of the established controlled, protected, and vital areas common to commercial facilities. These challenges, and others, are discussed in brief project histories of three recent (calendar year 2011) decommissioning activities at three University training and research reactors. These facilities include three separate Universities in three states. The work at each of the facilities addresses multiple phases of the decommissioning process, from initial characterization and pre-decommissioning waste removal, to core component removal and safe storage, through to complete structural dismantlement and site release. The results of the efforts at each University are presented, along with the challenges that were either anticipated or discovered during the decommissioning efforts, and results and lessons learned from each of the projects. (authors)

  4. Pilot program: NRC severe reactor accident incident response training manual: US Nuclear Regulatory Commission response

    International Nuclear Information System (INIS)

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. US Nuclear Regulatory Commission Response is the fifth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes NRC response modes, organizations, and official positions; roles of other federal agencies are also described briefly. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  5. The AKR training reactor of the University of Technology Dresden and its experimental programme for education

    International Nuclear Information System (INIS)

    The training and research reactor AKR (from the German Ausbildungskernreaktor) of the University of Technology Dresden was put into operation in the late 1970s, i.e. at a time when experts in Western and Eastern European countries expected an extensive development of nuclear energy generation. In the eastern part of Germany, i.e. the former German Democratic Republic, a 70 MW(el) WWER nuclear power plant (NPP) was in operation at Rheinsberg since 1966. A further five NPPs of the Russian WWER type (440 MW(e)) were put into operation at Greifswald on the Baltic Sea coast between 1973 and 1989. Three more plants were under construction at that site. At the end of the 1980s, a new NPP was being planned at Stendal, a 1000 MW(e) WWER plant. For construction, licensing, operation and maintenance of these NPPs, a well educated and trained staff was required. Authorities and technical surveillance organizations should have qualified experts at their disposal, too. Consequently, in 1968 the University of Technology Dresden introduced appropriate courses for the education of nuclear engineers in order to contribute to fulfilling the demands of industry, science and administration. Students were taught in lectures, but theoretical knowledge had to be combined with practical experience based on an extensive programme of fundamental experiments in the fields of reactor physics, neutron physics, nuclear technology, radiation measurement techniques, radiation protection, radiation dosimetry and others. The full scale of this experimental programme can preferably be made available by small training reactors which can be operated with great diversity in terms of experimental intentions and without commercial restrictions

  6. University of Florida Training Reactor. Annual progress report, September 1, 1983-August 31, 1984

    International Nuclear Information System (INIS)

    The University of Florida Training Reactor's overall utilization for the past reporting year has increased dramatically compared to previous years, even exceeding the levels of utilization characteristic of the early 1970's in some areas such as energy generation. Indeed, the total energy generation (kWh) for this reporting year is at the highest level ever and represents an increase of over 300% over the 1982-1983 reporting year which itself had an increase of 50% over the 1981-1982 reporting year

  7. The Budapest experience for installation of a liquid hydrogen moderator and guide equipment for neutron scattering research

    Energy Technology Data Exchange (ETDEWEB)

    Rosta, Laszlo [Research Institute for Solid State Physics, Budapest (Hungary)

    1997-07-01

    The 10 MW power Budapest Research Reactor serves various tasks, such as basic and applied research in physics, chemistry, biology, materials science as well as commercial utilization and education. It is open for the international user community. For neutron beam measurements different types of horizontal channels are available: seven thermal and two fast neutron channels; a tangential beam tube serves for the neutron guide system. A liquid hydrogen cold neutron source with cryogenic system of a direct cooling moderator assembly for enhanced performance and improved safety characteristics is under construction. The neutron guide system adjoining to the cold source is designed to be optimized for the specific experiments by providing the proper geometry and supermirror coating of the optical elements. A short description of the neutron guide equipment and examples from the related research activity are given.

  8. Progressive system of objective assessment of training at WWER-440 simulator at the Reactor Teaching and Training Centre of the Nuclear Power Plants Research Institute

    International Nuclear Information System (INIS)

    A system has been devised for an objective testing and examination of nuclear power plant personnel during the basic and repetitive training on a WWER-440/V-213 reactor simulator. This personnel includes shift engineers, reactor unit managers, and operators of the primary and secondary parts of nuclear power plants. The following are subject to testing: knowledge, intellectual and psychomotoric skill, habits, and attitudes. The objective testing and examination system proposed comprises four levels. The first level is based on permanent information acquisition and serves the daily needs of the training. The second level provides information on how each of the training stages has been mastered. The third level is concerned with the practical fulfilment of training tasks based on simple operations at the operator's working spot, and the fourth level examines all the worker's activity and personality features over the entire span of standard as well as nonstandard regimens of the nuclear power plant unit. (Z.M.). 1 fig., 2 refs

  9. Modeling Comovement among Emerging Stock Markets: The Case of Budapest and Istanbul

    OpenAIRE

    Numan Ülkü

    2011-01-01

    A double world index model is proposed as an ideal way of characterizing the comovement among emerging stock markets, and applied to Budapest-Istanbul as an interesting case. An exclusive increase in the correlation between Budapest and Istanbul during the recent crisis period is documented. To decompose this correlation into information dynamics, a structural vector autoregression (SVAR) model is employed which controls for global indices that enter the system exogenously. Istanbul and Budap...

  10. Training at the masters degree level in physics and technology of nuclear reactors in the uk

    International Nuclear Information System (INIS)

    This paper discusses the current situation of university-based training for the nuclear power industry in the UK, drawing on information gathered as part of the survey for a review currently being undertaken by the Committee for Technical and Economic Studies on Nuclear Energy Development and Fuel Cycle (NDC) of the Nuclear Energy Agency (NEA) of the OECD. A particular focus will be the Physics and Technology of Nuclear Reactors MSc course at the University of Birmingham. In the past there were other similar MSc courses in the UK, but through the evolution of time the Birmingham course is now unique in its role of providing masters level training so specifically aimed at the commercial nuclear programme. Mention will, however, be made of other training at the postgraduate level elsewhere in the UK. A description is given of the need to consider a new form of relationship between industry and university in order to provide optimise the provision of masters level training. (author)

  11. Personnel training program for WWR-S Nuclear Research Reactor - on the radiological characterization and cleanup activities

    International Nuclear Information System (INIS)

    The aim of this program is the development of competence by training, acquiring, extending and maintaining competence, using fundamental or refreshment training courses. Progress and suited approach are established based on the list with tasks and subjects to be assimilated. According to 'graded approach to training' method the training process will be assessed from initial training-to-training evaluation at the working place. The program responsible of and participants will provide a detailed report that will describe the progress, achieved competence area and the future training necessities. Report form will be given to the participants at the beginning of the training, which will be completed during the program. It will be taken in account that the Nuclear Reactor WWR-S is in the conservation phase for the Nuclear Reactor and the exploitation of the Nuclear Spent Fuel Ponds (Away from Reactor-AFR) - both phases are authorized by the Regulatory Body (CNCAN), as transition phase from the operating-shut-down-conservation phase and the decommissioning preparing: clean-up, maintaining and improvement of the nuclear safety, technical documentation elaboration, maintenance activities. (authors)

  12. Training courses for the staff of the nuclear power station KRSKO conducted at the TRIGA reactor center in Ljubljana

    International Nuclear Information System (INIS)

    The training program for the Nuclear Power Station Krsko was divided into two modules: fundamentals of nuclear engineering and specialized training according to duties that candidates are supposed to take at the power station. Basic training was organized at the TRIGA Reactor Center in Ljubljana in two different versions. The first version intended for plant operators and all engineers lasted for six months and included about 500 hours of classroom lessons and seminars and 31 laboratory experiments. The educational program was conventional. The following topics were covered: nuclear and atomic physics, reactor theory, reactor dynamics, reactor instrumentation and control, heat transfer in nuclear power plants, nuclear power plant systems, reactor materials, reactor safety, and radiation protection. Until now, two groups, consisting of 37 candidates altogether, have attended this basic course. Plans have been made to conduct two additional courses of about 20 students each for technicians other than operators. The program of this second version will be reduced, with the emphasis on reactor core physics and radiation protection. Classroom lessons will be strongly supported by laboratory experiments. (author)

  13. Research Reactor Utilization at the University of Utah for Nuclear Education, Training and Services

    International Nuclear Information System (INIS)

    In the years of nuclear renaissance we all recognize a need for modernizing the approaches in fostering nuclear engineering and science knowledge, in strengthening disciplinary depth in students’ education for their preparation for workforce, and in helping them learn how to extend range of skills, develop habits of mind and subject matter knowledge. The education infrastructure at the University of Utah has been recently revised to incorporate the experiential learning using our research reactor as integral part of curriculum, helping therefore that all of our students build sufficient level of nuclear engineering literacy in order to be able to contribute productively to nuclear engineering work force or continue their education toward doctoral degrees. The University of Utah TRIGA Reactor built 35 years ago represents a university wide facility to promote research, education and training, as well as is used for various applications of nuclear engineering, radiation science and health physics. Our curriculum includes two consecutive classes for preparation of our students for research reactor operating license. Every year the US Nuclear Regulatory Commission’s representatives hold the final exam for our students. Our activities serve the academic community of the University of Utah, commercial and government entities, other universities and national laboratories as well. (author)

  14. Education and training at the Penn State Breazeale reactor for the past twenty years

    International Nuclear Information System (INIS)

    For the past 20 yr, some of the original activities at the Penn State Breazeale Reactor (PSBR) have remained active, whereas other programs have been replaced by new ones. Overall there have been significant changes in research, training, and educational activities, but this was necessary to maintain a strong, viable program at the PSBR. The PSBR has always made an important contribution to the nuclear engineering department's laboratory courses. Activation analysis is a major activity that has continued robustly for the past 20 yr. Activation analysis has spawned a new low-level radiation monitoring laboratory that provides services for the university, local community, and the state. It supports research and broadens the activity in radiation research. The study of monitoring radiation is a focus of the research of a few faculty because of the presence of the PSBR. Recently, two new activities were introduced at the at the PSBR; they are neutron radiography and perturbed angular correlation (PAC). The nuclear engineering faculty that use a research reactor in their curriculum and research will be much stronger than without it. However, a nuclear research reactor facility will only be successful if the nuclear engineering faculty use it as a major tool

  15. University of Florida Training Reactor: Annual progress report, September 1, 1986-August 31, 1987

    International Nuclear Information System (INIS)

    The University of Florida Training Reactor's overall utilization for the past reporting year (September 1986 through August 1987) has returned to the increased levels of quality usage characteristic of the two years prior to the last reporting year when the maintenance outage to repair sticking control blades reduced availability for the year to near 50%. Indeed, the 91.5% availability factor for this reporting year is the highest in the last five years and probably in the 27 year history of the facility. As a final statement on the effectiveness of the corrective maintenance last year, the overall availability factor has been over 94% since returning to normal operations. The UFTR continues to experience a high rate of utilization in a broad spectrum of areas with total utilization continuing near the highest levels recorded in the early 1970's. This increase has been supported by a variety of usages ranging from research and educational utilization by users within the University of Florida as well as other researchers and educators around the state of Florida through the support of the DOE Reactor Sharing Program and several externally supported usages. Significant usage has also been devoted to facility enhancement where a key ingredient for this usage has been a stable management staff. Uses, reactor operation, maintenance, technical specifications, radioactive releases, and research programs are described in this report

  16. Experience in the recruitment, organization and training of operations and maintenance personnel for the Malaysian research reactor

    International Nuclear Information System (INIS)

    The TRIGA Reactor located at the Tun Ismail Atomic Research Centre (PUSPATI) Complex is owned and operated by the Nuclear Energy Unit of the Prime Minster's Department. The operations and maintenance personnel are part and parcel of the national civil service organization. As such, the requirement and remuneration of these personnel are handled by a central federal government personnel management agency in common with personnel from other federal government agencies. In addition, the reactor is the first and only one in Malaysia, a developing country, which is the process of committing herself towards a nuclear power programme. These factors coupled with the absence of an independent reactor operator licensing agency posed unique problems in the recruitment, organization, training and licensing of operations personnel for the facility. The paper discusses these factors and their bearing on the recruitment, training, licensing and career development prospects of the PUSPATI TRIGA Reactor operators. (author)

  17. Training and accreditation activities at the Department of Energy Category A Reactors and Nuclear Facilities

    International Nuclear Information System (INIS)

    A new era dawned within the Department of Energy (DOE) in 1989 when DOE Order 5480.18A 'Accreditation of Performance-Based Training for Category A Reactors and Nuclear Facilities' was issued. This new era emphasized the importance of personnel training and qualification in maintaining the continued safe and efficient operation of the diverse nuclear facilities within the DOE complex. This approach to the design, development, and implementation of training is very similar to the approach that has proven to be very successful within the commercial nuclear industry. During the 1980s in the aftermath of Three Mile Island (TMI), DOE made a significant effort to conduct its mission in an environmentally safe manner and to increase the existing level of protection of the workers and the public. The DOE, like the commercial nuclear industry, realized that a nuclear accident anywhere in the U.S.A. would negatively impact the public confidence in the entire industry. This effort has not been easy because of changes within DOE and changes in regulatory requirements. Difficulties include aging facilities, outdated equipment, ingrained operating habits, inflexible culture, outdated or nonexistent procedures, stagnated management structure, lack of technical specifications and safety analysis reports, no configuration control, informal and undocumented training and qualification processes, and a wide diversity of operating facilities. The commercial industry had problems adjusting to the new regulations after TMI, but none as challenging as those facing DOE. This paper centers on the importance and status of accreditation within the DOE community and the efforts to develop and implement a performance-based approach to the training of the personnel at these facilities

  18. Calibration of new I and C at VR-1 training reactor

    International Nuclear Information System (INIS)

    The paper describes a calibration of the new instrumentation and control (I and C) at the VR-1 training reactor in Prague. The I and C uses uncompensated fission chambers for the power measurement that operate in a pulse or a DC current and a Campbell regime, according to the reactor power. The pulse regime uses discrimination for the avoidance of gamma and noise influence of the measurement. The DC current regime employs a logarithmic amplifier to cover the whole reactor DC current power range with only one electronic circuit. The system computer calculates the real power from the logarithmic data. The Campbell regime is based on evaluation of the root mean square (RMS) value of the neutron noise. The calculated power from Campbell range is based on the square value of the RMS neutron noise data. All data for the power calculation are stored in computer flash memories. To set proper data there, it was necessary to carry out the calibration of the I and C. At first, the proper discrimination value was found while examining the spectrum of the neutron signal from the chamber. The constants for the DC current and Campbell calculations were determined from an independent reactor power measurement. The independent power measuring system that was used for the calibration was accomplished by a compensated current chamber with an electrometer. The calculated calibration constants were stored in the computer flash memories, and the calibrated system was again successfully compared with the independent power measuring system. Finally, proper gamma discrimination of the Campbell system was carefully checked.

  19. New Work Environment for Reactor Safety Analysts: Integrated Training and Accident Analysis System

    International Nuclear Information System (INIS)

    Safety and risk analyses are complex by nature and require significant effort, extensive skills and experience, analytical tools and supporting information. To reduce the effort and to enhance the analytical capabilities for present and future generation of nuclear systems, an Integrated Training and Accident Analysis System (ITAAS) has been developed. The primary objective of the ITAAS combined software/hardware system is to provide a comprehensive and integrated accident and safety analysis capability for research and technical support organizations and other potential users (such as regulators) having responsibilities related to nuclear power plants (NPPs), research reactors, and other nuclear facilities. More specifically, and in the context of well executed accident and safety analyses, ITAAS provides: Proven Analytical Tools via the Deterministic Analysis Module based on RELAP5 and the Probabilistic Analysis Module based on SAHPIRE, Specialized Skill Development via a Training Module, and a Broad Knowledge Base via a Reference Module. The modular design and connectivity of ITAAS allows for enhancement of existing, and addition of new modules, primarily in the context of future implementation of new analysis tools and their associated training requirements. ITAAS can be configured for specific NPPs or other nuclear installations as may be dictated by facility, organization or country needs. The first ITAAS system has been installed at the Kursk 1 NPP in Russia. (authors)

  20. URI Program Final Report FY 2001 Grant for the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    The purpose of the URI program is to upgrade and improve university nuclear research and training reactors and to contribute to strengthening the academic community's nuclear engineering infrastructure. It should be noted that the proposed UFTR facility instrumentation and equipment can generally be subdivided into three categories: (1) to improve reactor operations, (2) to improve existing facility/NAA Laboratory operations, and (3) to expand facility capability. All of these items were selected recognizing the objectives of the University Reactor Instrumentation Program to respond to the widespread needs in the academic reactor community for modernization and improvement of research and training reactor facilities, especially at large and diverse institutions such as the University of Florida. These needs have been particularly pressing at the UFTR which is the only such research and training reactor in the State of Florida which is undergoing rapid growth in a variety of technical areas. As indicated in Table 2, the first item is a security system control panel with associated wiring and detectors. The existing system is over 30 years old and has been the subject of repeated maintenance over the past 5 years. Some of its detection devices are no longer replaceable from stock. Modifications made many years ago make troubleshooting some parts of the system such as the backup battery charging subsystem essentially impossible, further increasing maintenance frequency to replace batteries. Currently, various parts of the system cable trays remain open for maintenance access further degrading facility appearance. In light of relicensing plans, this item is also a key consideration for housekeeping appearance considerations. The cost of a replacement ADEMCO Vista 20 security system including turnkey installation by a certified vendor was to be $2,206. Replacement of this system was expected to save up to 5 days of maintenance per year, decrease security alarm response

  1. Performance of small reactors at universities for teaching, research, training and service (TRTS): thirty five years' experience with the Dalhousie University SLOWPOKE-2 reactor

    International Nuclear Information System (INIS)

    The Dalhousie University SLOWPOKE-2 Reactor (DUSR) facility, operated during 1976-2011, was the only research reactor in Atlantic Canada as well as the only one associated with a chemistry department in a Canadian university. The most outstanding features of the facility included: a rapid (100 ms) cyclic pneumatic sample transfer system, a permanently installed Cd-site, and a Compton-suppression gamma-ray spectrometer. The usage encompassed fundamental as well as applied studies in various fields using neutron activation analysis (NAA). The facility was used for training undergraduate/graduate students, postdoctoral fellows, technicians, and visiting scientists, and for cooperative projects with other universities, research organizations and industries. (author)

  2. Use of a digital reactivity meter on TRIGA reactor for instrumentation and training purposes

    International Nuclear Information System (INIS)

    Development of a realtime reactivity calculation algorithm, based on recursive solution of the inverse point kinetic equation, and adapted for digital computer calculation, is described. Application of this algorithm to an ''off-the-shelf'' microcomputer is presented in order to produce an extremely low cost piece of equipment that can both alleviate the work of operators as well as serve as an extremely versatile tool for training purposes. Various applications of this device in a day to day work of a research reactor operators are given. A method of control rod worth measurement after core reconfiguration using this digital reactivity meter is described. Demonstration of various effects, such as control rod insertion or extraction, void coefficient measurement, temperature feedback effects, etc., is described. (author)

  3. The ENEN-III project: Technical Training on the Concepts and Design of GEN IV nuclear reactors

    International Nuclear Information System (INIS)

    ENEN-III (European Nuclear Education Network Training Schemes) is a project within the 7th Framework Programme that falls under the Euratom Fission Training Schemes (EFTS) in all areas of nuclear fission and radiation protection. ENEN-III joins 19 partners from 12 European countries and its specific area is nuclear engineering. It covers the structuring, organization, coordination and implementation of training schemes in cooperation with local, national and international training organizations, to provide training to professionals in nuclear organizations or their contractors and subcontractors. The schemes provide a portfolio of courses, training sessions, seminars and workshops, offered to these professionals for continuous learning, for updating their knowledge and developing their skills to maintain their performance at the current state-of-the-practice and to anticipate the implementation of new scientific and technological developments. One of the generic types that is addressed is the training scheme for the development and pre-conceptual design of generation IV nuclear reactors. A training scheme for the design of these advanced nuclear reactors, including the large variety of topics to be covered, will be more research oriented and will have a broader and less specialized scope than other schemes. It is expected to respond to the current needs of the research communities and engineering companies in order to design and build the prototypes of the nuclear reactors of the future, taking into account that there is a shortage of engineers with a satisfactory background in nuclear disciplines. The paper will present this training scheme developed within ENEN-III. (author)

  4. Design of a Control Room for Jordan Research and Training Reactor (JRTR)

    International Nuclear Information System (INIS)

    Since the main role of JRTR(Jordan Research and Training Reactor) operating personnel is safe and reliable operation of the reactor, MCR(Main Control Room) and SCR(Supplementary Control Room) must provide them with sufficient information and controls needed to optimize their performance. Before the TMI accident, control room were generally designed just with intuitive common sense, without using any proper HFE(human factors engineering) practices. Many results derived from the analysis of TMI accident showed that a more comprehensive and systematic approaches to develop MCR design requirements were needed. Moreover changes of operators' role as a decision maker from a physical controller in rapid improvement of control system which resulted in higher automation clearly needed more featured regulatory requirements and guidelines. So many regulatory and industrial guidance for control room design have been developed by relevant institution and regulatory bodies. In this paper, a conceptual design of the JRTR control room in the effort of satisfying current regulatory requirements and guidelines are presented. And some information display design is also presented

  5. The Text of the Instrument Concerning the Agency's Assistance to Argentina for the Establishment of a Training Reactor Project

    International Nuclear Information System (INIS)

    The text of the Agreement between the Agency and the Governments of Argentina and the Federal Republic of Germany concerning the Agency's assistance for the establishment of a training reactor project in Argentina is reproduced herein for the information of all Members. The Agreement entered into force on 13 March 1970.

  6. Assessment of the implications of conversion of university research and training reactors to low enrichment uranium fuel

    International Nuclear Information System (INIS)

    The tasks associated with conversion of a research reactor from HEU to LEU fuel are: initial program planning; safety analysis and license amendment; core physics calculations; operating thermal-hydraulics analysis; plant engineering modifications; LEU fuel specifications, procurement of fuel, and calculational confirmation of design; training of staff personnel; HEU core physics measurements and fuel disposal; and experimental verification of reactor behavior with LEU fuel. LEU fuel conversion of the 25 NRC licensed, university-owned reactors considered in this study is based upon the reactor fuel cycle, the type of license modification, and fuel meat technology. Reactors that operate on routine refueling cycles could periodically replace depleted HEU elements with fresh LEU elements. Ultimate full core conversion would depend on the average element residence time in the core. Reactors with lifetime cores would convert by full core replacement as a one-time event. For some reactors, LEU conversion depends upon high density uranium fuel meat technology development. The majority should be able to convert using a direct substitution of current fuel meat technology though some fuel plate or rod internal modifications may be necessary for 16 of the reactors

  7. Application of dosimetry measurements to analyze the neutron activation of a stainless steel sample in a training nuclear reactor

    International Nuclear Information System (INIS)

    All materials present in the core of a nuclear reactor are activated by neutron irradiation. The activity so generated produces a dose around the material. This dose is a potential risk for workers in the surrounding area when materials are withdrawn from the reactor. Therefore, it is necessary to assess the activity generated and the dose produced. In previous works, neutron activation of control rods and doses around the storage pool where they are placed have been calculated for a Boiling Water Reactor using the MCNP5 code based on the Monte Carlo method. Most of the activation is produced indeed in stainless steel components of the nuclear reactor core not only control rods. In this work, a stainless steel sample is irradiated in the Training Reactor AKR-2 of the Technical University Dresden. Dose measurements around the sample have been performed for different times after the irradiation. Experimental dosimetric values are compared with results of Monte Carlo simulation of the irradiation. Comparison shows a good agreement. Hence, the activation Monte Carlo model can be considered as validated. - Highlights: • Neutron activation of materials in the core of a nuclear reactor. • Application of the Monte Carlo method to simulate neutron activation. • Importance of steel components of the reactor core for neutron activation. • Irradiation of a stainless steel sample in a nuclear reactor. • Doses measured around the sample are compared with MC simulation results

  8. The human resources and training - A mandatory gate for water cooled reactors in the 21. century

    International Nuclear Information System (INIS)

    Full text: Despite the current situation of the global economy, the world's electricity needs will keep growing in the medium term and are about to double in 2030 from the today's figure. As per 2007 the total worldwide nuclear electricity production was totaling more than 2700 TWHR. The renaissance of nuclear power is still ahead of us and new NPPs will from today up to 2030 amount at a total of 350 MWe installed capacity. After the four EPR units already in construction, the projects decided or under preparation in the U.K., in the U.S. and in France for instance, confirm this steady trend. The nuclear industry, and in particular AREVA, needs of course to adapt to this demand for new builds, and at the same time not forget to supply and serve the unabated needs of the fleets in operation. More than 80% of our AREVA nuclear business consists in these recurring activities for the existing NPPs. Moreover our customers continue to seek for more integration of our front end, reactors and back end services. In parallel, the demand for water cooled reactors along the 21st century is foreseen to raise new challenges, industrially speaking but moreover in term of knowledge, training, and people. In order to address this increasing demand, we are investing in all our segments of activity. This is the case in the equipment sector where we are increasing both our primary components manufacturing capacity and our forging production capacity. This is the case in the nuclear fuel front end with an acceleration of exploration, the opening of new mines and the construction of new conversion and enrichment factories. This is the case in our nuclear engineering and nuclear services divisions and this is even the case in our T and D branch with continuous expansion of the industrial tool. What does all that mean in terms of human resources? It means of course more jobs in all our business units. From 2005 to 2008 the annual number of hiring has increased from 6000 to 12000. Such

  9. EERRI Coalition as a Platform for Close Cooperation - An Enhanced Utilization of Research Reactors in Central and Eastern Europe

    International Nuclear Information System (INIS)

    One the most visible trend in nuclear education and training which became visible during the last few years is networking and closer co-operation between universities at national and international level in nuclear education. Research reactors, which are mainly part of a research institute or university, had the same evolution in networking as universities but with a few years delay - research reactors started to create reactor coalitions. The first impulse towards reactor coalitions was done at the IAEA International Conference on Research Reactors: Safe Management and Effective Utilization, held in Sydney in November 2007, where research reactor coalitions and centres of excellence were two of the key topics of the conference. At this conference functioning and future sustainability of such reactor coalitions were widely discussed. As a result of those discussions, the first reactor coalition was established three months later. In the January 2008 the Eastern European Research Reactor Initiative (EERRI) was born in Budapest, Hungary. The EERRI reactor coalition now covers nine research reactors from seven European countries. The main purpose why reactor coalitions have been born is the chance to offer complex services in a wide range of activities which a single reactor cannot offer and synergy benefits from joint efforts of the coalition. The next reasons for coalitions cover sharing the irradiation and experimental capacities, coordination of the reactor operation for potential shutdown one of the coalition reactors, etc. A good example how the reactor coalition could work is the oldest coalition - EERRI. Wide power range and various reactors' use allow EERRI to offer to solve any type of the experimental work usually performed at research reactors from beam experiments through various types of neutron activation analysis, fuel investigation, material science, radioisotope production to education and training. All EERRI activities are focused in the four main

  10. Characterization and Application of the Thermal Neutron Radiography Beam in the Egyptian Second Experimental and Training Research Reactor (ETRR-2)

    OpenAIRE

    M. A. Abou Mandour; R. M. Megahid; Hassan, M.H.; T. M. Abd El Salam

    2007-01-01

    The Experimental, Training, Research Reactor (ETRR-2) is an open-pool multipurpose reactor (MPR) with a core power of 22 MWth cooled and moderated by light water and reflected with beryllium. It has four neutron beams and a thermal column as the main experimental devices. The neutron radiography facility unit utilizes one of the radial beam tubes. The track-etch technique using nitrocellulose films and converter screen is applied. In this work, the radial neutron beam for the thermal neutron ...

  11. Characterization and Application of the Thermal Neutron Radiography Beam in the Egyptian Second Experimental and Training Research Reactor (ETRR-2)

    OpenAIRE

    Abd El Salam, T. M.; Hassan, M.H.; Megahid, R. M.; M. A. Abou Mandour

    2008-01-01

    The Experimental, Training, Research Reactor (ETRR-2) is an open-pool multipurpose reactor (MPR) with a core power of 22 MWth cooled and moderated by light water and reflected with beryllium. It has four neutron beams and a thermal column as the main experimental devices. The neutron radiography facility unit utilizes one of the radial beam tubes. The track-etch technique using nitrocellulose films and converter screen is applied. In this work, the radial neutron beam for the thermal ...

  12. Transition of Monju simulator training owing to Monju accident and upgrade of Monju advanced reactor simulator (MARS)

    International Nuclear Information System (INIS)

    The Monju advanced reactor simulator (MARS) has been operated for training of Monju operators and for verification of Monju operating manual's appropriateness since 1991 for over 11 years. This report covers transition of Monju training system and modified of MARS owing to Monju accident as operating experience of MARS on from 1994 to 2001. The principal points mentioned are as follows: (1) Improved Monju training system owing to Monju accident 1) Reinforcement of sodium handling and sodium fire-fighting exercise. 2) Improved of training system and revised of training frequency. 3) Introduced of evaluation and analysis system regarding training results. 4) Providing of training guide line. 5) Step up of fundamental education by introducing of CAI (Computer Assisted Instruction System). (2) Upgrade of MARS for Monju restarting. 1) Reflected of the real plant data obtained from Monju performance test. 2) Addition of malfunction items. 3) Development of simulation software and addition of simulation panel concerning reinforced sodium leakage corresponding training. 4) Improvement of simulation ability and remodeling of calculating model by renewal of computer system. 5) Up graded program in the future. (author)

  13. Operational Radiation Protection and Radioactive Waste Management for Research ReactorsTraining Material

    International Nuclear Information System (INIS)

    The main objectives of the workshop are to provide the participants with the knowledge and understanding to be able to: • Develop and implement an Operational Radiation Protection Programme (ORPP) at their research reactor facilities; and • Develop and implement an Operational Radioactive Waste Management Programme (ORWMP) at their research reactor facilities. To accomplish these objectives, the workshop aims to equip the participants with the necessary information, conceptual understanding and knowledge that will enable them to carry out these tasks. By the end of the workshop, the participants will be able to: – Understand the basic concepts of radiation protection aimed at reducing the radiation hazard and radiation doses; – Understand the role of the ORPP to ensure the effective control of external and internal doses to workers and to the public and of releases to the environment; – Understand the risk assessment followed by a step-by-step approach in developing and implementing the ORPP; – Understand the importance of the optimization principle and a suitable dose limitation system; – Understand the role and responsibilities of the operating organization in developing and implementing the ORPP; – Develop operational radiation protection procedures and effectively use them; – Understand the importance of area classification including access control to such areas and the provision of information on actual dose and contamination levels; – Establish a training and surveillance programme for radiation protection officers and reactor operating staff; – Define the necessary arrangements for the response to an emergency; – Understand the basic concepts of establishing a ORWMP; – Establish the necessary provisions for keeping the generation of radioactive waste to the minimum practicable, in terms of both activity and volume; – Establish the necessary provisions for appropriate collection, characterization, classification, segregation and

  14. U.S. Department of Energy University Reactor Instrumentation Program Final Report for 1992-94 Grant for the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    Overall, the instrumentation obtained under the first year 1992-93 University Reactor Instrumentation Program grant assured that the goals of the program were well understood and met as well as possible at the level of support provided for the University of Florida Training Reactor facility. Though the initial grant support of $21,000 provided toward the purchase of $23,865 of proposed instrumentation certainly did not meet many of the facility's needs, the instrumentation items obtained and implemented did meet some critical needs and hence the goals of the Program to support modernization and improvement of reactor facilities such as the UFTR within the academic community. Similarly, the instrumentation obtained under the second year 1993-94 University Reactor Instrumentation Program grant again met some of the critical needs for instrumentation support at the UFTR facility. Again, though the grant support of $32,799 for proposed instrumentation at the same cost projection does not need all of the facility's needs, it does assure continued facility viability and improvement in operations. Certainly, reduction of forced unavailability of the reactor is the most obvious achievement of the University Reactor Instrumentation Program to date at the UFTR. Nevertheless, the ability to close out several expressed-inspection concerns of the Nuclear Regulatory Commission with acquisition of the low level survey meter and the area radiation monitoring system is also very important. Most importantly, with modest cost sharing the facility has been able to continue and even accelerate the improvement and modernization of a facility, especially in the Neutron Activation Analysis Laboratory, that is used by nearly every post-secondary school in the State of Florida and several in other states, by dozens of departments within the University of Florida, and by several dozen high schools around the State of Florida on a regular basis. Better, more reliable service to such a broad

  15. A Fully-reconstituted Safety Basis for the University of Florida Training Reactor

    International Nuclear Information System (INIS)

    The University of Florida Training Reactor, (UFTR), is restructuring its licensing framework to help facilitate its upgrade to a digital controls system. The strategy focuses on creating an encompassing safety analysis to prove, unequivocally, that the UFTR represents a negligible risk to the health and safety of the public. This will allow a change in the Limiting Safety System Settings (LSSS) and for a reduction in the number of safety system and components (SSCs) that are defined as safety related by the Code of Federal Regulations. The safety analysis is predicated on two postulated events: a rapid insertion of a large amount of positive reactivity and the release of fission products caused by mechanical damage to a spent fuel plate. These have been selected as limiting scenarios, whose extremity bound all other accidents of consequence. The rapid insertion of positive reactivity was modeled using PARET/ANL software. Analysis shows that a reactivity insertion of $2.00 creates a maximum peak fuel temperature approximately 250 .deg. below the failure limit of 530C. The radioisotope inventory of the fission products is modeled using the ORIGEN-S module in SCALE6.1. The doses to the workers and members of the public are determined with COMPLY software and shows that the worstcase hypothetical exposures are approximately 6.5% of the annual regulatory limit

  16. A journey through the pre-Budapest-2013 k0 Users Workshops

    International Nuclear Information System (INIS)

    A short survey is given of the five meetings preceding the 6th International k0 Users Workshop that was held from 22 to 27 September in Budapest/Hungary. These predecessors were the Workshops in: Gent/Belgium (1992), Ljubljana/Slovenia (1996), Bruges/Belgium (2001), Funchal-Madeira/Portugal (2005) and Belo Horizonte/Brazil (2009). (author)

  17. Some rare species of the genera Amphidelus and Aporcelaimellus (Nematoda: Dorylaimida) from Sas Hill, Budapest, Hungary

    OpenAIRE

    Kiss, M

    2009-01-01

    Four rare nematode species from Sas Hill in Budapest are described and illustrated. They are Amphidelus lagrecai Vinciguerra & De Francisci, 1973, Amphidelus coluber Andrássy, 1973, Aporcelaimellus alius Andrássy, 2002 and Apor¬ce¬laimellus amylovorus (Thorne & Swanger, 1936) Heyns, 1965. Of them, A. lagrecai is new to the fauna of Hungary.

  18. Some rare species of the genera Amphidelus and Aporcelaimellus (Nematoda: Dorylaimida from Sas Hill, Budapest, Hungary

    Directory of Open Access Journals (Sweden)

    Kiss, M.

    2009-06-01

    Full Text Available Four rare nematode species from Sas Hill in Budapest are described and illustrated. They are Amphidelus lagrecai Vinciguerra & De Francisci, 1973, Amphidelus coluber Andrássy, 1973, Aporcelaimellus alius Andrássy, 2002 and Apor¬ce¬laimellus amylovorus (Thorne & Swanger, 1936 Heyns, 1965. Of them, A. lagrecai is new to the fauna of Hungary.

  19. The role of the IPR-R1 TRIGA Mark I research reactor in nuclear education and training in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Andrea V.; Mesquita, Amir Z.; Maretti Junior, Fausto; Souza, Rose Mary G.P.; Dalle, Hugo M.; Paiano, Silvestre, E-mail: avf@cdtn.br, E-mail: amir@cdtn.br, E-mail: fmj@cdtn.br, E-mail: souzarm@cdtn.br, E-mail: dallehm@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The revival of the Brazilian nuclear program has anticipated a large demand for training in nuclear technology. The Nuclear Technology Development Center (CDTN), a research institute of the Brazilian Nuclear Energy Commission (CNEN), offers the Operator Training Course on Research Reactors (CTORP). This course has existed since 1974 and about 258 workers were certificated by CTORP. This article describes the activities of CTORP and presents a proposal for its activities expansion in order to provide the current demand in the nuclear technology. Experimental research projects programs would be created in the postgraduate course at CDTN. In addition to the normal reactor physics topics addressed by CTORP, new subjects such as thermal hydraulic and instrumentation should be added and discussed too. (author)

  20. The role of the IPR-R1 TRIGA Mark I research reactor in nuclear education and training in Brazil

    International Nuclear Information System (INIS)

    The revival of the Brazilian nuclear program has anticipated a large demand for training in nuclear technology. The Nuclear Technology Development Center (CDTN), a research institute of the Brazilian Nuclear Energy Commission (CNEN), offers the Operator Training Course on Research Reactors (CTORP). This course has existed since 1974 and about 258 workers were certificated by CTORP. This article describes the activities of CTORP and presents a proposal for its activities expansion in order to provide the current demand in the nuclear technology. Experimental research projects programs would be created in the postgraduate course at CDTN. In addition to the normal reactor physics topics addressed by CTORP, new subjects such as thermal hydraulic and instrumentation should be added and discussed too. (author)

  1. Power Excursion Accident Analysis of Research Water Reactor

    International Nuclear Information System (INIS)

    A three-dimensional neutronic code POWEX-K has been developed, and it has been coupled with the sub-channel thermal-hydraulic core analysis code SV based on the Single Mass Velocity Model. This forms the integrated neutronic/thermal hydraulics code system POWEX-K/SV for the accident analysis. The Training and Research Reactors at Budapest University of Technology and Economics (BME-Reactor) has been taken as a reference reactor. The cross-section generation procedure based on WIMS. The code uses an implicit difference approach for both the diffusion equations and thermal-hydraulics modules, with reactivity feedback effects due to coolant and fuel temperatures. The code system was applied to analyzing power excursion accidents initiated by ramp reactivity insertion of 1.2 $. The results show that the reactor is inherently safe in case of such accidents i.e. no core melt is expected even if the safety rods do not fall into the core

  2. A survey of innovative trains of thoughts for nuclear power fuel cycle engineering of pressurized water reactor

    International Nuclear Information System (INIS)

    Based on achievements in technique innovation of nuclear power fuel cycle engineering of pressurized water reactor since the late 1970's, the progress is sumed up and classified as three trains of innovation thoughts: once-through cycle reprocessing fuel cycle and reprocessing-partitioning-transmutation cycle. From angles of sustainable development of fission nuclear power utilization and development of circuit economy, the necessity is inquired and analyzed to develop the reprocessing-partitioning-transmutation closed circulating. (authors)

  3. Modelling of the WWER-440 type reactor emergency conditions associated with a pipeline breakage while training equipment designing

    International Nuclear Information System (INIS)

    A theoretical investigation of the emergency conditions connected with the rupture of 500 mm dia main circulating pipe of the primary circuit of the WWER-440 type reactor nuclear power plant has been carried out. The calculations have been performed using the ''''Minsk-32'' digital computer. A method is described of data presentation in the form suitable for modelling of transients in conformity with the training equipment

  4. The first critical experiment with a LEU Russian fuel IRT-4M at the training reactor VR-1

    International Nuclear Information System (INIS)

    A critical experiment is a standard part of training of students at the Training Reactor VR-1 operated within the Faculty of Nuclear Sciences and Physical Engineering at the Czech Technical University in Prague. In autumn 2005 the HEU fuel IRT-3M with enrichment 36 % 235U was replaced by the LEU fuel IRT-4M with enrichment 19.7 % 235U. The fuel replacement at the VR-1 Reactor is a part of an international program RERTR. This Paper presents basic information about preparation for the fuel replacement and approaching of the first critical state with the new zone configuration C1 which replaced B1 core with the old IRT-3M fuel. The whole process was carried out according to the Czech law and the relevant international recommendations. The experience with the VR-1 operation confirms the assumption that the C1 core configuration will be suitable from the point of view of the reactivity balance for the long term safe operation of the Training Reactor VR-1. (author)

  5. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit

  6. Development of the learning-training lessons for functional-analytical training facility of NPP with WWER-1000 reactor

    International Nuclear Information System (INIS)

    General principles of construction of functional-analytical training facility of a NPP, which represents the computation system consisting of the ES-1045 type computer and personal computers, are considered. The KIPR program used for the ES computer describes stationary and dynamic regimes of a power unit real time operation. The personal computers perform service functions of displaying the information required by an operator. The high efficiency of the algorithms used for NPP operator training is proved

  7. Safety evaluation report related to the renewal of the operating license for the training and research reactor at the University of Maryland (Docket No. 50-166)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Maryland (UMD) for a renewal of operating license R-70 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Maryland and is located at a site in College Park, Prince Georges County, Maryland. The staff concludes that this training reactor facility can continue to be operated by UMD without endangering the health and safety of the public

  8. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Utah (Docket No. 50-407)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Utah (UU) for a renewal of operating license R-126 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Utah and is located on its campus in Salt Lake City, Salt Lake County, Utah. The staff concludes that this training reactor facility can continue to be operated by UU without endangering the health and safety of the public

  9. Safety Evaluation Report Related to the Renewal of the Operating License for the TRIGA Training and Research Reactor at the University of Utah

    OpenAIRE

    United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulations

    1985-01-01

    This Safety Evaluation Report for the application filed by the University of Utah (UU) for a renewal of operating license R-126 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission. The facility is owned and operated by the University of Utah and is located on its campus in Salt Lake City, Salt Lake County, Utah. The staff concludes that this training reactor facility can conti...

  10. Simulation of the Syrian miniature neutron source reactor for training operators on the analysis of its anticipated operational accidents

    International Nuclear Information System (INIS)

    For the purpose of training operators and other educational aspects, a mathematical model capable of assessing potential accidents and safety implications of the research Miniature Neutron Source Reactor (MNSR) has been developed. The model considers relevant physical phenomena that govern the core such as reactor kinetics, reactivity feedbacks due to coolant temperature and xenon, and thermal hydraulics. Natural convection and point kinetics including the prompt jump and complete mixing approximations were employed. Peak power, reactivity core load, core outlet temperature, and other variables are predicted during self-limiting power excursions. Compared to related references, close results have been obtained. The simulating model proves to be a useful tool to train operators and students to assess qualitatively the transient behaviour of the MNSR as a result of sudden reactivity insertion in the core. In addition, the model was utilized to verify some of the design basis accidents already presented in both the Safety Analysis Report (SAR) and the Commissioning Report (CR) of the reactor. Furthermore, the dynamic model generates other core variables that are of interest to update the SAR on one side, and confirms others measured and reported in the CR

  11. Simulation of the Syrian Miniature Neutron Source Reactor for training operators on the analysis of its anticipated operational accidents

    International Nuclear Information System (INIS)

    For the purpose of training operators and other educational aspects, a mathematical model capable of assessing potential accidents and safety implications of the research Miniature Neutron Source Reactor (MNSR) has been developed. The model considers relevant physical phenomena that govern the core such as reactor kinetics, reactivity feed-backs due to coolant temperature and xenon, and thermal hydraulics. Natural convection and point kinetics including the prompt jump and complete mixing approximations were employed. Peak power, reactivity core load, core outlet temperature, and other variables are predicted during self-limiting power excursions. Compared to related references, close results have been obtained. The simulating model proves to be a useful tool to train operators and students to assess qualitatively the transient behaviour of the MNSR as a result of sudden reactivity insertion in the core. In addition, the model was utilized to verify some of the design basis accidents already presented in both the Safety Analysis Report (SAR) and the Commissioning Report (CR) of the reactor, as can be seen in Table 1. Furthermore, the dynamic model generates other core variables that are of interest to update the SAR on one side, and confirms others measured and reported in the CR. (author)

  12. Origin of bank filtered groundwater on the Csepel Island (below Budapest)

    International Nuclear Information System (INIS)

    The drinking water for the Hungarian capitol is mainly covered from bank filter wells of the riparian aquifer system of the River Danube. A part of these wells are located on the Csepel Island (south of Budapest). The aquifer system is highly vulnerable for pollution coming either from the Danube or from the background shallow groundwater. Budapest contaminates continuously the Danube water with communal and industrial wastewater. The contamination can have an effect on the quality of the bank-filtered water on the Csepel Island. The knowledge of the flowing system in the alluvial aquifer is very important for providing high quality drinking water and for protecting the drinking water resources. The aims of this study are to determine the origin of the exploited water and the shallow groundwater, the ratio Danube water/background water, and the average transit time of the infiltrated Danube water for the observed wells

  13. 75 FR 54657 - University of Florida; University of Florida Training Reactor; Environmental Assessment and...

    Science.gov (United States)

    2010-09-08

    ... UFTR. In addition, samples are collected of water, soil, and vegetation at twenty-two locations within...-central part of Florida about midway between the Gulf of Mexico and the Atlantic Ocean. The reactor is housed in a vault-type building which serves as a confinement. The Nuclear Reactor Building and its...

  14. Territorial consumption issues of urban sprawl in Central European capitals, especially in the Budapest metropolitan region

    OpenAIRE

    Viktória Szirmai; Zsuzsanna Váradi; Szilvia Kovács; Júlia Schuchmann; Nóra Baranyai

    2011-01-01

    The article presents the urban sprawl phenomena in Central European capitals and in the Budapest metropolitan region, based on statistical data and empirical survey analysis. The study concentrates on territorial consumption issues, which are determined by the suburbanisation processes, the changes of city and outskirt populations, and the transformation of land use patterns. It describes the negative environmental and social impacts (air pollution, spatial and social stratification phenomena...

  15. Zooplankton (Cladocera, Copepoda) dynamics in the River Danube upstream and downstream of Budapest, Hungary

    OpenAIRE

    Vadadi-Fülöp, Cs.

    2009-01-01

    The spatial distribution and seasonal dynamics of zooplankton (Cladocera, Copepoda) were studied in the River Danube near Budapest, Hungary. The investigated river section was relatively poor in plankton, nauplii dominated. A total of 36 species was recorded of which Acanthocyclops robustus, Thermocyclops crassus, Bosmina longirostris were the most abundant. There was a downstream increase in copepod densities, however, no other remarkable differences could be observed between the profiles up...

  16. Budapest Gay Pride og mødet med højreekstremismens grimme ansigt

    DEFF Research Database (Denmark)

    Ginnerskov Hansen, Mette

    2013-01-01

    Den årlige Gay Pride Parade i Ungarns hovedstad Budapest blev afholdt den 6. juli 2013, og med knap 8000 deltagere blev begivenheden den største i sin 16 årige levetid. Trods det imponerende opbud blev paraden dog ikke kun en fejring af menneskelig mangfoldighed, men bød også på et skræmmende møde...

  17. INJECTING EQUPMENT SHARING AND PERCEPTION OF HIV AND HEPATITIS RISK AMONG INJECTING DRUG USERS IN BUDAPEST

    OpenAIRE

    Rácz, József; Gyarmathy, V. Anna; Neaigus, Alan; Ujhelyi, Eszter

    2007-01-01

    In Central European states, rates of HIV among IDUs have been low although HCV infection is widespread. The goal of our study was to assess HIV infection, risk perceptions and injecting equipment sharing among injection drug users in Budapest, Hungary. Altogether 150 IDUs were interviewed (121 structured between 1999-2000 and 29 ethnographic between 2003-2004). The majority of them injected heroin (52% and 79%) and many injected amphetamines (51% and 35%). One person tested positive for HIV. ...

  18. Pilot program: NRC severe reactor accident incident response training manual: Public protective actions: Predetermined criteria and initial actions

    International Nuclear Information System (INIS)

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Public Protective Actions - Predetermined Criteria and Initial Actions is the fourth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume reviews public protective action criteria and objectives, their bases and implementation, and the expected public response. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  19. Pilot program: NRC [Nuclear Regulatory Commission] severe reactor accident incident response training manual: Overview and summary of major points

    International Nuclear Information System (INIS)

    This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assessment. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance of license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

  20. A Prediction Study of Aluminum Alloy Oxidation of the Fuel Cladding in Jordan Research and Training Reactor

    International Nuclear Information System (INIS)

    U3Si2-Al dispersion fuel with Al cladding will be used for Jordan Research and Training Reactor (JRTR). Aluminum alloy cladding experiences the oxidation layer growth on the surface during the reactor operation. The formation of oxides on the cladding affects fuel performance by increasing fuel temperature. According to the current JRTR fuel management scheme and operation strategy for 5 MW power, a fresh fuel is discharged after 900 effective full power days (EFPD) with 18 cycles of 50 days loading. For the proper prediction of the aluminum oxide thickness of fuel cladding during the long residence time, a reliable model is needed. In this work, several oxide thickness prediction models are compared with the measured data from in-pile test by RERTR program. Moreover, specific parametric studies and a preliminary prediction of the aluminum alloy oxidation using the latest model are performed for JRTR fuel

  1. Origin and quality of bank filtered groundwater near Budapest: An evaluation of isotope data

    International Nuclear Information System (INIS)

    The infiltration of the Danube water into the aquifers of the Szentendre and Csepel Islands was studied by stable oxygen isotope ratio measurements. On the Szentendre Island the Danube water component was identified in all the wells sampled. Although the ratio of the Danube water varies well-by-well the Danube 'flows' under the whole island. On the Csepel Island the infiltration of the Danube water is not so intensive. it could not be identified in the wells along the mid-line of the island. The δ18O values of the Danube at Vienna and Budapest differ by about 0.4-0.5 per mille so for isotope hydrological investigations of the riparian groundwater system nearby Budapest the δ18O data for Danube at Vienna are not recommended to use, they should be measured at Budapest. The transit time calculations made by time series analysis and 2-dimensional hydraulic modelling give fairly comparable results with isotope data for the Halasztelek-5 production well. Water stable isotope measurements through transit time and mixing ratio calculations can be used as an independent calibration of the hydraulic modelling. (author)

  2. The text of the instrument concerning the Agency's assistance to Argentina for the establishment of a training reactor project

    International Nuclear Information System (INIS)

    The document reproduces the text of the Protocol of 30 August 1996 suspending the application of safeguards under the Agreement between the Agency and the Government of Argentina and the Federal Republic of Germany concerning the Agency's assistance for the establishment of a training reactor project in Argentina, which entered into force on 13 March 1970, in light of the provisions for the application of safeguards pursuant to the quadripartite safeguards agreement between Argentina, Brazil, the Brazilian-Argentine Agency for the Accounting and Control of Nuclear Materials and the IAEA

  3. Utilisation of research and training reactors in the study programme of students at the Slovak University of Technology

    International Nuclear Information System (INIS)

    Preparing operating staff for the nuclear industry is and also will be one of the most serious education processes, mainly in the Central-European countries where about 40-50% of the electricity is produced in nuclear power plants. In the Central-European region there exists a very extensive and also effective international collaboration in nuclear industry and education. Similarly, the level of education in universities and technical high schools of this area is also good. Slovak University of Technology Bratislava has established contacts with many universities abroad for utilisation of research and training reactors. (author)

  4. FISA 2009 - 7th European Commission conference on EURATOM research and training in reactor systems. Conference proceedings

    International Nuclear Information System (INIS)

    The main achievements of the first series of projects under EURATOM FP-7 for nuclear research and training activities (2007 to 2011) were discussed. Approximately 500 participants were registered at FISA 2009 and at the 7 post-conference workshops, representing a wide audience of nuclear scientists and decision makers coming from 32 countries worldwide. The focus of the conference was on scientific and technological research in the following areas: nuclear plant life management for existing reactors (Generation II), severe accident management (Generation III), assessment of future nuclear fission systems (Generation IV), partitioning and transmutation systems (innovative fuels), access to large research infrastructures, and nuclear education and training. Special attention was devoted to the societal and industrial goals of GIF: sustainability, industrial competitiveness, safety and reliability, proliferation resistance. (orig.)

  5. Construction and testing of the instrument for neutron holographic study at the Budapest Research Reactor

    International Nuclear Information System (INIS)

    Neutron scattering device dedicated to neutron holography experiments is described. The device is operating at a constant wavelength prepared by a double focusing monochromator. It is equipped by highly efficient shielding, proper collimator, Eulerian cradle, monitor detector, gamma-ray, and neutron detectors as well. Relevant software serves as control for the measurement and data collection. The harmonized application of the components enumerated above makes our device extremely efficient and unparalleled. Two atomic resolution neutron holographic experiments carried out illustrate the efficiency and power of the instrument.

  6. AIR SHIPMENT OF SPENT NUCLEAR FUEL FROM THE BUDAPEST RESEARCH REACTOR

    Energy Technology Data Exchange (ETDEWEB)

    Dewes, J.

    2014-02-24

    The shipment of spent nuclear fuel is usually done by a combination of rail, road or sea, as the high activity of the SNF needs heavy shielding. Air shipment has advantages, e.g. it is much faster than any other shipment and therefore minimizes the transit time as well as attention of the public. Up to now only very few and very special SNF shipments were done by air, as the available container (TUK6) had a very limited capacity. Recently Sosny developed a Type C overpack, the TUK-145/C, compliant with IAEA Standard TS-R-1 for the VPVR/M type Skoda container. The TUK-145/C was first used in Vietnam in July 2013 for a single cask. In October and November 2013 a total of six casks were successfully shipped from Hungary in three air shipments using the TUK-145/C. The present paper describes the details of these shipments and formulates the lessons learned.

  7. First elemental imaging experiments on a combined PGAI and NT setup at the Budapest Research Reactor

    International Nuclear Information System (INIS)

    The European collaboration 'ANCIENT CHARM' (http://ancient-charm.neutron-eu.net/ach/) aims to develop new non-destructive neutron techniques to image the internal composition of complex archaeological objects in order to answer various archaeological questions. Among these techniques, prompt gamma activation imaging (PGAI) and neutron tomography (NT) form a unique combination which can determine the 3D distribution of most elements in objects with a non-destructive procedure. A spatial resolution better than 2 mm has already been achieved in a moderately scattering matrix material. (author)

  8. Nuclear Data Measurements at the PGAA-NIPS Facilities of the Budapest Research Reactor

    International Nuclear Information System (INIS)

    Description of the current status of our PGAA-NIPS experimental setup is presented. Methods, for calculations of thermal capture cross section from partial gamma ray production cross sections are described. High precision radiative capture cross section determination with AMS measurements and methods based on partial gamma ray production cross sections are given for 54Fe(n , γ)55Fe reaction. (author)

  9. McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: The national organization of test research and training reactors

    International Nuclear Information System (INIS)

    This year's TRTR conference is being hosted by the McClellan Nuclear Radiation Center. The conference will be held at the Red Lion Hotel in Sacramento, CA. The conference dates are scheduled for October 11-14, 1994. Deadlines for sponsorship commitment and papers have not been set, but are forthcoming. The newly remodeled Red Lion Hotel provides up-to-date conference facilities and one of the most desirable locations for dining, shopping and entertainment in the Sacramento area. While attendees are busy with the conference activities, a spouses program will be available. Although the agenda has not been set, the Sacramento area offers outings to San Francisco, Pier 39, Ghirardelli Square (famous for their chocolate), and a chance to discover 'El Dorado' in the gold country. Not to forget our own bit of history with visits to 'Old Sacramento and Old Folsom', where antiquities abound, to the world renown train museum and incredible eating establishments. (author)

  10. Selection, training, qualification and licensing of Three Mile Island reactor operating personnel

    International Nuclear Information System (INIS)

    The various programs which were intended to staff Three Mile Island with competent, trained operators and supervisors are reviewed. The analysis includes a review of the regulations concerning operator training and licensing, and describes how the requirements were implemented by the NRC, Metropolitan Edison Company, and Babcock and Wilcox Company. Finally the programs conducted by these three organisations are evaluated. (U.K.)

  11. Nuclear power reactor security personnel training and qualification plan reviewer workbook

    International Nuclear Information System (INIS)

    The Training and Qualification Plan Reviewer Workbook has been developed to provide the information required for evaluating the adequacy of the Training and Qualification (T and Q) Plans developed to meet the requirements of 10 CFR 73.55(b)(4) and 10 CFR 73, Appendix B

  12. Dynamic Comparison of Three- and Four-Equation Reactor Core Models in a Full-Scope Power Plant Training Simulator

    International Nuclear Information System (INIS)

    A comparative analysis of the dynamic behavior of a boiling water reactor in a full-scope power plant simulator for operator training is presented. Three- and four-equation reactor core models were used to examine three transients following tests described in acceptance test procedures: scram, loss of feedwater flow, and closure of main isolation valves. The three-equation model consists of water and steam mixture momentum, including mass and energy balances. The four-equation model is based on liquid and gas phase mass balances, together with a drift-flux approach for the analysis of phase separation. Analysis of the models showed that the scram transient was slightly different for three- and four-equation models. The drift-flux effects can explain such differences. Regarding the loss-of-feedwater transient, the predicted steam flow after scram is larger for the three-equation model. Finally, for the transient related to the closure of main steam isolation valves, the three-equation model provides slightly different results for the pressure change, which affects reactor level behavior

  13. Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Alatrash, Yazan [Advanced Nuclear Engineering System Department, Korea University of Science and Technology (UST), 217 Gajeong-ro Yuseong-gu, Daejeon 305-350 (Korea, Republic of); Kang, Han-ok; Yoon, Hyun-gi; Seo, Kyoungwoo; Chi, Dae-Young [Korea Atomic Energy Institute (KAERI), 989-111 Daeduk-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Yoon, Juhyeon, E-mail: yoonj@kaeri.re.kr [Korea Atomic Energy Institute (KAERI), 989-111 Daeduk-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Korea University of Science and Technology (UST), Daejeon (Korea, Republic of)

    2015-05-15

    Highlights: • Core flow coastdown phenomena of a research reactor are investigated experimentally. • The experimental dataset is well predicted by a simulation software package, MMS. • The validity and consistency of the experimental dataset are confirmed. • The designed coastdown half time is confirmed to be well above the design requirement. - Abstract: Many low-power research reactors including the Jordan Research and Training Reactor (JRTR) are designed to have a downward core flow during a normal operation mode for many convenient operating features. This design feature requires maintaining the downward core flow for a short period of time right after a loss of off-site power (LOOP) accident to guarantee nuclear fuel integrity. In the JRTR, a big flywheel is installed on a primary cooling system (PCS) pump shaft to passively provide the inertial downward core flow at an initial stage of the LOOP accident. The inertial pumping capability during the coastdown period is experimentally investigated to confirm whether the coastdown half time requirement given by safety analyses is being satisfied. The validity and consistency of the experimental dataset are evaluated using a simulation software package, modular modeling system (MMS). In the MMS simulation model, all of the design data that affect the pump coastdown behavior are reflected. The experimental dataset is well predicted by the MMS model, and is confirmed to be valid and consistent. The designed coastdown half time is confirmed to be well above the value required by safety analysis results. (wwwyoon@gmail.com)

  14. Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

    International Nuclear Information System (INIS)

    Highlights: • Core flow coastdown phenomena of a research reactor are investigated experimentally. • The experimental dataset is well predicted by a simulation software package, MMS. • The validity and consistency of the experimental dataset are confirmed. • The designed coastdown half time is confirmed to be well above the design requirement. - Abstract: Many low-power research reactors including the Jordan Research and Training Reactor (JRTR) are designed to have a downward core flow during a normal operation mode for many convenient operating features. This design feature requires maintaining the downward core flow for a short period of time right after a loss of off-site power (LOOP) accident to guarantee nuclear fuel integrity. In the JRTR, a big flywheel is installed on a primary cooling system (PCS) pump shaft to passively provide the inertial downward core flow at an initial stage of the LOOP accident. The inertial pumping capability during the coastdown period is experimentally investigated to confirm whether the coastdown half time requirement given by safety analyses is being satisfied. The validity and consistency of the experimental dataset are evaluated using a simulation software package, modular modeling system (MMS). In the MMS simulation model, all of the design data that affect the pump coastdown behavior are reflected. The experimental dataset is well predicted by the MMS model, and is confirmed to be valid and consistent. The designed coastdown half time is confirmed to be well above the value required by safety analysis results. (wwwyoon@gmail.com)

  15. Reactors

    International Nuclear Information System (INIS)

    Purpose: To provide a spray cooling structure wherein the steam phase in a bwr reactor vessel can sufficiently be cooled and the upper cap and flanges in the vessel can be cooled rapidly which kept from direct contaction with cold water. Constitution: An apertured shielding is provided in parallel spaced apart from the inner wall surface at the upper portion of a reactor vessel equipped with a spray nozzle, and the lower end of the shielding and the inner wall of the vessel are closed to each other so as to store the cooling water. Upon spray cooling, cooling water jetting out from the nozzle cools the vapor phase in the vessel and then hits against the shielding. Then the cooling water mostly falls as it is, while partially enters through the apertures to the back of the shielding plate, abuts against stoppers and falls down. The stoppers are formed in an inverted L shape so that the spray water may not in direct contaction with the inner wall of the vessel. (Horiuchi, T.)

  16. Design of Seismic Test Rig for Control Rod Drive Mechanism of Jordan Research and Training Reactor

    International Nuclear Information System (INIS)

    The reactor assembly is submerged in a reactor pool filled with water and its reactivity is controlled by locations of four control absorber rods(CARs) inside the reactor assembly. Each CAR is driven by a stepping motor installed at the top of the reactor pool and they are connected to each other by a tie rod and an electromagnet. The CARs scram the reactor by de-energizing the electromagnet in the event of a safe shutdown earthquake(SSE). Therefore, the safety function of the control rod drive mechanism(CRDM) which consists of a drive assembly, tie rod and CARs is to drop the CAR into the core within an appropriate time in case of the SSE. As well known, the operability for complex equipment such as the CRDM during an earthquake is very hard to be demonstrated by analysis and should be verified through tests. One of them simulates the reactor assembly and the guide tube of the CAR, and the other one does the pool wall where the drive assembly is installed. In this paper, design of the latter test rig and how the test is performed are presented. Initial design of the seismic test rig and excitation table had its first natural frequency at 16.3Hz and could not represent the environment where the CRDM was installed. Therefore, experimental modal analyses were performed and an FE model for the test rig and table was obtained and tuned based on the experimental results. Using the FE model, the design of the test rig and table was modified in order to have higher natural frequency than the cutoff frequency. The goal was achieved by changing its center of gravity and the stiffness of its sliding bearings

  17. Design of Seismic Test Rig for Control Rod Drive Mechanism of Jordan Research and Training Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sun, Jongoh; Kim, Gyeongho; Yoo, Yeonsik; Cho, Yeonggarp; Kim, Jong In [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The reactor assembly is submerged in a reactor pool filled with water and its reactivity is controlled by locations of four control absorber rods(CARs) inside the reactor assembly. Each CAR is driven by a stepping motor installed at the top of the reactor pool and they are connected to each other by a tie rod and an electromagnet. The CARs scram the reactor by de-energizing the electromagnet in the event of a safe shutdown earthquake(SSE). Therefore, the safety function of the control rod drive mechanism(CRDM) which consists of a drive assembly, tie rod and CARs is to drop the CAR into the core within an appropriate time in case of the SSE. As well known, the operability for complex equipment such as the CRDM during an earthquake is very hard to be demonstrated by analysis and should be verified through tests. One of them simulates the reactor assembly and the guide tube of the CAR, and the other one does the pool wall where the drive assembly is installed. In this paper, design of the latter test rig and how the test is performed are presented. Initial design of the seismic test rig and excitation table had its first natural frequency at 16.3Hz and could not represent the environment where the CRDM was installed. Therefore, experimental modal analyses were performed and an FE model for the test rig and table was obtained and tuned based on the experimental results. Using the FE model, the design of the test rig and table was modified in order to have higher natural frequency than the cutoff frequency. The goal was achieved by changing its center of gravity and the stiffness of its sliding bearings.

  18. Demonstration of core neutronic calculation for research and training reactors via SCALE4.4

    International Nuclear Information System (INIS)

    In this work, full core modelling is performed to improve neutronic analyses capability for nuclear research reactors using SCALE4.4 system. KENOV.a module of SCALE4.4 system is utilized for full core neutronic analysis. The ORIGEN-S module is also coupled with the KENOV.a module to perform burnup dependent core analyses. Results of control rod worths for 1st cycle of Cekmece TR-2 research reactor are presented. In particular, coupling of KENOV.a and ORIGEN-S modules of SCALE4.4 is discussed. The preliminary results of 2-D burnup dependent neutronic calculations are also given. (author)

  19. Training simulator for nuclear power plant reactor coolant system and method

    International Nuclear Information System (INIS)

    A description is given of a method and system for simulating the dynamic real-time operation of a nuclear power plant wherein a plurality of remote control devices provides input data to a digital computer to calculate physical values corresponding to plant operation to operate indicating devices for monitoring the physical operation of the plant. The simulation includes the dynamic operation of the reactor coolant loops for normal, reverse, and natural coolant flow and corresponding heat transfer; also the simulation of the pressurizer in its solid, bubble, and transitional states together with its interaction with the reactor coolant loops

  20. Education & Training in Support to Sodium Fast Reactors Around the World

    International Nuclear Information System (INIS)

    The results of these ambitious and long term strategies are: - first the creation of a new generation of skilled nuclear engineers in the field. - secondly a share of knowledge gained through experimental studies carried out in research laboratories as well as feedback from fast reactors operation, - thirdly a standardized information on safety, - and finally the creation of a “Sodium Fast Reactor community” is promoted, able to debate, share the knowledge and suggest new tracks for a better definition of design and operating rules

  1. Euratom research and training in nuclear reactor safety: Towards European research and the higher education area

    International Nuclear Information System (INIS)

    In this invited lecture, research and training in nuclear fission are looked at from a European perspective with emphasis on the three success factors of any European policy, namely: common needs, vision and instruments, that ought to be strongly shared amongst the stakeholders across the Member States concerned. As a result, the following questions are addressed: What is driving the current EU trend towards more research, more education and more training, in general? Regarding nuclear fission, in particular, who are the end-users of Euratom 'research and training' and what are their expectations from EU programmes? Do all stakeholders share the same vision about European research and training in nuclear fission? What are the instruments proposed by the European Commission (EC) to conduct joint research programmes of common interest for the nuclear fission community? In conclusion, amongst the stakeholders in Europe, there seems to be a wide consensus about common needs and instruments, but not about a common vision regarding nuclear. (author)

  2. Implementation and training methodology of subcritical reactors neutronic calculations triggered by external neutron source and applications

    International Nuclear Information System (INIS)

    This works had as goal to investigate calculational methodologies on subcritical source driven reactor, such as Accelerator Driven Subcritical Reactor (ADSR) and Fusion Driven Subcritical Reactor (FDSR). Intense R and D has been done about these subcritical concepts, mainly due to Minor Actinides (MA) and Long Lived Fission Products (LLFP) transmutation possibilities. In this work, particular emphasis has been given to: (1) complement and improve calculation methodology with neutronic transmutation and decay capabilities and implement it computationally, (2) utilization of this methodology in the Coordinated Research Project (CRP) of the International Atomic Energy Agency Analytical and Experimental Benchmark Analysis of ADS and in the Collaborative Work on Use of Low Enriched Uranium in ADS, especially in the reproduction of the experimental results of the Yalina Booster subcritical assembly and study of a subcritical core of IPEN / MB-01 reactor, (3) to compare different nuclear data libraries calculation of integral parameters, such as keff and ksrc, and differential distributions, such as spectrum and flux, and nuclides inventories and (4) apply the develop methodology in a study that may help future choices about dedicated transmutation system. The following tools have been used in this work: MCNP (Monte Carlo N particle transport code), MCB (enhanced version of MCNP that allows burnup calculation) and NJOY to process nuclear data from evaluated nuclear data files. (author)

  3. Computerized reactor monitor and control for nuclear reactors

    International Nuclear Information System (INIS)

    The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

  4. Safety evaluation report related to the renewal of the operating license for the Worcester Polytechnic Institute open-pool training reactor, Docket No. 50-134

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the Worcester Polytechnic Institute (WPI) for a renewal of Operating License R-61 to continue to operate the WPI 10-kW open-pool training reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Worcester Polytechnic Institute and is located on the WPI campus in Worcester, Worcester County, Massachusetts. The staff concludes that the reactor facility can continue to be operated by WPI without endangering the health and safety of the public

  5. Urban modelling for Budapest using the Weather Research and Forecasting model

    Science.gov (United States)

    Göndöcs, Júlia; Breuer, Hajnalka; Pongrácz, Rita; Bartholy, Judit

    2016-04-01

    The population of Earth is continuously growing, and due to urbanisation it is quite concentrated in metropolitan areas. Overall, cities cover almost 2% of the global surface causing several environmental and social issues. These artificial surface covers significantly modify the surface energy exchange processes through modification of naturally covered lands resulting in altered local wind and temperature patterns because of the presence of buildings. The architectures' three-dimensional extensions certainly affect the incoming radiation, the sky-view factors as well, as the 3D wind fields, resulting in specific local microclimate at each metropolitan area. The increased temperature in the central built-up areas and the cooler surrounding of the cities lead to the urban heat island phenomenon, which is widely studied both with observations and numerical models. The Weather Research and Forecasting (WRF) mesoscale model coupled to multilayer urban canopy parameterisation is used to investigate this phenomenon for Budapest and its surroundings. Before starting the simulations, the detailed surface has to be set up according to the actual conditions, for which CORINE and OpenStreetMap databases are used, both including buildings, different land use categories, and waterbodies. The new land use distribution serving as input for WRF runs distinguishes three urban categories: (i) low-intensity residential, (ii) high-intensity residential, and (iii) commercial/industrial. For the simulations the initial meteorological fields are derived from the publicly available GFS (Global Forecast System) outputs. Simulations are completed for one-week-long periods in summer and winter in 2015, for which we selected periods with the atmospheric conditions of weak wind and clear sky. In order to keep the stability of the simulations, the entire downscaling is carried out in several steps using gradually smaller domains embedded to each other. Thus, three embedded target areas have

  6. Calculations and Experiments on the Poison Sheet Reactivity in the Hitachi Training Reactor

    International Nuclear Information System (INIS)

    A new method for calculating the control-rod reactivity is derived within the framework of the variational theory, which can be used for an arbitrary shaped reactor with infinite height. The reactivity of the poison sheets was measured in HTR in order to check the variational method and the conventional method. The agreement among the variational method, the conventional method and the experiment was very good. (author)

  7. Survey of foreign reactor operator qualifications, training, and staffing requirements. Final report

    International Nuclear Information System (INIS)

    The report is a compilation of the data obtained from a survey of foreign nuclear power plant operator requirements. Included among the considerations are: (1) shift staffing; (2) operator eligibility; (3) operator training programs; (4) operator licensing or certification; and (5) operator retraining. The data obtained from this survey are presented in matrix form and contrasted with U.S. requirements

  8. Modular design of an instructor's console for a real-time nuclear reactor training simulator

    International Nuclear Information System (INIS)

    A modular design of an Instructor's Console for a real-time operator training simulator is presented in this paper. The particular design addresses a console that was implemented in phases. The console was developed in a simulation environment that supports multiprocessing. The design and subsequent implementation is discussed

  9. Characterization and Application of the Thermal Neutron Radiography Beam in the Egyptian Second Experimental and Training Research Reactor (ETRR-2)

    International Nuclear Information System (INIS)

    The Experimental, Training, Research Reactor (ETRR-2) is an open-pool multipurpose reactor (MPR) with a core power of 22 MWth cooled and moderated by light water and reflected with beryllium. It has four neutron beams and a thermal column as the main experimental devices. The neutron radiography facility unit utilizes one of the radial beam tubes. The track-etch technique using nitrocellulose films and converter screen is applied. In this work, the radial neutron beam for the thermal neutron radiography facility has been characterized and the following values were determined: thermal flux of 1.5 @ 107 π/cm2 s, πth/ ratio of 0.1@106π cm-2@ mR-1; a Cd ratio of 10.26, a resolution of 0.188 mm, and L/D ratio of 117.3. This characterization verifies the design parameters of the unit. Various radiographs were taken and results indicate that the neutron radiography facility of the ETRR-2 holds promising opportunities for nuclear as well as nonnuclear applications.

  10. Effects of land use on chemical water quality of three small streams in Budapest

    Science.gov (United States)

    Angyal, Zsuzsanna; Sárközi, Edit; Gombás, Ádám; Kardos, Levente

    2016-02-01

    The location and development of cities has been influenced basically by various environmental factors. However, the relationship is bilateral, because not only the environment can affect the city, but the city can affect the environment in different ways, depending on recovery. This is especially true in the case of large cities such as Budapest where the different geological, geomorphological, hydrological, soil and bio-geographical conditions can be changed in very small areas, which implies that land use can be also modified as well. The aim of our study was to determine the chemical water quality of three small streams in Budapest which have same water flow and compare the field and the laboratory test results. Between many natural characteristics of these streams similarity is evident, however, several differences were found between the watersheds in terms of human land use. Statistical data analysis was performed as well, which was the aim to explore the relationship between the parameters. Overall, according to our study it can be concluded, the small streams have similar water chemical properties, but some parameters need special attention in the future, because the investigated small streams can be categorized into polluted and sometimes heavily polluted category.

  11. Challenges and experiences of a participative green space development in Budapest-Józsefváros

    Directory of Open Access Journals (Sweden)

    Attila Csaba Kondor

    2008-01-01

    Full Text Available This article is an attempt to present the theoretical and practical backgrounds of a participative green space development in Hungary. The renewed green space, Mátyás square is located in District VIII of Budapest, known as Józsefváros. The neighbourhood of Mátyás square had a very negative image, neglected residential areas extended into the heart of the district suffered by different social problems. The local government of Józsefváros elaborated the so called Magdolna Quarter Programme, that contains the details of the social rehabilitation of surroundings of Mátyás square. In frame of this programme – co-financed by EU through GreenKeys Project – the square has been renewed, a collaborative and participative green space development has been fulfilled. The authors were engaged in this model programme, they attempt to summarize briefly the experiences of this unique project of Budapest. The local residents were successfully involved into the planning and the implementation of the project. The participation was considerably efficient, however the experience shows that a participative project may be shorter than the project leaders thought. As a result of this activities the Urban Green Space Strategy of Józsefváros and a computer program for monitoring of green spaces were compiled as well.

  12. Analysis of human thermal comfort and its tendencies in Budapest (Hungary)

    Science.gov (United States)

    Nemeth, Akos; Kovacs, Attila

    2013-04-01

    In spite of the fact that the evaluation of the thermal conditions in the urban areas is extremely important and timely, in Budapest (capital of Hungary) very few studies were performed in this direction until now. The aim of this paper is to analyze the differences and changes of the thermal comfort conditions in the last half century (1961-2010) by comparing measurements of two meteorological stations located in different environments of Budapest: one in the central urban area (Local Climate Zone 2 - 'compact midrise') and the other in the suburbs (between Local Climate Zones 6 - 'open lowrise' and A - 'dense trees'). The thermal comfort was characterized by two human bioclimatological comfort indices, the Physiologically Equivalent Temperature (PET) and the Universal Thermal Climate Index (UTCI), for four characteristic times of the day in the examined period. Then the thermal comfort differences between the stations according to two climatic normal periods (1961-1990 and 1981-2010), and the tendencies detected among the periods were also under investigation. For the last decade, 2001-2010, hourly-resolution investigations were carried out. The results indicate that the central area is affected by a higher degree of hot stress and less cold stress. Additionally, the warm stress has become more frequent, however, the cold heat load decreased in both examined area at each time.

  13. District-level local measuring program of the urban environment in Budapest

    Science.gov (United States)

    Dian, Csenge; Pongrácz, Rita; Dezsö, Zsuzsanna; Bartholy, Judit

    2016-04-01

    The natural environment and thus, the climatic conditions are modified by the concentrated human presence of urban areas. In our research we aim to analyze the resulting urban climatic effects in a downtown district of Budapest, Hungary. For this purpose, we have started a measuring program of in-situ measurements in the southern central located district called Ferencváros, which can be found near the river Danube, and mainly consists of 3- and 4-storey older and newly built buildings. The newly built buildings are mainly the results of the Ferencváros local government's efforts to improve the environment for the citizens. Within the framework of the block rehabilitation program, inner parts of the old house blocks were demolished, and inside the blocks common green areas have been created. In our urban climate measurement program air temperature and relative humidity are recorded along a pre-defined path consisting of 22 measuring points, which covers the studied area. The measuring sites are located in different characteristical points of the district, such as green parks, narrow streets, paved squares and roads. In order to calculate the urban heat island intensity, temperature measurements are compared to the hourly recorded data of the Budapest synoptic station (ID number: 12843) located in the southeastern suburb district of the city. After completing an entire year of measurements, the seasonal cycle of temperature and relative humidity differences are analyzed as well, as the diurnal changes and the spatial structure within the study area.

  14. Diagnostics of Nuclear Reactor Accidents Based on Particle Swarm Optimization Trained Neural Networks

    International Nuclear Information System (INIS)

    Automation in large, complex systems such as chemical plants, electrical power generation, aerospace and nuclear plants has been steadily increasing in the recent past. automated diagnosis and control forms a necessary part of these systems,this contains thousands of alarms processing in every component, subsystem and system. so the accurate and speed of diagnosis of faults is an important factors in operation and maintaining their health and continued operation and in reducing of repair and recovery time. using of artificial intelligence facilitates the alarm classifications and faults diagnosis to control any abnormal events during the operation cycle of the plant. thesis work uses the artificial neural network as a powerful classification tool. the work basically is has two components, the first is to effectively train the neural network using particle swarm optimization, which non-derivative based technique. to achieve proper training of the neural network to fault classification problem and comparing this technique to already existing techniques

  15. Ludwig: A Training Simulator of the Safety Operation of a CANDU Reactor

    OpenAIRE

    Gustavo Boroni; Alejandro Clausse

    2011-01-01

    This paper presents the application Ludwig designed to train operators of a CANDU Nuclear Power Plant (NPP) by means of a computer control panel that simulates the response of the evolution of the physical variables of the plant under normal transients. The model includes a close set of equations representing the principal components of a CANDU NPP plant, a nodalized primary circuit, core, pressurizer, and steam generators. The design of the application was performed using the object-oriented...

  16. 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)

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

    International Nuclear Information System (INIS)

    Full text: The development of this work is directly related to the change of an old system by a new Pneumatic Transfer System, used in the transport and transfer of materials that will be irradiated in the IEA-RI reactor, located in the Institute of Energetic and Nuclear Research, IPEN-CNEN/ SP, for Neutron Activation Analysis (NAA) application, specifically in isotopes of short half-life. The new PTS project was developed in: (a) the phases of dimension, details and definitions of the technical specifications of all the mechanic and electro/electronic components of the system: (b) approach and calculation of the delivery and return velocity of this irradiated samples, within the specified parameters in the standards. A structural evaluation of the supporting metallic plate of the reactor core was performed, using specific software, in order to assess its stability, when submitted to the strain of the new PTS irradiation element set. A study of the IEA-RI Reactor operation security was done, due to the impact of the new installation, with risk evaluation of accidents that could be caused by it. The development of the PTS electro-electronic and operation automation, plus the preparation of technical instructions to standardize the cold and hot tests were, also, carried out, to validate the system operation. Due the inclusion of an irradiation device, the new PTS, positioned on the matrix plate was required prove of the mechanical strength of the matrix plate in the new configuration , it was then developed a calculation model using the finite element program ANSYS, by the Structural Mechanics area of the Nuclear Engineering Center (CENM) of IPEN that evaluated the possible configurations with two new elements of irradiation on the matrix plate and checking tensions for the cases evaluated. After computer simulations was verified that the resulting strains for the configurations evaluated are not significant. Whereas the configuration with the new elements of

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

    International Nuclear Information System (INIS)

    Full text: We use the DRAGON and DONJON code in an optimization scheme for selecting alternative fuels in CANDU-6 reactors to develop devices reactivity worth adjustment procedure based on a coupled transport-diffusion calculation scheme that uses 3D supercell calculations and the time-average discrete refueling model. This low computer cost methodology provides various fuel management properties such as average exit burnup and maximal power peaks and also adjuster bank reactivity worth. The method is based on geometrical modifications of the adjuster rods configuration within conservative margins in order to match the total adjuster reactivity worth or the operator's action and decision time when the reactor is spuriously tripped. For the total adjuster reactivity worth optimization, we modify the pure geometrical procedure by doping the stainless steel adjuster rods with cadmium in order to achieve our goal for advanced fuel cycles. For the operator's action and decision time reactivity worth optimization, we implemented an infinite lattice model with neutron leakage in order to follow the xenon-135 built-up in out-of-core condition and to determine how much compensation time the adjuster's reactivity worth provides to operators. This model provides xenon reactivity transient in such a way that we can estimate when the xenon peaks occur, its height and also how long the core is poisoned. This method is applied to reference natural uranium fuel cycle and to a Thorium-DUPIC and a Thorium-SEU fuel cycles. Results show that our goals are achievable, albeit small fuel management penalties.

  19. Proceedings of the 14. International cancer congress held at Budapest, Hungary, 21-27 Aug 1986 v. 2, v. 3

    International Nuclear Information System (INIS)

    The volumes contain abbreviated forms or abstracts of lectures and contributions delivered at the 14th International Cancer Congress held between 21-27 August, 1986 in Budapest, Hungary. Altogether, more than 5000 papers were presented. About 250 items falling in the INIS scope are indexed separately. Volumes 2 and 3 contain about 3000 titles with abstracts of the majority of papers. (author)

  20. Proceedings of the 14. International cancer congress held at Budapest, Hungary, 21-27 Aug 1986 v. 1

    International Nuclear Information System (INIS)

    The volume contains abbreviated forms or abstracts of lectures and contributions delivered at the 14th International Cancer Congress held between 21-27 August, 1986 in Budapest, Hungary. Altogether, more than 5000 papers were presented. About 250 items falling in the INIS scope are indexed separately. Volume 1 contains about 1840 titles with abstracts of the majority of papers. (R.P.)

  1. Ludwig: A Training Simulator of the Safety Operation of a CANDU Reactor

    Directory of Open Access Journals (Sweden)

    Gustavo Boroni

    2011-01-01

    Full Text Available This paper presents the application Ludwig designed to train operators of a CANDU Nuclear Power Plant (NPP by means of a computer control panel that simulates the response of the evolution of the physical variables of the plant under normal transients. The model includes a close set of equations representing the principal components of a CANDU NPP plant, a nodalized primary circuit, core, pressurizer, and steam generators. The design of the application was performed using the object-oriented programming paradigm, incorporating an event-driven process to reflect the action of the human operators and the automatic control system. A comprehensive set of online graphical displays are provided giving an in-depth understanding of transient neutronic and thermal hydraulic response of the power plant. The model was validated against data from a real transient occurring in the Argentine NPP Embalse Río Tercero, showing good agreement. However, it should be stressed that the aim of the simulator is in the training of operators and engineering students.

  2. Research reactors

    International Nuclear Information System (INIS)

    There are currently 284 research reactors in operation, and 12 under construction around the world. Of the operating reactors, nearly two-thirds are used exclusively for research, and the rest for a variety of purposes, including training, testing, and critical assembly. For more than 50 years, research reactor programs have contributed greatly to the scientific and educational communities. Today, six of the world's research reactors are being shut down, three of which are in the USA. With government budget constraints and the growing proliferation concerns surrounding the use of highly enriched uranium in some of these reactors, the future of nuclear research could be impacted

  3. Hospitality, culture and regeneration: urban decay, entrepreneurship and the "ruin" bars of Budapest.

    Science.gov (United States)

    Lugosi, Peter; Bell, David; Lugosi, Krisztina

    2010-01-01

    This paper considers the relationships between hospitality, culture and urban regeneration through an examination of rom (ruin) venues, which operate in dilapidated buildings in Budapest, Hungary. The paper reviews previous work on culture and urban regeneration in order to locate the role of hospitality within emerging debates. It subsequently interrogates the evolution of the rom phenomenon and demonstrates how, in this context, hospitality thrives because of social and physical decay in urban locations, how operators and entrepreneurs exploit conflicts among various actors involved in regeneration and how hospitality may be mobilised purposefully in the regeneration process. The paper demonstrates how networked entrepreneurship maintains these operations and how various forms of cultural production are entangled and mobilised in the venues' hospitality propositions. PMID:21114092

  4. Discussions related to the modernization process of control rooms, reactor operator performance and three training programmes

    International Nuclear Information System (INIS)

    In the past, nuclear plants had commonly looked at 'like-for-like' replacements when they start defining modernisation of old systems. That is, plants just implement the same functionality and capability of the old system with new technology. At the most, some simple interface or other minor changes may be made. In this paper we discuss the most important aspects related to the modernization of control rooms, comparing their technologies, human factors and errors. In that sense, to support safe and effective operation, it is critical to specify, design, implement, operate, and maintain, as well as train and retrain operators for, the control room and HIS changes to take advantage of human cognitive processing abilities and reduce the likelihood of human errors. Therefore, it is important to look at and take advantage of the improvements that modern, digital technology can bring now and in the foreseeable future. Finally, we also discuss some aspects related to the turnover of operation skilled people from Angra-1, Westinghouse design, to Angra-2, Siemens/KWU design and the crew perspective for Angra-3, Siemens/KWU digital control room design. (author)

  5. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

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

  6. Nuclear Reactor RA Safety Report, Vol. 11, Reactor operation

    International Nuclear Information System (INIS)

    This volume includes the following chapters describing: Organisation of reactor operation (including operational safety, fuel management, and regulatory rules for RA reactor operation); Control and maintenance of reactor components (reactor core, nuclear fuel, heavy water and cover gas systems, mechanical structures, electric power supply system, reactor instrumentation); Quality assurance and Training of the reactor personnel

  7. GENETICS OF THE RABBIT FOR MEAT PRODUCTION : WHAT'S NEW SINCE THE WORLD RABBIT CONGRESS HELD IN BUDAPEST IN 1988? l A REVIEW.

    OpenAIRE

    De Rochambeau, H

    1997-01-01

    Abstract not available. Rochambeau, HD. (1997). GENETICS OF THE RABBIT FOR MEAT PRODUCTION : WHAT'S NEW SINCE THE WORLD RABBIT CONGRESS HELD IN BUDAPEST IN 1988? l A REVIEW. http://hdl.handle.net/10251/10427.

  8. Berglund, Bruce R. and Brian Porter-Szűcs, eds. 2013. Christianity and Modernity in Eastern Europe. Budapest and New York: Central European University Press. 386 pp.

    OpenAIRE

    Dorottya Nagy

    2015-01-01

    Berglund, Bruce R. and Brian Porter-Szűcs, eds. 2013. Christianity and Modernity in Eastern Europe. Budapest and New York: Central European University Press. 386 pp.  Reviewed by Dorottya Nagy, University of South Africa, Helsinki, Finland.

  9. Innovations and enhancements in neutronic analysis of the Big-10 university research and training reactors based on the AGENT code system

    International Nuclear Information System (INIS)

    Introduction. This paper summarizes salient aspects of the 'virtual' reactor system developed at Purdue Univ. emphasizing efficient neutronic modeling through AGENT (Arbitrary Geometry Neutron Transport) a deterministic neutron transport code. DOE's Big-10 Innovations in Nuclear Infrastructure and Education (INIE) Consortium was launched in 2002 to enhance scholarship activities pertaining to university research and training reactors (URTRs). Existing and next generation URTRs are powerful campus tools for nuclear engineering as well as a number of disciplines that include, but are not limited to, medicine, biology, material science, and food science. Advancing new computational environments for the analysis and configuration of URTRs is an important Big-10 INIE aim. Specifically, Big-10 INIE has pursued development of a 'virtual' reactor, an advanced computational environment to serve as a platform on which to build operations, utilization (research and education), and systemic analysis of URTRs physics. The 'virtual' reactor computational system will integrate computational tools addressing the URTR core and near core physics (transport, dynamics, fuel management and fuel configuration); thermal-hydraulics; beam line, in-core and near-core experiments; instrumentation and controls; confinement/containment and security issues. Such integrated computational environment does not currently exist. The 'virtual' reactor is designed to allow researchers and educators to configure and analyze their systems to optimize experiments, fuel locations for flux shaping, as well as detector selection and configuration. (authors)

  10. [Professor Frantisek Por MD and Professor Robert Klopstock MD, students at Budapest and Prague Faculties of Medicine].

    Science.gov (United States)

    Mydlík, M; Derzsiová, K

    2010-11-01

    Professor Frantisek Por MD and Professor Robert Klopstock MD were contemporaries, both born in 1899, one in Zvolen, the other in Dombovar, at the time of Austro-Hungarian Monarchy. Prof. Por attended the Faculty of Medicine in Budapest from 1918 to 1920, and Prof. Klopstock studied at the same place between 1917 and 1919. From 1920 until graduation on 6th February 1926, Prof. Por continued his studies at the German Faculty of Medicine, Charles University in Prague. Prof. Klopstock had to interrupt his studies in Budapest due to pulmonary tuberculosis; he received treatment at Tatranske Matliare where he befriended Franz Kafka. Later, upon Kafka's encouragement, he changed institutions and continued his studies at the German Faculty of Medicine, Charles University in Prague, where he graduated the first great go. It is very likely that, during their studies in Budapest and Prague, both professors met repeatedly, even though their life paths later separated. Following his graduation, Prof. Por practiced as an internist in Prague, later in Slovakia, and from 1945 in Kosice. In 1961, he was awarded the title of university professor of internal medicine at the Faculty of Medicine, Pavol Jozef Safarik University in Kosice, where he practiced until his death in 1980. Prof. Klopstock continued his studies in Kiel and Berlin. After his graduation in 1933, he practiced in Berlin as a surgeon and in 1938 left for USA. In 1962, he was awarded the title of university professor of pulmonary surgery in NewYork, where he died in 1972. PMID:21250499

  11. Mineral phases containing heavy metals in the suspended dust from Budapest, Hungary

    Directory of Open Access Journals (Sweden)

    Sipos P.

    2013-04-01

    Full Text Available The mineralogy, geochemistry and magnetic properties of total suspended particulate (TSP matter in Budapest, Hungary were studied to identify their heavy metal-bearing mineral phases. Amorphous organic matter, magnetite, salts as well as mineral phases characteristic of the surrounding geology are the main components of the TSP. They show significant enrichment in several heavy metals, such as Zn (up to 19 046 mg/kg, Pb (up to 3597 mg/kg, Cu (up to 699 mg/kg and Mo (up to 53 mg/kg. The most frequent heavy metal-bearing mineral phases are spherular or xenomorphic magnetite particles containing 2-3 wt% Pb and Zn. They often form aggregates and are closely associated with soot and/or clay minerals. The size of these particles is rarely below 30 nm. Cu and Mo could be associated to magnetite too. Clay minerals and mica particles may also contain significant amount of Zn (up to 5wt%. Additionally, ZnO and ZnCO3 particles were found in the sample with highest Zn content and our data suggest the potential association of Pb and carbonates, as well. Magnetite particles are resistant to weathering releasing its toxic components slowly to the environment, while layer silicates (and carbonates may be the potential source of mobile toxic metals in the TSP.

  12. Zooplankton (Cladocera, Copepoda dynamics in the River Danube upstream and downstream of Budapest, Hungary

    Directory of Open Access Journals (Sweden)

    Vadadi-Fülöp, Cs.

    2009-11-01

    Full Text Available The spatial distribution and seasonal dynamics of zooplankton (Cladocera, Copepoda were studied in the River Danube near Budapest, Hungary. The investigated river section was relatively poor in plankton, nauplii dominated. A total of 36 species was recorded of which Acanthocyclops robustus, Thermocyclops crassus, Bosmina longirostris were the most abundant. There was a downstream increase in copepod densities, however, no other remarkable differences could be observed between the profiles upstream and downstream of the capital. Generally, the streamline was characterized by lower densities and lower number of taxa as compared to the river bank; nevertheless, there were differences between the left and the right banks both upstream or downstream as well. Seasonal dynamics was defined by a marked late winter–spring aspect and abundance peaks were found to be characteristic for Danube with high densities in May–June and August–September. Examining the relationship between zooplankton density and the hydrological regime, it can be concluded that zooplankton production in the main channel is of minor importance, rather floodplain areas and adjacent water bodies seem to be important sources of plankton biomass.

  13. Book reviews. Kulturgeschichte der Physik by K. Simonyi, Akademiai Kindo, Budapest, 1990

    International Nuclear Information System (INIS)

    This review presents the German version of the 3rd edition of the book A fizika Kulturtoertenete, by professor K. Simonyi, issued in 1990 at Gondolat Kiado, Budapest. It contains 576 pp, 662 figs, 33 full-color plates and 26 tables. The book is designed for a broad spectrum of readers from laymen to professionals. This goal was achieved by resorting to two paralleled texts, one of general accessibility and a second one printed distinctly, addressed to more specialized readers like students, professors or physicists. It is build of 5 parts and presents the physics as a part of universal cultural evolution of humanity. The cultural and philosophical historical environment is created through an extremely rich illustration as images and pertinent excerpts from physics and mathematics, literature and philosophy of the time as well as through biographical sketches of the physicists as they entered the scene of history. In the reviewer's view the occurrence of this book is an important cultural event of these years. (Author)

  14. ANALYSING URBAN EFFECTS IN BUDAPEST USING THE WRF NUMERICAL WEATHER PREDICTION MODEL

    Directory of Open Access Journals (Sweden)

    JÚLIA GÖNDÖCS

    2016-03-01

    Full Text Available Continuously growing cities significantly modify the entire environment through air pollution and modification of land surface, resulting altered energy budget and land-atmosphere exchange processes over built-up areas. These effects mainly appear in cities or metropolitan areas, leading to the Urban Heat Island (UHI phenomenon, which occurs due to the temperature difference between the built-up areas and their cooler surroundings. The Weather Research and Forecasting (WRF mesoscale model coupled to multilayer urban canopy parameterisation is used to investigate this phenomenon for Budapest and its surroundings with actual land surface properties. In this paper the basic ideas of our research and the methodology in brief are presented. The simulation is completed for one week in summer 2015 with initial meteorological fields from Global Forecasting System (GFS outputs, under atmospheric conditions of weak wind and clear sky for the Pannonian Basin. Then, to improve the WRF model and its settings, the calculated skin temperature is compared to the remotely sensed measurements derived from satellites Aqua and Terra, and the temporal and spatial bias values are estimated.

  15. [Scientific activity of the University Urological Department in Budapest after WWII (1946-1956)].

    Science.gov (United States)

    Romics, I; Romics, M

    2016-04-01

    The authors studied the publications written by the staff of the University Department of Urology in Budapest, Hungary between 1946 and 1956. The collection was contributed on the occasion of Professor Babics's 10-year-long chairmanship. Over a period of 10 years, 214 papers were published by 15 urologists, including 3 books and 3 PhD theses; 16 papers were published in German, 22 in English, 2 in French, and 1 in Italian. The most frequent topic of the papers (26) was basic science (e.g., ureter motility, lymph circulation, intrarenal pressure condition). Other papers dealt with nephrology, artificial kidneys, TURP, and nephron-sparing renal surgery. Some articles examined various types of malignant tumors and benign prostatic hyperplasia, while 17 publications focused on the topic of andrology. Tuberculosis was also discussed by the authors. Despite political isolation, the communist dictatorship, poverty, the lack of health equipment, physicians educated before WWII with their work morality and hard work managed to perform contemporary clinical and basic scientific research. PMID:27000284

  16. Operating Experience Review(OER) and development of Issues Tracking System(ITS) for Jordan Research and Training Reactor(JRTR)

    International Nuclear Information System (INIS)

    The operation of the Jordan Research and Training Reactor which Korean consortium designs will start in March 2015. Though the power level of JRTR is different from the one of HANARO, a Korean research reactor, experience and expertise gained from the successful operation of the multipurpose research reactor, HANARO, would be applied for the design of JRTR because the basic operation principles of two reactors are almost same. From the point of human factors view, Operating Experience Review (OER) has the accurate purpose of reflecting accumulated knowledge to a new design and this activity are required to perform in the beginning stage of the control room designs in nuclear facilities. OER is to identify human factors engineering (HFE) issues related to safety. The issues from operating experience provide a basis for improving the plant design in a timely way. Identified issues are reported to an issues tracking system (ITS) so as to manage and resolve issues. HFE related safety issues are to be extracted from OER. The purpose of this paper is to present the scope and methods of OER for the JRTR design. In addition, a new ITS is proposed. The ITS is effective for issue management and has simplified states for issue development and small numbers of steps for issue control

  17. Requirements for a reactor simulator of the konvoi generation of nuclear power plants according to training programs

    International Nuclear Information System (INIS)

    This report is based an a review of the literature published on simulator training and on discussions with representatives from the German nuclear power plant operator training schools. A brief description of the organisation and content of the simulator training of control room operators in a number of countries, together with a categorisation of the various types of simulators which are used. The concepts of the systems approach to training and simulator fidelity are discussed. Some general training principles which are considered important for simulator training are summarised. From the available descriptions and analyses of control room operator tasks, the skills (in most general terms) which can be trained on simulators have been identified. Methods for training these skills which are used in the simulator training programmes in various industries and which have been developed in research work in the area of training psychology have been summarised. Using these methods as a basis, the necessary instructor facilities which should be included in the design of a full simulator for the Konvoi generation of nuclear power plants have been derived. (orig.)

  18. Origin of bank filtered groundwater on the Csepel Island (below Budapest)

    International Nuclear Information System (INIS)

    The drinking water for the Hungarian capitol is mainly covered from bank filter wells of the riparian aquifer system of the River Danube. A part of these wells are located on the Csepel Island (south of Budapest). The aquifer system is highly vulnerable for pollution coming either from the Danube or from the background shallow groundwater. Budapest contaminates continuously the Danube water with communal and industrial wastewater. The contamination can have an effect on the quality of the bank-filtered water on the Csepel Island. The knowledge of the flowing system in the alluvial aquifer is very important for providing high quality drinking water and for protecting the drinking water resources. The aims of this study are to determine the origin of the exploited water and the shallow groundwater, the ratio Danube water/background water, and the average transit time of the infiltrated Danube water for the observed wells. For reaching of these purposes stable oxygen and radioactive tritium isotope measurements, water chemical and hydraulic data have been applied. These data are compared and built together with the hydraulic data in the modeling process that was made with the 3 dimensional variation of the model program MODFLOW. The origin of the water from production or observation wells can be determined on the basis of the significant difference between the δ18O values of the Danube water and the shallow groundwater (recharging from the infiltrating precipitation). The mean δ18O values in Hungary: -11.0 [per mille]VSMOW for the Danube water, -9.3 ± 0.4 [per mille]VSMOW for the locally infiltrated phreatic groundwater and -11.8 ± 0.8 [per mille]VSMOW for the deep old groundwater. From 1998 till 2002 in every quarter a year water samples were taken from several observation wells in the northern part of the island for stable oxygen isotope measurements. On the basis of the isotopic significance we could separate the middle area of the island, where the measured

  19. The association of syringe type and syringe cleaning with HCV infection among IDUs in Budapest, Hungary.

    Science.gov (United States)

    Gyarmathy, V Anna; Neaigus, Alan; Mitchell, Mary M; Ujhelyi, Eszter

    2009-03-01

    We assessed whether syringe type, syringe cleaning and distributive syringe sharing were associated with self-reported and laboratory-confirmed HCV infection among Hungarian IDUs. Injecting drug users (N=215) were recruited from non-treatment settings in Budapest, Hungary between October 2005 and December 2006. Multivariate logistic regression models identified correlates of self-report of being HCV infected and testing positive for HCV. While 37% tested positive for HCV, 14% of the total (39% of those who tested positive) self-reported being HCV infected. Using any two-piece syringes was significantly associated with self-reported HCV infection, while distributive syringe sharing was not associated with self-report of being HCV infected. Engaging in receptive sharing of only one-piece syringes but always cleaning before reuse was not associated with testing HCV positive, while any receptive sharing of only one-piece syringes and not always cleaning before reuse was significantly associated with testing HCV positive. Sharing cookers and squirting drugs from one syringe into another syringe were not associated with testing HCV positive. The high percent of those HCV infected who did not know they were infected highlights the need to provide better access to confidential testing and counseling services. Counseling should emphasize secondary prevention of HCV among HCV infected IDUs. Our findings also indicate that syringe type and syringe cleaning practices may play a role in HCV transmission. Ethnographic research should identify the reasons why IDUs may use two-piece syringes and suggest means to reduce their use. Thorough cleaning of one-piece syringes when sterile syringes are unavailable may be an efficient way to reduce the risk of HCV infection. PMID:19058925

  20. Study of the urban climatic effect for Budapest on district scale using satellite observations

    Science.gov (United States)

    Dezso, Zsuzsanna; Dian, Csenge; Molnar, Gergely; Fricke, Cathy; Bartholy, Judit; Pongracz, Rita

    2015-04-01

    About 1.7 million inhabitants are living in the Hungarian capital, Budapest, which consists of 23 districts altogether. The entire city is divided by the river Danube into a hilly, greener Buda side on the west, and the flat, more densely built-up Pest side on the east. Our study aims to analyse the urban effect on both sides. In case of the Buda side, the analysis focuses on the extended urban vegetation since most of the forested green area is located there. The effects of the past changing of these green areas are analyzed using surface temperature data calculated from satellite measurements in the infrared channels, and NDVI (Normalized Difference Vegetation Index) derived from visible and near-infrared satellite measurements. We aim to evaluate the relationship of surface temperature and NDVI in this urban environment with special focus on either increased or decreased vegetation cover, e.g., recently built shopping centers in previously vegetated area or brown industrial area where low quality vegetation appeared in the past decade. In case of the Pest side, several block rehabilitation programs have been started since the 1980s. Due to these programs functional and structural changes of special subsections of the districts occurred in the past few decades. Their consequent local climatic changes are evaluated in this poster on the basis of satellite measurements, namely, surface temperature fields derived from radiation data of seven different infrared channels measured by sensor MODIS (onboard satellites Terra and Aqua). Our main goal is to analyze whether the generally positive changes of the built environment can also be recognized in the urban heat island effect of this area.

  1. Parameterizable Consensus Connectomes from the Human Connectome Project: The Budapest Reference Connectome Server v3.0

    OpenAIRE

    Szalkai, Balázs; Kerepesi, Csaba; Varga, Bálint; Grolmusz, Vince

    2016-01-01

    Connections of the living human brain, on a macroscopic scale, can be mapped by a diffusion MR imaging based workflow. Since the same anatomic regions can be corresponded between distinct brains, one can compare the presence or the absence of the edges, connecting the very same two anatomic regions, among multiple cortices. Previously, we have constructed the consensus braingraphs on 1015 vertices first in five, then in 96 subjects in the Budapest Reference Connectome Server v1.0 and v2.0, re...

  2. Search and the City: Comparing the Use of WiFi in New York, Budapest and Montreal

    OpenAIRE

    Laura Forlano

    2009-01-01

    Over the past five years, the use of mobile and wireless technology in public spaces of cities around the country has grown exponentially. There has been little analysis of the ways in which the use of the wireless Internet via WiFi may differ from that of the wireline Internet. This paper compares the results from a six-month survey of the use of WiFi hotspots in New York, Budapest and Montreal. It is hoped that further analysis of these survey results will contribute to a more acute underst...

  3. CERN and the Wigner Research Centre for Physics inaugurate CERN data centre’s extension in Budapest, Hungary

    CERN Multimedia

    Wigner Research Centre for Physics, Hungary

    2013-01-01

    On 13 June 2013 CERN and the Wigner Research Centre for Physics inaugurated the Hungarian data centre in Budapest, marking the completion of the facility hosting the extension for CERN computing resources. About 500 servers, 20,000 computing cores, and 5.5 Petabytes of storage are already operational at the site. The dedicated and redundant 100 Gbit/s circuits connecting the two sites are functional since February 2013 and are among the first transnational links at this distance. The capacity at Wigner will be remotely managed from CERN, substantially extending the capabilities of the Worldwide LHC Computing Grid (WLCG) Tier-0 activities and bolstering CERN’s infrastructure business continuity.

  4. Statistical analysis in the design of nuclear fuel cells and training of a neural network to predict safety parameters for reactors BWR

    International Nuclear Information System (INIS)

    In this work the obtained results for a statistical analysis are shown, with the purpose of studying the performance of the fuel lattice, taking into account the frequency of the pins that were used. For this objective, different statistical distributions were used; one approximately to normal, another type X2 but in an inverse form and a random distribution. Also, the prediction of some parameters of the nuclear reactor in a fuel reload was made through a neuronal network, which was trained. The statistical analysis was made using the parameters of the fuel lattice, which was generated through three heuristic techniques: Ant Colony Optimization System, Neuronal Networks and a hybrid among Scatter Search and Path Re linking. The behavior of the local power peak factor was revised in the fuel lattice with the use of different frequencies of enrichment uranium pines, using the three techniques mentioned before, in the same way the infinite multiplication factor of neutrons was analyzed (k..), to determine within what range this factor in the reactor is. Taking into account all the information, which was obtained through the statistical analysis, a neuronal network was trained; that will help to predict the behavior of some parameters of the nuclear reactor, considering a fixed fuel reload with their respective control rods pattern. In the same way, the quality of the training was evaluated using different fuel lattices. The neuronal network learned to predict the next parameters: Shutdown Margin (SDM), the pin burn peaks for two different fuel batches, Thermal Limits and the Effective Neutron Multiplication Factor (keff). The results show that the fuel lattices in which the frequency, which the inverted form of the X2 distribution, was used revealed the best values of local power peak factor. Additionally it is shown that the performance of a fuel lattice could be enhanced controlling the frequency of the uranium enrichment rods and the variety of the gadolinium rods

  5. Innovatives Medizinstudium der Semmelweis Universität Budapest am Asklepios Campus Hamburg [Innovation in the Field of Medical Studies in Europe: Asklepios Campus Hamburg of Budapest's Semmelweis University

    Directory of Open Access Journals (Sweden)

    Weidenhammer, Jörg

    2010-05-01

    Full Text Available [english] In our article we present a pioneering and unique transnational European model of university education. We discuss the cooperation between Semmelweis University Budapest and Asklepios Campus Hamburg. After several years of negotiation, it is now possible for students who did their preliminary medical examination in Hungary to continue and finish their medical studies in Hamburg, Germany. We report on the background of this development, the historical ties and legal requirements. We also describe the status quo and the future plans for the project. [german] In diesem Artikel stellen wir ein neues bisher in Europa einzigartiges länderübergreifendes Hochschulbildungsmodell vor. Dargestellt wird die Zusammenarbeit der Semmelweis Universität Budapest mit dem Asklepios Campus Hamburg. Nach mehrjährigen Verhandlungen ist es nun möglich, dass Studenten, die in Ungarn ihr Physikum gemacht haben, in Hamburg ihre klinische Ausbildung fortsetzen und abschließen können. Wir berichten über die Hintergründe und historischen Zusammenhänge sowie die rechtlichen Voraussetzungen dieser Entwicklung und beschreiben den gegenwärtigen Stand sowie die zukünftigen Planungen dieses Projekts.

  6. Chemical durability of glaze on Zsolnay architectural ceramics (Budapest, Hungary) in acid solutions

    Science.gov (United States)

    Baricza, Ágnes; Bajnóczi, Bernadett; May, Zoltán; Tóth, Mária; Szabó, Csaba

    2015-04-01

    Zsolnay glazed architectural ceramics are among the most famous Hungarian ceramics, however, there is no profound knowledge about the deterioration of these building materials. The present study aims to reveal the influence of acidic solutions in the deterioration of Zsolnay ceramics. The studied ceramics are glazed roof tiles, which originate from two buildings in Budapest: one is located in the densely built-up city centre with high traffic rate and another one is in a city quarter with moderate traffic and more open space. The roof tiles represent the construction and the renovation periods of the buildings. The ceramics were mainly covered by lead glazes in the construction period and mainly alkali glazes in the renovation periods. The glaze of the tiles were coloured with iron (for yellow glaze) or chromium/copper/iron (for green glazes) in the case of the building located in the city centre, whereas cobalt was used as colorant and tin oxide as opacifier for the blue glaze of the ceramics of the other building. Six tiles were selected from each building. Sulphuric acid (H2SO4) solutions of pH2 and pH4 were used to measure the durability of the glazes up to 14 days at room temperature. The surfaces of the glazed ceramics after the treatment were measured by X-ray diffraction, Raman spectroscopy and SEM-EDS techniques to determine the precipitated phases on the surface of the glaze. Electron microprobe analysis was used to quantitatively characterise phases found and to determine the chemical composition of the treated glaze. The recovered sulphuric acid solutions were measured with ICP-OES technique in order to quantify the extent of the ion exchange between the glaze and the solutions. There is a significant difference in the dissolution rates in the treatments with sulphuric acid solutions of pH2 and pH4, respectively. The solution of pH2 induced greater ion exchange (approx. 7-10 times) from the glaze compared to the solution of pH4. Alkali and alkali earth

  7. The ENEN-III project: Technical Training on the Concepts and Design of GEN IV nuclear reactors

    International Nuclear Information System (INIS)

    Some conclusions: • Not enough training courses to cover the LO’s: – Especially GEN IV; – Many introductory courses, little specific courses; – Reach out to other partners for more courses. • Skills and Attitudes: – Much more difficult to train/measure; – To be treated in a separate project. • Use of Learning Outcomes must be promoted; • Involvement of human resources necessary for the successful implementation of the schemes: – End of project workshop

  8. Tourist Intensity in Capital Cities in Central Europe: Comparative Analysis of Tourism in Prague, Vienna and Budapest

    Directory of Open Access Journals (Sweden)

    Dumbrovská Veronika

    2014-12-01

    Full Text Available Urban tourism has become a significant phenomenon of tourism over the last decade. the importance of urban tourism has grown mainly due to the development of transport and information technologies. rapid advancement of low cost airlines and reduction of administrative barriers owing to the expansion of the schengen area caused not only the development of a number of urban destinations, including Prague, but also the growth of new source markets. this paper compares the development of urban tourism in Prague with the situation in Vienna and Budapest in the last decade. the aim of the paper is to describe the main trends of tourism development and the geographic distribution of tourism in Prague in comparison with culturally and historically similar cities - Vienna and Budapest. the analysis shows high load of tourism in Prague and its strong concentration in the old city. this causes congestion in the city centre and an extrusion of residential functions by the functions of tourism. As a result, a tourism ghetto has been formed in the centre of Prague and the urban society has been increasingly dualized.

  9. Differences between satellite- and ground-based urban heat island effect - Case study for the Budapest agglomeration area

    Science.gov (United States)

    Pongracz, R.; Bartholy, J.; Lelovics, E.; Dezso, Z. S.; Dobi, I.

    2012-04-01

    Urban heat island (UHI) is defined as the positive temperature anomaly occurring between built-in areas and their surroundings. For detailed analysis of UHI in a particular area, different approaches can be used. Here, two different techniques (ground-based and satellite-based) are applied to the Budapest agglomeration area and the results are compared. (1) Hourly recorded air temperature observations are available from six automatically operating climatological stations of the Hungarian Meteorological Service. Two stations are located in the downtown of Budapest (Kitaibel Pál street and Lágymányos); two stations can be found in the suburbs (Újpest and Pestszentlőrinc); and two stations are in the rural region (Penc - located to the northeast from the capital, and Kakucs - to the southeast from Budapest). These ground-based observations at the Budapest weather stations provide air temperature data at standard 2 m height above surface. However, due to the limited station number, this approach is not suitable for detailed evaluation of spatial UHI distribution. (2) Remotely sensed surface temperature values are available from seven thermal infrared channel measurements of the multi-spectral radiometer sensor called MODIS (Moderate Resolution Imaging Spectroradiometer), which is one of the sensors on-board satellites Terra and Aqua. They were launched to polar orbit as part of the NASA's Earth Observing System in December 1999, and in May 2002, respectively. Satellite Terra (Aqua) provides surface temperature fields around 09-10 UTC (12-13 UTC) and 20-21 UTC (02-03 UTC) with 1 km spatial resolution. The whole agglomeration has been divided into urban and rural pixels using the MODIS Land Cover Product categories, distance from the city centre, satellite images of the Google Earth, and GTOPO-30 global digital elevation model. However, the main disadvantage of this method is that for UHI analysis, data can be used only in case of clear sky conditions, which occurs

  10. Development of modern safe systems of work at the Imperial College Reactor Centre and their application to neutron detector testing and nuclear training courses

    International Nuclear Information System (INIS)

    safety hazards. For straight forward not especially hazardous tasks the risk assessment is sufficient to control the operation and provides all the information and instructions for the work to be carried out safely. Operations with a radiological risk, particularly those involving non classified workers in controlled areas have additional written controls in the form of a Written System of Work which goes into details of radiological hazards and safeguards and may involve hold points. The most hazardous tasks (both radiological and conventional) are controlled through the use of Permits to Work. In all cases, operations which involve the use of contractors, require careful assessment of the Contracting Organisation and their plans for the work (method statements etc.) to ensure that the contractors are suitably trained and experienced to do the work. These procedures have allowed the development of the facility requiring man access into a Controlled Area with an open beam tube where doses are maintained ALARP. The CONSORT reactor provides a facility for the calibration and periodic testing of neutron flux detectors (primarily fission chambers and ion chambers). The first case study outlines the detector testing programme which requires the use of a broad range of well thermalised neutron fluxes over eleven orders of magnitude. The facility in which these tests are carried out consists of a beam tube penetrating the graphite thermal column located immediately outside of the tank housing the reactor core. During testing, the detectors are manually loaded into and unloaded from the beam tube with the reactor operating at low power (up to 2kW). This process has been developed, assessed and controlled using the procedures described, in order to ensure that the doses are minimised and acceptable in line with the ALARP principle. On line testing of the detectors is carried out by the manufacturer's employees on site, and involves the control and supervision of these workers

  11. Berglund, Bruce R. and Brian Porter-Szűcs, eds. 2013. Christianity and Modernity in Eastern Europe. Budapest and New York: Central European University Press. 386 pp.

    Directory of Open Access Journals (Sweden)

    Dorottya Nagy

    2015-01-01

    Full Text Available Berglund, Bruce R. and Brian Porter-Szűcs, eds. 2013. Christianity and Modernity in Eastern Europe. Budapest and New York: Central European University Press. 386 pp.  Reviewed by Dorottya Nagy, University of South Africa, Helsinki, Finland.

  12. The Budapest meeting 2005 intensified networking on ethics of science : the case of reproductive cloning, germline gene therapy and human dignity

    NARCIS (Netherlands)

    Steendam, van Guido; Dinnyes, Andras; Mallet, Jacques; Roosendaal, Hans E.

    2006-01-01

    This paper reports on the meeting of the Sounding Board of the EU Reprogenetics Project that was held in Budapest, Hungary, 6–9 November 2005. The Reprogenetics Project runs from 2004 until 2007 and has a brief to study the ethical aspects of human reproductive cloning and germline gene therapy. Dis

  13. Collection of scientific papers in collaboration with Joint Institute for Nuclear Research, Dubna, USSR and Central Research Institute for Physics, Budapest, Hungary Pt. 5

    International Nuclear Information System (INIS)

    The results of JINR (Dubna) - CRIP (Budapest) collaboration in the field of numerical and computer methods for solving physical problems are reported. The topics cover pure mathematical problems with applications in organization theory, numerical data handling, construction and simulation of physical devices and reinterpretation of current problems in mathematical physics. (D.Gy.)

  14. Optimization of a Chemical Reaction Train

    Directory of Open Access Journals (Sweden)

    Bahar Sansar

    2010-01-01

    Full Text Available This project consists of the optimization of a chemical reactor train. The reactor considered here is the continuous stirred tank reactor (CSTR, one of the reactor models used in engineering. Given the design equation for the CSTR and the cost function for a reactor, the following values are determined; the optimum number of reactors in the reaction train, the volume of each reactor and the total cost.

  15. Optimization of a Chemical Reaction Train

    OpenAIRE

    Bahar Sansar

    2010-01-01

    This project consists of the optimization of a chemical reactor train. The reactor considered here is the continuous stirred tank reactor (CSTR), one of the reactor models used in engineering. Given the design equation for the CSTR and the cost function for a reactor, the following values are determined; the optimum number of reactors in the reaction train, the volume of each reactor and the total cost.

  16. Determination of neutron flux density distribution in the core with LEU fuel IRT-4M at the training reactor VR-1

    International Nuclear Information System (INIS)

    The objective of this work was to determine the neutron flux density distribution in various places of the training reactor VR-1 Sparrow. This experiment was performed on the new core design C1, composed of the new low-enriched uranium fuel cells IRT-4M (19.7 %). This fuel replaced the old high-enriched uranium fuel IRT-3M (36 %) within the framework of the RERTR Program in September 2005. The measurement used the neutron activation analysis method with gold wires. The principle of this method consists in neutron capture in a nucleus of the material forming the activation detector. This capture can change the nucleus in a radioisotope, whose activity can be measured. The absorption cross-section values were evaluated by MCNP computer code. The gold wires were irradiated in seven different positions in the core C1. All irradiations were performed at reactor power level 1E8 (1 kWtherm). The activity of segments of irradiated wires was measured by special automatic device called 'Drat' (Wire in English). (author)

  17. The Text of the Instrument Concerning the Agency's Assistance to Argentina for the Establishment of a Training Reactor Project. A Letter from the Resident Representative of the Federal Republic of Germany to the Director General

    International Nuclear Information System (INIS)

    On 21 December 1971 the Director General received a letter from the Resident Representative of the Federal Republic of Germany to the Agency in connection with the Agreement between the Agency and the Governments of Argentina and the Federal Republic of Germany concerning the Agency's assistance for the establishment of a training reactor project in Argentina.

  18. The 250 kW FiR 1 TRIGA research reactor - International role in Boron Neutron Capture Therapy (BNCT) and regional role in isotope production, education and training

    International Nuclear Information System (INIS)

    The Finnish TRIGA reactor, FiR 1, has been in operation since 1962. From its early days the reactor created versatile research to support both the national nuclear program as well as generally the industry and health care sector. The volume of neutron activation analysis was impressive in the 70's and 80's. In the 1990's a BNCT treatment facility was build at the FiR 1 reactor. The treatment environment is of world top quality after a major renovation of the whole reactor building in 1997. Over one hundred patient irradiations have been performed since May 1999. FiR 1 is one of the few facilities in the world providing this kind of treatments. Due to the BNCT project FiR 1 has become an important research and education unit for medical physics. Education and training play also a role at FiR 1 in the form of university courses and training of nuclear industry personnel. Isotopes for tracer studies are produced normally twice a week. The reactor is operated by four reactor operators and five shift supervisors; this in addition to their work as research scientists or research engineers. (author)

  19. Survey of research reactors

    International Nuclear Information System (INIS)

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  20. The First 24 Years of Reverse Monte Carlo Modelling, Budapest, Hungary, 20-22 September 2012

    Science.gov (United States)

    Keen, David A.; Pusztai, László

    2013-11-01

    This special issue contains a collection of papers reflecting the content of the fifth workshop on reverse Monte Carlo (RMC) methods, held in a hotel on the banks of the Danube in the Budapest suburbs in the autumn of 2012. Over fifty participants gathered to hear talks and discuss a broad range of science based on the RMC technique in very convivial surroundings. Reverse Monte Carlo modelling is a method for producing three-dimensional disordered structural models in quantitative agreement with experimental data. The method was developed in the late 1980s and has since achieved wide acceptance within the scientific community [1], producing an average of over 90 papers and 1200 citations per year over the last five years. It is particularly suitable for the study of the structures of liquid and amorphous materials, as well as the structural analysis of disordered crystalline systems. The principal experimental data that are modelled are obtained from total x-ray or neutron scattering experiments, using the reciprocal space structure factor and/or the real space pair distribution function (PDF). Additional data might be included from extended x-ray absorption fine structure spectroscopy (EXAFS), Bragg peak intensities or indeed any measured data that can be calculated from a three-dimensional atomistic model. It is this use of total scattering (diffuse and Bragg), rather than just the Bragg peak intensities more commonly used for crystalline structure analysis, which enables RMC modelling to probe the often important deviations from the average crystal structure, to probe the structures of poorly crystalline or nanocrystalline materials, and the local structures of non-crystalline materials where only diffuse scattering is observed. This flexibility across various condensed matter structure-types has made the RMC method very attractive in a wide range of disciplines, as borne out in the contents of this special issue. It is however important to point out that since

  1. Course on reactor physics

    International Nuclear Information System (INIS)

    In Germany only few students graduate in nuclear technology, therefore the NPP operating companies are forced to develop their own education and training concepts. AREVA NP has started together with the Technical University of Dresden a one-week course ''reactor physics'' that includes the know-how of the nuclear power plant construction company. The Technical University of Dresden has the training reactor AKR-2 that is retrofitted by modern digital instrumentation and control technology that allows the practical training of reactor control.

  2. Trip report on IAEA Training Workshop on Implementation of Integrated Management Systems for Research Reactors (T3-TR-45496).

    Energy Technology Data Exchange (ETDEWEB)

    Pratt, Richard J.

    2013-11-01

    From 17-21 June 2013, Sandia National Laboratories, Technical Area-V (SNL TA-V) represented the United States Department of Energy/National Nuclear Security Administration (DOE/NNSA) at the International Atomic Energy Agency (IAEA) Training Workshop (T3-TR-45486). This report gives a breakdown of the IAEA regulatory structure for those unfamiliar, and the lessons learned and observations that apply to SNL TA-V that were obtained from the workshop. The Safety Report Series, IAEA workshop final report, and SNL TA-V presentation are included as attachments.

  3. A detailed neutronics comparison of the university of Florida training reactor (UFTR) current HEU and proposed LEU cores

    International Nuclear Information System (INIS)

    For over 35 years, the UFTR highly-enriched core has been safely operated. As part of the Reduced Enrichment for Research and Test Reactors Program, the core is currently being converted to low-enriched uranium fuel. The analyses presented in this paper were performed to verify that, from a neutronic perspective, a proposed low-enriched core can be operated as safely and as effectively as the highly-enriched core. Detailed Monte Carlo criticality calculations are performed to determine: i) Excess reactivity for different core configurations, ii) Individual integral blade worth and shutdown margin, iii) Reactivity coefficients and kinetic parameters, and iv) Flux profiles and core six-factor formula parameters. (authors)

  4. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  5. Guidance for training program evaluation

    International Nuclear Information System (INIS)

    An increased concern about the training of nuclear reactor operators resulted from the incident at TMI-2 in 1979. Purpose of this guide is to provide a general framework for the systematic evaluation of training programs for DOE Category-A reactors. The primary goal of such evaluations is to promote continuing quality improvements in the selection, training and qualification programs

  6. A Coffin Dispersed: Case-study of 21st Dynasty Coffin Fragments (Timişoara 1142–1146, Budapest 51.325

    Directory of Open Access Journals (Sweden)

    Branislav Anđelković

    2016-02-01

    The lack of a name, the corrupt texts, unusual iconography, and the lack of varnish may reflect the lack of resources of the coffin’s owner. A fragment in Budapest (51.325 is shown to join the Timişoara coffin sections. The dismantling/sawing of an object to make it more portable and saleable reflects an established practice of late 1800s and early 1900s Egyptian antiquities market.

  7. Collection of scientific papers in collaboration with Joint Institute for Nuclear Research, Dubna, USSR and Central Research Institute for Physics, Budapest, Hungary Vol. 6

    International Nuclear Information System (INIS)

    Papers of collaboration of JINR, Dubna and CRIP, Budapest, are presented in the field of algorithms and computer programs for solution of physical problems. The topics include computer evaluation and calculation of functional integrals and Pade approximants, occurring in theoretical particle physics, field theory and statistical physics, error estimations for approximate solutions of quasilinear integrodifferential evolution equations, overview of protocol testing, improved random number generation methods and computer simulation methods in molecule physics. Computer codes are also presented. (D.G.)

  8. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015; Session “Pharmacology”

    OpenAIRE

    Various Authors

    2015-01-01

    Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN), European Society for Paediatric Research (ESPR), Union of European Neonatal & Perinatal Societies (UENPS), European Foundation for the Care of Newborn Infants (EFCNI), with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (...

  9. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015; Session “Brain & Development”

    OpenAIRE

    Various Authors

    2015-01-01

    Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN), European Society for Paediatric Research (ESPR), Union of European Neonatal & Perinatal Societies (UENPS), European Foundation for the Care of Newborn Infants (EFCNI), with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (MPT), supp...

  10. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015; Session “Other”

    OpenAIRE

    Various Authors

    2015-01-01

    Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN), European Society for Paediatric Research (ESPR), Union of European Neonatal & Perinatal Societies (UENPS), European Foundation for the Care of Newborn Infants (EFCNI), with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (MPT),...

  11. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015; Session “Pulmonology”

    OpenAIRE

    Various Authors

    2015-01-01

    Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN), European Society for Paediatric Research (ESPR), Union of European Neonatal & Perinatal Societies (UENPS), European Foundation for the Care of Newborn Infants (EFCNI), with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (...

  12. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015; Session “Epidemiology”

    OpenAIRE

    Various Authors

    2015-01-01

    Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN), European Society for Paediatric Research (ESPR), Union of European Neonatal & Perinatal Societies (UENPS), European Foundation for the Care of Newborn Infants (EFCNI), with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (MPT),...

  13. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

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

  14. Atmospheric aerosol sampling campaign in Budapest and K-puszta. Part 2. Application of Stochastic Lung Model

    International Nuclear Information System (INIS)

    Complete text of publication follows. The Stochastic Lung Model [1] is a new important tool for the investigation of the health impact of atmospheric aerosols. The obtained concentrations of urban and rural aerosols (see part 1) were applied for lung deposition calculations with this model. The health effects of the inhaled particles may strongly depend on the location of deposition within the lung. This model was applied in order to calculate the deposition efficiencies of the measured aerosols in the tracheobronchial and the acinar regions of human respiratory system. In the acinar regions takes place the gas-exchange. In this model a lot of parameters can be adjusted and changed. For example: tidal volume, aerosol diameter and density, time of breathing cycle, etc. So can be calculation some cases among others males, females or children, sleep, sitting, light or heavy exercise, etc. As example the Figure 1. demonstrates that the acinar deposition has a maximum at 1-3 μm aerosol size and above 10 μm the practically do not reach the acinar region at sitting breathing conditions for male person. In the part I. the elements have been grouped. The first group was composed of Fe, Si and Ca. These elements can be found in 2-8 m size range with the largest rate. The deposition of Fe, Si and Ca elements has the largest probability in acinar region. The elemental concentrations in Budapest are much larger than in K-puszta. Thus, the acinar deposition of aerosol containing Fe, Si and Ca is relatively more significant in Budapest than in K-puszta. The second group was composed of S, Pb and W. The majority of these elements was in the 0,25-1 μm size range. These elements also deposit in acinar region but with less probability. Because their particles have large concentration they can also deposit in large amount. This work was supported by the National Research and Development Program (NRDP 3/005/2001). (author)

  15. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

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

  16. Multipurpose Utilisation of a Medium Flux Research Reactor. Benefit for the Society

    International Nuclear Information System (INIS)

    The Budapest Research Reactor (BRR) was restarted after a major refurbishment and increase in power to 10 MW in 1992. Basically, the experience gained with the utilization of this multipurpose facility during the past 20 years is described here. The utilization aims for 3 major activities: i) Research and development base for the energy sector: scientific and safety support for the Paks NPP; research in energy saving and production. ii) A complex source of irradiations for materials testing and modification, diagnostics in nanotechnologies, engineering, healthcare etc. iii) Neutron beams from the horizontal channels of the reactor serve for exploratory as well as for applied research in a very wide range of disciplines. Graduate and professional training is also in the scope of our activity. The reactor went critical first in 1959. It served nearly 3 decades as a home base for learning nuclear sciences and technologies, to development nuclear energetics, which resulted in launching four power plant blocks in the eighties, as well as to establish neutron beam research in our country. Nearly 20 years passed now that the decision was made - after the falling of the Iron Curtain'' - the practically brand new 10 megawatt reactor should be commissioned and opened for the international user community. The reactor reached its nominal power in May 1993 and neutron beam experiments were available on 4 instruments at that time. Thanks to a continuous development the number of experimental stations now is 15, the research staffs has grown from 10 to nearly 50 scientists and research facilities have been improved considerably. A few important milestones should be mentioned: a liquid hydrogen cold source was installed and the neutron guide system was replaced by a supermirror guide configuration, yielding a factor of 50-80 gain in neutron intensity; a second guide hall was constructed to house a new time-of-flight instrument; BRR became a member of the European neutron

  17. Nuclear energy: 21st century promise. 10 October 2005, Budapest, Hungary

    International Nuclear Information System (INIS)

    What role will nuclear energy play can not be can not be answered definitively, but IAEA projections for the coming decades are markedly higher than they were even five years ago. Nuclear reactors currently generate electricity for nearly 1 billion people, producing about 16% of the world's electricity. This percentage has held relatively steady for more than a decade, keeping pace with the steady expansion in the global electricity market. But in just the past few years, we have witnessed a significant change in attitudes towards nuclear power. Fast growing global energy demands, an increased emphasis on the security of energy supply, and the risk of climate change are driving a renewed consideration, in many quarters, towards investment in nuclear power. This past March, at an international ministerial conference in Paris, participants from 65 countries were upbeat regarding the role of nuclear power in meeting 21st century electricity and energy needs. Near term nuclear growth remains centred in Asia and Eastern Europe, which together account for 22 of the 24 units now under construction. The Russian Federation intends to double its nuclear generating capacity by 2020; China plans nearly a six-fold expansion in capacity by the same date; and India anticipates a ten-fold increase by 2022. Elsewhere, plans remain more modest, but it is clear that nuclear energy is regaining stature as a serious option. When Finland began pouring concrete for Olkiluoto-3 earlier this year, it was the first new nuclear construction in Western Europe since 1991. France will likely be next, with construction of a European Pressurized Water Reactor (EPR) at Flamanville scheduled to start in 2007. Some 'newcomer' developing countries, such as Indonesia and Vietnam, are also moving steadily forward with plans for nuclear power investment. And at last month's IAEA General Conference in Vienna, a host of countries were discussing plans and possibilities for initiating or expanding nuclear

  18. Physical security at research reactors

    International Nuclear Information System (INIS)

    Of the 84 non-power research facilities licensed under 10 CFR Part 50, 73 are active (two test reactors, 68 research reactors and three critical facilities) and are required by 10 CFR Part 73.40 to provide physical protection against theft of SNM and against industrial sabotage. Each licensee has developed a security plan required by 10 CFR Part 50.34(c) to demonstrate the means of compliance with the applicable requirements of 10 CFR Part 73. In 1974, the Commission provided interim guidance for the organization and content of security plans for (a) test reactors, (b) medium power research and training reactors, and (c) low power research and training reactors. Eleven TRIGA reactors, with power levels greater than 250 kW and all other research and training reactors with power levels greater than 100 kW and less than or equal to 5,000 kW are designated as medium power research and training reactors. Thirteen TRIGA reactors with authorized power levels less than 250 kW are considered to be low power research and training reactors. Additional guidance for complying with the requirements of 73.50 and 73.60, if applicable, is provided in the Commission's Regulatory Guides. The Commission's Office of Inspection and Enforcement inspects each licensed facility to assure that an approved security plan is properly implemented with appropriate procedures and physical protection systems

  19. Secondary charged particle activation method for measuring the tritium production rate in the breeding blankets of a fusion reactor

    International Nuclear Information System (INIS)

    In this work, a new passive technique has been developed for measuring the tritium production rate in ITER (International Thermonuclear Experimental Reactor) test blanket modules. This method is based on the secondary charged particle activation, in which the irradiated sample contains two main components: a tritium producing target (6Li or 7Li) and an indicator nuclide, which has a relatively high cross-section for an incoming tritium particle (triton). During the neutron irradiation, the target produces a triton, which has sufficiently high energy to cause the so-called secondary charged particle activation on an indicator nuclide. If the product of this reaction is a radioactive nuclide, its activity must be proportional to the amount of generated tritium. A comprehensive set of irradiations were performed at the Training Reactor of the Budapest University of Technology and Economics. The following charged particle reactions were observed and investigated: 27Al(t,p)29Al; 26Mg(t,p)28Mg; 26Mg(t,n)28Al; 32S(t,n)34mCl; 16O(t,n)18F; and 18O(t,α)17N. The optimal atomic ratio of the indicator elements and 6Li was also investigated. The reaction rates were estimated using calculations with the MCNPX Monte Carlo particle transport code. The trend of the measured and the simulated data are in good agreement, although accurate data for triton induced reaction cross-sections cannot be found in the literature. Once the technique is calibrated with a reference LSC (Liquid Scintillation Counting) measurement, a new passive method becomes available for tritium production rate measurements.

  20. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  1. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Michigan (Docket No. 50-2)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Michigan (UM) for renewal of the Ford Nuclear Reactor (FNR) operating license number R-28 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Michigan in Ann Arbor, Michigan. The staff concludes that the reactor can continue to be operated by the University of Michigan without endangering the health and safety of the public

  2. Selecting reactor operator trainees

    International Nuclear Information System (INIS)

    Reactor operator trainee selection tends to be more effective if tailored to a utility's unique needs, and offers the organization a better chance for compliance with Federal regulations than if selection methods are adopted without benefit of local research. The costs of operator training range from $50,000 to $100,000. The test validity relative to a variety of training grades and performance measures is reviewed. Of interest is the degree to which tests differentiate reactor operators with respect to simulator training grades and performance in simulator operation; forms of evaluation which have become fairly standard throughout the power industry. The tests administered to each individual were selected because of their presumed relevance to training grades, and the aptitude measures are intended to assess an individual's potential to benefit from training. Tests, availability, form, the abilities they measure, and the time limit are described. (MCW)

  3. TRIGA reactor main systems

    International Nuclear Information System (INIS)

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

  4. Multipurpose research reactors

    International Nuclear Information System (INIS)

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

  5. Nuclear reactor power monitor

    International Nuclear Information System (INIS)

    The device of the present invention monitors phenomena occurred in a nuclear reactor more accurately than usual case. that is, the device monitors a reactor power by signals sent from a great number of neutron monitors disposed in the reactor. The device has a means for estimating a phenomenon occurred in the reactor based on the relationship of a difference of signals between each of the great number of neutron monitors to the positions of the neutron monitors disposed in the reactor. The estimation of the phenomena is conducted by, for example, conversion of signals sent from the neutron monitors to a code train. Then, a phenomenon is estimated rapidly by matching the code train described above with a code train contained in a data base. Further. signals sent from the neutron monitors are processed statistically to estimate long term and periodical phenomena. As a result, phenomena occurred in the reactor are monitored more accurately than usual case, thereby enabling to improve reactor safety and operationability. (I.S.)

  6. The validation of Kayzero-assisted NAA in Budapest, Rez, and Ljubljana via the analysis of three BCR certified reference materials.

    Science.gov (United States)

    De Corte, F; van Sluijs, R; Simonits, A; Kucera, J; Smodis, B; Byrne, A R; De Wispelaere, A; Bossus, D; Frána, J; Horák, Z; Jaćimović, R

    2001-05-01

    After installation and calibration of k0-assisted NAA in three Central European research institutes (AEKI-Budapest, NPI-Rez, and IJS, Ljubljana), its validation was established via the analysis of three BCR certified reference materials. The matrices of choice were: CRM 277 estuarine sediment, CRM 038 coal fly ash from pulverized coal, and CRM 101 spruce needles. For some elements, e.g. Zn, Cd, and Hg, the analyses were not only performed instrumentally (INAA), but also in the radiochemical mode (RNAA). The work was performed in the framework of a European Copernicus Project. PMID:11393234

  7. The SAM software system for modeling severe accidents at nuclear power plants equipped with VVER reactors on full-scale and analytic training simulators

    Science.gov (United States)

    Osadchaya, D. Yu.; Fuks, R. L.

    2014-04-01

    The architecture of the SAM software package intended for modeling beyond-design-basis accidents at nuclear power plants equipped with VVER reactors evolving into a severe stage with core melting and failure of the reactor pressure vessel is presented. By using the SAM software package it is possible to perform comprehensive modeling of the entire emergency process from the failure initiating event to the stage of severe accident involving meltdown of nuclear fuel, failure of the reactor pressure vessel, and escape of corium onto the concrete basement or into the corium catcher with retention of molten products in it.

  8. Safety Evaluation Report related to renewal of the operating license for the CAVALIER Training Reactor at the University of Virginia (Docket No. 50-396)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Virginia for a renewal of Operating License R-123 to continue to operate the CAVALIER (Cooperatively Assembled Virginia Low Intensity Educational Reactor) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Virginia and is located on the campus in Charlottesville, Virginia. Based on its technical review, the staff concludes that the reactor facility can continue to be operated by the university without endangering the health and safety of the public or the environment

  9. Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Arizona (Docket No. 50-113)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Arizona for the renewal of Operating License R-52 to continue operating its research reactor at an increased operating power level has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the University of Arizona campus in Tucson, Arizona. The staff concludes that the reactor can continue to be operated by the University of Arizona without endangering the health and safety of the public. 20 refs., 8 figs., 5 tabs

  10. Safety Evaluation Report related to the renewal of the operating license for the training and research reactor at the University of Lowell (Docket No. 50-223)

    International Nuclear Information System (INIS)

    This Safety Evaluation Report for the application filed by the University of Lowell (UL) for renewal of operating license number R-125 to continue to operate its research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located on the North Campus of the University of Lowell in Lowell, Massachusetts. The staff concludes that the reactor can continue to be operated by the University of Lowell without endangering the health and safety of the public

  11. PREFACE: The First Fifteen Years of Reverse Monte Carlo Modelling, Budapest, Hungary (9--11 October 2003)

    Science.gov (United States)

    Keen, David A.; Pusztai, Laszlo; Dove, Martin T.

    2005-02-01

    This special issue contains a collection of papers reflecting the content of the second workshop on reverse Monte Carlo (RMC) methods, held in a hotel on hills overlooking Budapest in October 2003. Around forty participants gathered to hear talks and discuss a broad range of science based on the RMC technique in very convivial surroundings. Reverse Monte Carlo modelling is a method for producing three-dimensional disordered structural models in quantitative agreement with experimental data. The method was developed in the late 1980’s and has since achieved wide acceptance within the scientific community. It is particularly suitable for studies of the structures of liquid and amorphous materials, although it has also been used for a number of disordered crystalline systems. There is currently a great interest in the properties of disordered materials and this has produced a resurgence in methods for investigating their structures, with an increased number of high-quality instruments at central facilities for neutron and x-ray scattering from disordered materials. Methods such as RMC are currently in great demand for analysing the resulting total scattering and XAS data and the RMC methodology is actively being developed by a number of groups worldwide. Within this context, the RMC workshop was particularly timely, providing a forum for those workers in the field to take stock of past achievements and to look forward to future developments. It is our hope that the collection of papers within this special issue will also communicate this to the wider scientific community, by providing a balance between papers that have more of an introductory review flavour and those that concentrate on current state of the art research opportunities using the RMC method. The order of the papers within this special issue reflects this balance. The first two papers are introductory reviews of the RMC method in general and as applied specifically to crystalline systems, respectively

  12. Development of Modern Safe Systems of Work at the Imperial College Reactor Centre and Their Application to Neutron Detector Testing and Nuclear Training Courses

    International Nuclear Information System (INIS)

    The CONSORT design reactor is owned by, and licensed to, Imperial College of Science, Technology and Medicine, and has been in continuous safe operation since 1965. Today, it is the only civil research reactor left in the United Kingdom. CONSORT is designated a low power research reactor and is rated at 100 kW. The paper concentrates on the issues that have been addressed in ensuring that worker doses are maintained as low as reasonably practicable (ALARP), and describes how robust systems have been implemented to ensure that all assessments are in line with this principle. The principles of risk assessment are applied to all operations within the reactor centre and the framework leading to the establishment of the safe system of work will be outlined and discussed. Two case studies are described in detail as examples, showing the importance to the industry of ensuring that a system is in place to allow the work to continue and summarizes the experience gained in the past few years at Imperial College Reactor Centre. These experiences will provide useful information that managers of similar facilities may wish to consider in formulating their own arrangements. The CONSORT reactor provides an open beam tube facility for the calibration and periodic testing of neutron flux detectors (primarily fission chambers and ion chambers). The first case study outlines the detector testing programme that takes place on the CONSORT reactor using this facility. The second case study relates to the use of this integrated approach to safety management in the teaching environment. With ''safe systems of work'' in place, it is now possible to reinstate the popular student experiment of directly viewing the Cerenkov radiation emitted from the critical CONSORT reactor core. This particular activity had been discontinued for some years on ALARP grounds. (author)

  13. Nuclear reactor simulator

    International Nuclear Information System (INIS)

    The Nuclear Reactor Simulator was projected to help the basic training in the formation of the Nuclear Power Plants operators. It gives the trainee the opportunity to see the nuclear reactor dynamics. It's specially indicated to be used as the support tool to NPPT (Nuclear Power Preparatory Training) from NUS Corporation. The software was developed to Intel platform (80 x 86, Pentium and compatible ones) working under the Windows operational system from Microsoft. The program language used in development was Object Pascal and the compiler used was Delphi from Borland. During the development, computer algorithms were used, based in numeric methods, to the resolution of the differential equations involved in the process. (author)

  14. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  15. Perspectives on reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  16. 2012 review of French research reactors

    International Nuclear Information System (INIS)

    Proposed by the French Reactor Operators' Club (CER), the meeting and discussion forum for operators of French research reactors, this report first gives a brief presentation of these reactors and of their scope of application, and a summary of highlights in 2012 for each of them. Then, it proposes more detailed presentations and reviews of characteristics, activities, highlights, objectives and results for the different types of reactors: neutron beam reactors (Orphee, High flux reactor-Laue-Langevin Institute or HFR-ILL), technological irradiation reactors (Osiris and Phenix), training reactors (Isis and Azur), reactors for safety research purposes (Cabri and Phebus), reactors for neutronic studies (Caliban, Prospero, Eole, Minerve and Masurca), and new research reactors (the RES facility and the Jules Horowitz reactor or JHR)

  17. RA reactor operation and maintenance in 1992, Part 1

    International Nuclear Information System (INIS)

    During 1992 Ra reactor was not in operation. All the activities were fulfilled according to the previously adopted plan. Basic activities were concerned with revitalisation of the RA reactor and maintenance of reactor components. All the reactor personnel was busy with reconstruction and renewal of the existing reactor systems and building of the new systems, maintenance of the reactor devices. Part of the staff was trained for relevant tasks and maintenance of reactor systems

  18. First Algerian research reactor

    International Nuclear Information System (INIS)

    In 1985, both the Algerian Commissariat of New Energies and the Argentine National Atomic Energy Commission plus the firm INVAP S.E., started a series of mutual visits aimed at defining the mechanisms for cooperation in the nuclear field. Within this framework, a commercial contract was undersigned covering the supply of a low-power reactor (RUN), designed for basic and applied research in the fields of reactor physics and nuclear engineering. The reactor may also be used for performing experiences with neutron beams, for the irradiation of several materials and for the training of technicians, scientists and operators

  19. Site security personnel training manual

    International Nuclear Information System (INIS)

    As required by 10 CFR Part 73, this training manual provides guidance to assist licensees in the development of security personnel training and qualifications programs. The information contained in the manual typifies the level and scope of training for personnel assigned to perform security related tasks and job duties associated with the protection of nuclear fuel cycle facilities and nuclear power reactors

  20. Budapest scientific a guidebook

    CERN Document Server

    Hargittai, István

    2015-01-01

    This guidebook introduces the reader—the scientific tourist and others—to the visible memorabilia of science and scientists in Budapest—statues, busts, plaques, buildings, and other artefacts. According to the Hungarian–American Nobel laureate Albert Szent-Györgyi, this metropolis at the crossroads of Europe has a special atmosphere of respect for science. It has been the venue of numerous scientific achievements and the cradle, literally, of many individuals who in Hungary, and even more beyond its borders became world-renowned contributors to science and culture. Six of the eight chapters of the book cover the Hungarian Nobel laureates, the Hungarian Academy of Sciences, the university, the medical school, agricultural sciences, and technology and engineering. One chapter is about selected gimnáziums from which seven Nobel laureates (Szent-Györgyi, de Hevesy, Wigner, Gabor, Harsanyi, Olah, and Kertész) and the five “Martians of Science” (von Kármán, Szilard, Wigner, von Neumann, and Teller...

  1. Performance of TOF powder diffractometers on reactor sources

    Energy Technology Data Exchange (ETDEWEB)

    Peters, Judith [Hahn-Meitner-Institut Berlin, Glienicker Str. 100, D-14109 Berlin (Germany)]. E-mail: peters@hmi.de; Bleif, Hans-Juergen [Hahn-Meitner-Institut Berlin, Glienicker Str. 100, D-14109 Berlin (Germany); Kali, Gyoergy [Budapest Research Reactor, 1121 Budapest, Konkoly Thege ut 29-33 (Hungary); Rosta, Laszlo [Research Institute for Solid State Physics and Optics, 1525 Budapest, P.O.B. 49 (Hungary); Mezei, Ferenc [Hahn-Meitner-Institut Berlin, Glienicker Str. 100, D-14109 Berlin (Germany): LANSCE, Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)

    2006-11-15

    In 1998, a prototype of a time-of-flight (TOF) powder diffractometer was built at KFKI in Budapest in collaboration with the Hahn-Meitner-Institut (HMI) in Berlin. At a reactor source the neutron pulses are produced by a chopper system, which allows for shorter pulses than those obtained at pulsed spallation sources in the wavelength range most relevant for diffraction work, i.e. {lambda}{>=}0.7 A. Furthermore, the chopper system provides an ideal symmetric line shape. First results proved the high potential of the approach, namely an excellent resolution of 1-5x10{sup -3} for {delta}d/d was achieved. The prototype is presently rebuilt as a user instrument at the Budapest Neutron Centre. At HMI Berlin a new much more complex TOF powder diffractometer (EXED=extreme environment diffractometer) with higher resolution is under construction. It will benefit from variable resolution to achieve either ultrahigh resolution or very high intensities at conventional resolutions. EXED is devoted to studies under extreme sample conditions, for instance the TOF technique permits the access of a broad range of Q-values or d-spacing domains under scattering angle access strongly restricted by the use of highest field magnets. The whole instrument was simulated by Monte Carlo (MC) technique, and the simulations yield promising results.

  2. Performance of TOF powder diffractometers on reactor sources

    International Nuclear Information System (INIS)

    In 1998, a prototype of a time-of-flight (TOF) powder diffractometer was built at KFKI in Budapest in collaboration with the Hahn-Meitner-Institut (HMI) in Berlin. At a reactor source the neutron pulses are produced by a chopper system, which allows for shorter pulses than those obtained at pulsed spallation sources in the wavelength range most relevant for diffraction work, i.e. λ≥0.7 A. Furthermore, the chopper system provides an ideal symmetric line shape. First results proved the high potential of the approach, namely an excellent resolution of 1-5x10-3 for Δd/d was achieved. The prototype is presently rebuilt as a user instrument at the Budapest Neutron Centre. At HMI Berlin a new much more complex TOF powder diffractometer (EXED=extreme environment diffractometer) with higher resolution is under construction. It will benefit from variable resolution to achieve either ultrahigh resolution or very high intensities at conventional resolutions. EXED is devoted to studies under extreme sample conditions, for instance the TOF technique permits the access of a broad range of Q-values or d-spacing domains under scattering angle access strongly restricted by the use of highest field magnets. The whole instrument was simulated by Monte Carlo (MC) technique, and the simulations yield promising results

  3. Reactor simulator development. Workshop material

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in reactor operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. This publication consists of course material for workshops on development of such reactor simulators. Participants in the workshops are provided with instruction and practice in the development of reactor simulation computer codes using a model development system that assembles integrated codes from a selection of pre-programmed and tested sub-components. This provides insight and understanding into the construction and assumptions of the codes that model the design and operational characteristics of various power reactor systems. The main objective is to demonstrate simple nuclear reactor dynamics with hands-on simulation experience. Using one of the modular development systems, CASSIMtm , a simple point kinetic reactor model is developed, followed by a model that simulates the Xenon/Iodine concentration on changes in reactor power. Lastly, an absorber and adjuster control rod, and a liquid zone model are developed to control reactivity. The built model is used to demonstrate reactor behavior in sub-critical, critical and supercritical states, and to observe the impact of malfunctions of various reactivity control mechanisms on reactor dynamics. Using a PHWR simulator, participants practice typical procedures for a reactor startup and approach to criticality. This workshop material consists of an introduction to systems used for developing reactor simulators, an overview of the dynamic simulation

  4. Research reactor activities in support of national nuclear programmes

    International Nuclear Information System (INIS)

    This report is the result of an IAEA Technical Committee Meeting on Research Reactor Activities in Support of National Nuclear Programmes held in Budapest, Hungary during 10-13 December 1985. The countries represented were Belgium, Finland, France, Federal Republic of Germany, German Democratic Republic, India, Poland, Spain, United Kingdom, United States, Yugoslavia and Hungary. The purpose of the meeting was to present information and details of several well-utilized research reactors and to discuss their contribution to national nuclear programmes. A related Agency activity, a Seminar on Applied Research and Service Activities for Research Reactor Operations was held in Copenhagen, Denmark during 9-13 September 1985. Selected papers from this Seminar relevant to the topic of research reactor support of national nuclear programmes have been included in this report. A separate abstract was prepared for each of 19 papers presented at the Technical Committee Meeting on Research Reactor Activities in Support of National Nuclear Programmes and for each of 15 papers selected from the presentations of the Seminar on Applied Research and Service Activities for Research Reactor Operations

  5. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015; Budapest (Hungary; September 16-20, 2015; Session “Pulmonology”

    Directory of Open Access Journals (Sweden)

    Various Authors

    2015-09-01

    Full Text Available Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015; Budapest (Hungary; September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN, European Society for Paediatric Research (ESPR, Union of European Neonatal & Perinatal Societies (UENPS, European Foundation for the Care of Newborn Infants (EFCNI, with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (MPT, supported by Council of International Neonatal Nurses (COINN, organizing secretariat MCA Scientific EventsPROGRAMME COMMITTEEArtúr Beke (Hungarian Society, Morten Breindahl (ESN, Giuseppe Buonocore (UENPS, Pierre Gressens (ESPR, Silke Mader (EFCNI, Manuel Sánchez Luna (UENPS, Miklós Szabó (Hungarian Society of Perinatology, Luc Zimmermann (ESPR Session “Pulmonology”ABS 1. URINE NEUTROPHIL GELATINASE-ASSOCIATED LIPOCALIN AS A MARKER OF BRONCHOPULMONARY DYSPLASIA AND RETINOPATHY OF PREMATURITY IN PRETERM NEONATES • H. Ergin, T. Atilgan, M. Dogan, O.M.A. Ozdemir, C. YeniseyABS 2. LUNG COMPLIANCE AND LUNG ULTRASOUND DURING POSTNATAL ADAPTATION IN HEALTHY NEWBORN INFANTS • L. Süvari, L. Martelius, C. Janér, A. Kaskinen, O. Pitkänen, T. Kirjavainen, O. Helve, S. AnderssonABS 3. PRE-DISCHARGE RESPIRATORY OUTCOMES IN SMALL-FOR-GESTATIONAL-AGE AND APPROPRIATE-FOR-GESTATIONAL-AGE VERY PRETERM INFANTS • A. Matic, A. RistivojevicABS 4. THE EFFECT OF CHANGING OXYGEN SATURATION TARGET RANGE ON COMPLIANCE IN OXYGEN SATURATION TARGETING IN THE NEONATAL INTENSIVE CARE UNIT • H.A. van Zanten, S. Pauws, E.C.H. Beks, B.J. Stenson, E. Lopriore, A.B. te PasABS 5. BINASAL PRONG VERSUS NASAL MASK FOR APPLYING CPAP TO PRETERM INFANTS: RANDOMIZED CONTROLLED TRIAL • B. Say, G. Kanmaz, S.S. OguzABS 6. TRAINING AND RAISING AWARENESS IMPROVES COMPLIANCE IN OXYGEN SATURATION TARGETING IN THE NEONATAL INTENSIVE CARE UNIT • H.A. van Zanten, S. Pauws, E.C.H. Beks, B.J. Stenson, E

  6. Approach to team skills training

    International Nuclear Information System (INIS)

    The US commercial nuclear power industry has recognized the importance of team skills in control room operation. The desire to combine training of team interaction skills, like communications, with technical knowledge of reactor operations requires a unique approach to training. An NRC-sponsored study identified a five-phase approach to team skills training designed to be consistent with the systems approach to training currently endorsed by the NRC Policy Statement on Training and Qualification. This paper describes an approach to team skills training with emphasis on the nuclear power plant control room crew. An approach to team skills training

  7. Monju operator training report. Training results and upgrade of the operation training simulator in 2005 FY

    International Nuclear Information System (INIS)

    The prototype fast breeder reactor, Monju, has been performing deliberately the operator training which is composed of the regulated training required by the government and the self-training. The training used a full scope type simulator (MARS: Monju Advanced Reactor Simulator) plays an important role among of the above mentioned trainings and greatly contributes to the Monju operator training for Monju restarting. This report covers the activities of Monju operator training in 2005 FY, i.e. the training results, modification and maintenance of the MARS. (1) Eight simulator training courses were carried out 42 times and 205 trainees participated. Compared with the preceding year, the numbers increased 7 times and 55 trainees. (2) Not only Monju operator training but also university student training was added. The university students study the system of Monju by this training. We will promote cooperation with a university more from now on. (3) The operator of the fast reactor in China was educated this year. This training is a part of sodium handling training. (author)

  8. SEVERE ACCIDENT MANAGEMENT TRAINING

    International Nuclear Information System (INIS)

    The purpose of this paper is (a) to define the International Atomic Energy Agency's role in the area of severe accident management training, (b) to briefly describe the status of representative severe accident analysis tools designed to support development and validation of accident management guidelines, and more recently, simulate the accident with sufficient accuracy to support the training of technical support and reactor operator staff, and (c) provide an overview of representative design-specific accident management guidelines and training. Since accident management and the development of accident management validation and training software is a rapidly evolving area, this paper is also intended to evolve as accident management guidelines and training programs are developed to meet different reactor design requirements and individual national requirements

  9. External audit on the clinical practice and medical decision-making at the departments of radiotherapy in Budapest and Vienna

    International Nuclear Information System (INIS)

    Purpose: To present an example of how to study and analyze the clinical practice and the quality of medical decision-making under daily routine working conditions in a radiotherapy department, with the aims of detecting deficiencies and improving the quality of patient care.Methods: Two departments, each with a divisional organization structure and an established internal audit system, the University Clinic of Radiotherapy and Radiobiology in Vienna (Austria), and the Department of Radiotherapy at the National Institute of Oncology in Budapest (Hungary), conducted common external audits. The descriptive parameters of the external audit provided information on the auditing (auditor and serial number of the audit), the cohorts (diagnosis, referring institution, serial number and intention of radiotherapy) and the staff responsible for the treatment (division and physician). During the ongoing external audits, the qualifying parameters were (1) the sound foundation of the indication of radiotherapy, (2) conformity to the institution protocol (3), the adequacy of the choice of radiation equipment, (4) the appropriateness of the treatment plan, and the correspondence of the latter with (5) the simulation and (6) verification films. Various degrees of deviation from the treatment principles were defined and scored on the basis of the concept of Horiot et al. (Horiot JC, Schueren van der E, Johansson KA, Bernier J, Bartelink H. The program of quality assurance of the EORTC radiotherapy group. A historical overview. Radiother. Oncol. 1993;29:81-84), with some modifications. The action was regarded as adequate (score 1) in the event of no deviation or only a small deviation with presumably no alteration of the desired end-result of the treatment. A deviation adversely influencing the result of the therapy was considered a major deviation (score 3). Cases involving a minor deviation (score 2) were those only slightly affecting the therapeutic end-results, with effects

  10. Isochron burial dating of Danube terraces in the course of an interlaboratory comparison on sample preparation in Vienna and Budapest

    Science.gov (United States)

    Neuhuber, Stephanie; Ruszkiczay-Rüdiger, Zsófia; Decker, Kurt; Braucher, Regis; Fiebig, Markus; Braun, Mihály; Häuselmann, Philipp; Aster Team

    2016-04-01

    -depositional history, but have different pre-exposure and transport histories [4]. The sandy gravel of the Haslau terrace was sampled in an active gravel pit. At this location, two major sedimentary units are separated by an erosional hiatus of unknown duration. The upper sequence was sampled at 5.5 m depth and the lower one was sampled at 11.8 m depth. From both depths six quartzite or quartz-bearing cobbles were taken together with a bulk sample from the matrix for isochron burial duration determination. Five samples were split after crushing and sieving and were processed at both the Cosmogenic Nuclide Sample Preparation Laboratory at Vienna and at Budapest (http://www.geochem.hu/kozmogen/Lab_en.html), in order to assess and compare the sample processing preocedures of these recently operating sample preparation laboratories. AMS measurements were performed at the French national facility ASTER (CEREGE (Aix-en-Provence, France). Thanks to OTKA PD83610, NKM-96/2014, NKM-31/2015; OMAA 90öu17; LP2012-27/2012. INSU/CNRS, the ANR through the program "EQUIPEX Investissement d'Avenir", IRD and CEA. [1] Decker et al., 2005. QSR 24, 307-322 [2] Hintersberger et al, 2013, EGU2013-12755 [3] Salcher et al. 2012. Tectonics, 31, TC3004, doi:10.1029/2011TC002979 [4] Balco and Rovey, 2008. AJS 908, 1083-1114 [5] Fuchs and Grill, 1984, Geologische Gebietskarte der Republik Österreich 1:200 000 Wien und Umgebung

  11. Problems of Decommissioning Research Reactor IR-100

    International Nuclear Information System (INIS)

    The research reactor IR-100 with a thermal power of 200 kW is assigned to conduct science research and training activities in the fields of nuclear and molecular physics, radiation chemistry, radioactive isotope production, material, irradiation in neutron and gamma fields of devices and equipment, as well as for training of specialists for nuclear reactor operation

  12. Nuclear Business Acumen Training for Executives

    International Nuclear Information System (INIS)

    The presentation is structured as follows: Failure in large technology projects; Simulations in industry; Training in reactor simulators; Business simulation; NPP business simulation Nuclear Inc.; Knowledge retention; Boosting the effect of training; Contact

  13. Final Stage Development of Reactor Console Simulator

    International Nuclear Information System (INIS)

    The Reactor Console Simulator PUSPATI TRIGA Reactor was developed since end of 2011 and now in the final stage of development. It is will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behavior and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of human system interface (HSI) is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate and estimated reactor console parameters. The capabilities in user interface, reactor physics and thermal-hydraulics can be expanded and explored to simulation as well as modeling for New Reactor Console, Research Reactor and Nuclear Power Plant. (author)

  14. Research reactor support

    International Nuclear Information System (INIS)

    Research reactors (RRs) have been used in a wide range of applications including nuclear power development, basic physics research, education and training, medical isotope production, geology, industry and other fields. However, many research reactors are fuelled with High Enriched Uranium (HEU), are underutilized and aging, and have significant quantities of spent fuel. HEU inventories (fresh and spent) pose security risks Unavailability of a high-density-reprocessable fuel hinders conversion and limits back-end options and represents a survival dilemma for many RRs. Improvement of interim spent fuel storage is required at some RRs. Many RRs are under-utilized and/or inadequately funded and need to find users for their services, or permanently shut down and eventually decommission. Reluctance to decommission affect both cost and safety (loss of experienced staff ) and many shut down but not decommissioned RR with fresh and/or spent fuel at the sites invoke serious concern. The IAEA's research reactor support helps to ensure that research reactors can be operated efficiently with fuels and targets of lower proliferation and security concern and that operators have appropriate technology and options to manage RR fuel cycle issues, especially on long term interim storage of spent research reactor fuel. Availability of a high-density-reprocessable fuel would expand and improve back end options. The International Atomic Energy Agency provides assistance to Member States to convert research reactors from High Enriched Uranium fuel and targets (for medical isotope production) to qualified Low Enriched Uranium fuel and targets while maintaining reactor performance levels. The assistance includes provision of handbooks and training in the performance of core conversion studies, advice for the procurement of LEU fuel, and expert services for LEU fuel acceptance. The IAEA further provides technical and administrative support for countries considering repatriation of its

  15. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    The general design, characteristics and parameters of TRIGA reactors and fuel are described. This is a training module with the learning objectives: to understand the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and realize the differences between TRIGA fuels and other more traditional. 10 figs., 6 tabs. (nevyjel)

  16. Reactor operation experience

    International Nuclear Information System (INIS)

    Since the TRIGA Users Conference in Helsinki 1970 the TRIGA reactor Vienna was in operation without any larger undesired shutdown. The integrated thermal power production by August 15 1972 accumulated to 110 MWd. The TRIGA reactor is manly used for training of students, for scientific courses and research work. Cooperation with industry increased in the last two years either in form of research or in performing training courses. Close cooperation is also maintained with the IAEA, samples are irradiated and courses on various fields are arranged. Maintenance work was performed on the heat exchanger and to replace the shim rod magnet. With the view on the future power upgrading nine fuel elements type 110 have been ordered recently. Experiments, performed currently on the reactor are presented in details

  17. 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...

  18. Therapy results of malignant tumors of the paranasal sinuses in patients treated at the Metropolitan Onco-Radiologic Centre of Budapest

    International Nuclear Information System (INIS)

    A report is given on the therapy of 301 patients with ethmoidomaxillary tumors treated at the Metropolitan Onco-Radiologic Centre of Budapest between 1946 und 1974. Most of these patients were in an advanced stage when the first diagnosis was established. The five-year survival rate of all stages was 27%, which does not strongly differ from the average falue of 30% mentioned in literature. The five-year survival rate of the patients submitted to a combined surgical and radiologic treatment was 33%, that of the patients treated by irradiations only was 16%. 81 patients received an intracavitary brachycurietherapy after having undergone a non-radical operation. The five-year survival rate of this group was 38%. The intracavitary brachycurietherapy is most favorable and should always be applied in case of this not very radiosensible, often even radioresistant tumor. (orig.)

  19. Statistical analysis in the design of nuclear fuel cells and training of a neural network to predict safety parameters for reactors BWR; Analisis estadistico en el diseno de celdas de combustible nuclear y entrenamiento de una red neuronal para predecir parametros de seguridad para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Jauregui Ch, V.

    2013-07-01

    In this work the obtained results for a statistical analysis are shown, with the purpose of studying the performance of the fuel lattice, taking into account the frequency of the pins that were used. For this objective, different statistical distributions were used; one approximately to normal, another type X{sup 2} but in an inverse form and a random distribution. Also, the prediction of some parameters of the nuclear reactor in a fuel reload was made through a neuronal network, which was trained. The statistical analysis was made using the parameters of the fuel lattice, which was generated through three heuristic techniques: Ant Colony Optimization System, Neuronal Networks and a hybrid among Scatter Search and Path Re linking. The behavior of the local power peak factor was revised in the fuel lattice with the use of different frequencies of enrichment uranium pines, using the three techniques mentioned before, in the same way the infinite multiplication factor of neutrons was analyzed (k..), to determine within what range this factor in the reactor is. Taking into account all the information, which was obtained through the statistical analysis, a neuronal network was trained; that will help to predict the behavior of some parameters of the nuclear reactor, considering a fixed fuel reload with their respective control rods pattern. In the same way, the quality of the training was evaluated using different fuel lattices. The neuronal network learned to predict the next parameters: Shutdown Margin (SDM), the pin burn peaks for two different fuel batches, Thermal Limits and the Effective Neutron Multiplication Factor (k{sup eff}). The results show that the fuel lattices in which the frequency, which the inverted form of the X{sup 2} distribution, was used revealed the best values of local power peak factor. Additionally it is shown that the performance of a fuel lattice could be enhanced controlling the frequency of the uranium enrichment rods and the variety of

  20. Unique approaches in emphasizing the role of reactor laboratories and facilities for training and education of future nuclear engineers 'without the borders'

    International Nuclear Information System (INIS)

    The 21st century brings numerous challenges into daily lives of nuclear engineers worldwide, such as at nuclear power plants (facing new safety paradigm influenced by 2011-unfortunate Japanese Fukushima incident), at the universities in educating and training new generations of nuclear engineers in capturing new expectations of safety standards, and in reaching out to countries that are interested to develop new or revitalize their decades-old education and training programs as pertaining to nuclear engineering and science. In this paper we present two novel aspects we have developed: (a) the establishment of novel educational approaches pertaining to training and practices of nuclear safety culture in university curricula, and (b) development of novel digital-type class focused on the basic aspects of nuclear science and engineering shared between a class in the State of Utah (USA) and Uruguay. (author)

  1. Oxygen influence on water chemistry and steel corrosion in its injection in the low temperature part of the condensate/feed train of NPS with a RBMK-1000 reactor

    International Nuclear Information System (INIS)

    Injection of gaseous oxygen in condensate reduces steel corrosion. However, the information is lacking on possible influence of oxygen on the corrosion of steels with different chrome content and water iron concentration in the low-temperature part of the condensate/feedwater train of NPS with a RBMK-1000 reactor. A 1600 h.test experiment was carried out at the Leningrad NPS with water oxygen concentration of 200 mg/kg, and conductivity not higher than 0.2 ms/cm. All the steels tested demonstrated the 10-fold reduction of corrosion and release of corrosion products into water. The 2.5% chrome alloying of steel results in strong reduction (in respect to steel 20) of corrosion product release. (author)

  2. A radiation protection training program designed to reduce occupational radiation dose to individuals using pneumatic-transfer systems at the Oregon State TRIGA reactor

    International Nuclear Information System (INIS)

    In order to keeping personnel doses as low as reasonably achievable, and also to help satisfy requirements of NRC regulations contained in 10 CFR 19, a training program was established to qualify all individuals prior to their use of the OSTR PT systems. Program objectives are directed mainly towards minimizing the spread of radioactive contamination and reducing the potential for unnecessary and inappropriate personnel radiation exposure; however, other operational and emergency procedures are also covered. The PT systems training program described in this report was established approximately 8 to 10 years ago but recently there was an increased interest to use it. Whether or not a PT system training program should be implemented at a specific TRIGA operation (assuming the facility is equipped with a PT system) will undoubtedly be influenced heavily by the nature and frequency of the PT system's use, by who uses the system, and by whether the system is one of the automatic loading and unloading types, or one of the more' commonly encountered manually operated systems. However, from our experience we feel that training commensurate with the type of PT system operation being conducted is a wise investment, and should be a requirement for all system operators

  3. Contents of the RA reactor Safety Report - Annex G

    International Nuclear Information System (INIS)

    RA reactor safety report covers the following four main Chapters: 1. Technical characteristics and safety analysis of the Ra reactor; 2. Regulations for RA reactor operation; 3. Procedures and instructions for RA reactor operation; and 4. Training of the staff and quality assurance for operation and maintenance of the RA reactor. This Annex includes detailed content of the mentioned chapters of the RA reactor safety report

  4. Multi-purpose reactor

    International Nuclear Information System (INIS)

    The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MWth, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co60) production capacity is 50000 Ci/yr, 200Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

  5. TOF powder diffractometer on a reactor source

    International Nuclear Information System (INIS)

    Complete text of publication follows. The performance of time-of-flight (TOF) methods on Long Pulse Spallation Sources can be studied at a reactor source. For this purpose a prototype TOF monochromator instrument will be installed at the KFKI reactor in Budapest. The initial setup will be a powder diffractometer with a resolution of δd/d down to 2 x 10-3 at a wavelength of 1 A. The instrument uses choppers to produce neutron pulses of down to 10 μs FWHM. The optimal neutron source for a chopper instrument is a Long Pulse Spallation Source, but even on a continuous source simulations have shown that this instrument outperforms a conventional crystal monochromator powder diffractometer at high resolution. The main components of the TOF instrument are one double chopper defining the time resolution and two single choppers to select the wavelength range and to prevent frame overlap. For inelastic experiments a further chopper can be added in front of the sample. The neutron guide has a super-mirror coating and a curvature of 3500m. The total flight path is 20m and there are 24 single detectors in backscattering geometry. (author)

  6. Operation and utilizations of Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    The reconstructed Dalat nuclear research reactor was commissioned in March 1984 and up to September 1988 more than 6200 hours of operation at nominal power have been recorded. The major utilizations of the reactor include radioisotope production, activation analysis, nuclear data research and training. A brief review of the utilizations of the reactor is presented. Some aspects of reactor safety are also discussed. (author)

  7. Computer training aids for nuclear operator training

    International Nuclear Information System (INIS)

    The Royal Navy's Nuclear Propulsion School at HMS SULTAN which is responsible for training all ratings and officers who operate Submarine Pressurised Water Reactor plants, has available a varied selection of classroom simulator training aids as well as purpose built Submarine Manoeuvring Room simulators. The use of these classroom training aids in the twelve months prior to Autumn 1981 is discussed. The advantages and disadvantages of using relatively expensive computer based aids to support classroom instruction for students who do not investigate mathematically the dynamics of the Reactor Plant are identified. The conclusions drawn indicate that for students of limited academic ability the classroom simulators are disproportionately expensive in cost, maintenance load, and instructional time. Secondly, the experience gained in the use of the Manoeuvring Room Simulators to train future operators who have just finished the academic phase of their training is outlined. The possible pitfalls for the instructor are discussed and the lessons learnt, concluding that these simulators provide a valuable substitute for the live plant enabling trainees to be brought up to a common standard and reducing their on job training time to an acceptable level. (author)

  8. Training safely, Training safety

    OpenAIRE

    Jianjun Wu; An, M.; Jin, Y.; H. Geng

    2014-01-01

    It is the basic requirement of maritime safety education to guarantee the safety of teaching operation while training the crew's occupation safety capability. Marine Training Center of Shanghai Maritime University has undertaken the practical teaching of "marine survival" for many years and come up with the whole safety procedures of training. Based on the requirements of SOLAS convention and regulations of STCW over crew training, this paper introduces the safety allocation, utilization and ...

  9. Research reactor job analysis - A project description

    International Nuclear Information System (INIS)

    Addressing the need of the improved training in nuclear industry, nuclear utilities established training program guidelines based on Performance-Based Training (PBT) concepts. The comparison of commercial nuclear power facilities with research and test reactors owned by the U.S. Department of Energy (DOE), made in an independent review of personnel selection, training, and qualification requirements for DOE-owned reactors pointed out that the complexity of the most critical tasks in research reactors is less than that in power reactors. The U.S. Department of Energy (DOE) started a project by commissioning Oak Ridge Associated Universities (ORAU) to conduct a job analysis survey of representative research reactor facilities. The output of the project consists of two publications: Volume 1 - Research Reactor Job Analysis: Overview, which contains an Introduction, Project Description, Project Methodology,, and. An Overview of Performance-Based Training (PBT); and Volume 2 - Research Reactor Job Analysis: Implementation, which contains Guidelines for Application of Preliminary Task Lists and Preliminary Task Lists for Reactor Operators and Supervisory Reactor Operators

  10. Netherlands Interuniversity Reactor Institut

    International Nuclear Information System (INIS)

    This is the annual report of the Interuniversity Reactor Institute in the Netherlands for the Academic Year 1977-78. Activities of the general committee, the daily committee and the scientific advice board are presented. Detailed reports of the scientific studies performed are given under five subjects - radiation physics, reactor physics, radiation chemistry, radiochemistry and radiation hygiene and dosimetry. Summarised reports of the various industrial groups are also presented. Training and education, publications and reports, courses, visits and cooperation with other institutes in the area of scientific research are mentioned. (C.F.)

  11. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Paper dwells upon the design and the operation of one of the German test reactors, namely, the TRIGA Mainz one (TRIGA: Training Research Isotope Production General Atomic). The TRIGA reactor is a pool test reactor the core of which contains a graphite reflector and is placed into 2 m diameter and 6.25 m height aluminum vessel. There are 75 fuel elements in the reactor core, and any of them contains about 36 g of 235U. The TRIGA reactors under the stable operation enjoy wide application to ensure tests and irradiation, namely: neutron activation analysis, radioisotope production, application of a neutron beam to ensure the physical, the chemical and the medical research efforts. Paper presents the reactor basic experimental program lines

  12. Operating experiences of the research reactors

    International Nuclear Information System (INIS)

    Nuclear research reactors are devices of wide importance, being used for different scientific research tasks, for testing and improving reactor systems and components, for the production of radioisotopes, for the purposes of defence, for staff training and for other purposes. There are three research reactors in Yugoslavia: RA, RB and TRIGA. Reactors RA and RB at the 'Boris Kidric' Institute of Nuclear Sciences are of heavy water type power being 6500 and 10 kW, and maximum thermal neutron flux of 1014 and 1011(n/cm2s), respectively. TRIGA reactor at the 'Jozef Stefan' Institute in Ljubljana is of 250 kW power and maximum thermal neutron flux of 1013(n/cm2s). Reactors RA and RB use soviet fuel in the form of uranium dioxide (80% enriched) and metallic uranium (2%). Besides, RB reactor operates with natural uranium too. TRIGA reactor uses american uranium fuel 70% and 20% enriched, uranium being mixed homogeneously with moderator (ZrH). Experiences in handling and controlling the fuel before irradiation in the reactor, in reactor and after it are numerous and valuable, involving either the commercial arrangements with foreign producers, or optimal burn up in reactor or fuel treatment after the reactor irradiation. Twenty years of operating experience of these reactors have great importance especially having in mind the number of trained staff. Maintenance of reactors systems and fluids in continuous operation is valuable experience from the point of view of water reactor utilization. The case of the RA reactor primary cycle cobalt decontamination and other events connected with nuclear and radiation security for all three reactors are also specially emphasized. Owing to our research reactors, numerous theoretical, numerical and experimental methods are developed for nuclear and other analyses and design of research and power reactors,as well as methods for control and protection of radiation. (author)

  13. Reactor Physics

    International Nuclear Information System (INIS)

    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

  14. Reactor Physics

    International Nuclear Information System (INIS)

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

  15. 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.

  16. Research reactors: design, safety requirements and applications

    International Nuclear Information System (INIS)

    There are two types of reactors: research reactors or power reactors. The difference between the research reactor and energy reactor is that the research reactor has working temperature and fuel less than the power reactor. The research reactors cooling uses light or heavy water and also research reactors need reflector of graphite or beryllium to reduce the loss of neutrons from the reactor core. Research reactors are used for research training as well as testing of materials and the production of radioisotopes for medical uses and for industrial application. The difference is also that the research reactor smaller in terms of capacity than that of power plant. Research reactors produce radioactive isotopes are not used for energy production, the power plant generates electrical energy. In the world there are more than 284 reactor research in 56 countries, operates as source of neutron for scientific research. Among the incidents related to nuclear reactors leak radiation partial reactor which took place in three mile island nuclear near pennsylvania in 1979, due to result of the loss of control of the fission reaction, which led to the explosion emitting hug amounts of radiation. However, there was control of radiation inside the building, and so no occurred then, another accident that lead to radiation leakage similar in nuclear power plant Chernobyl in Russia in 1986, has led to deaths of 4000 people and exposing hundreds of thousands to radiation, and can continue to be effect of harmful radiation to affect future generations. (author)

  17. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015; Budapest (Hungary; September 16-20, 2015; Session “Other”

    Directory of Open Access Journals (Sweden)

    Various Authors

    2015-09-01

    . Al Omran, S. AL AbdiABS 44. DECREASE OF ADMISSION HYPOTHERMIA AMONG NEWBORNS IN NICU • A. Bystricka, J. Abu Asbeh, M. Qadir, K. Annadurai, J.M. KhanABS 45. LUNG ULTRASOUND TRAINING REDUCES RADIATION EXPOSURE IN NICU-ADMITTED PRETERM NEONATES • G. Escourrou, N. Yousef, A. Debray, C. Boussard, D. De LucaABS 46. POST-DISCHARGE NEONATAL FOLLOW-UP OF HYPERBILIRUBINEMIA BASED ON TRANSCUTANEOUS BILIRUBINOMETRY. RELIABILITY AND EFFICACY IN TERM AND NEAR-TERM INFANTS • A. Juster-Reicher, O. Flidel-Rimon, I. Vexler, I. Rozin, E.S. ShinwellABS 47. DECISION-MAKING FOR EXTREMELY PRETERM INFANTS: A SURVEY ABOUT THE ATTITUDES AND VALUES WITHIN A MULTI-CULTURAL SOCIETY • M. Hendriks, H.U. Bucher, S. Klein, R. Baumann-Hölzle, J.-C. FauchèreABS 48. EFFICACY OF SYSTEMIC FLUCONAZOLE PROPHYLAXIS IN REDUCTION OF SYSTEMIC CANDIDIASIS IN EXTREMELY LOW BIRTHWEIGHT (ELBW INFANTS • V.S. Rajadurai, B. Sriram, P.C. Khoo, J.M. Manuel, P. AgarwalABS 49. DEVELOPING COLLABORATION BETWEEN STAFF AND PARENTS IN THE NICU AT HONVED KORHAZ, BUDAPEST, HUNGARY • Z. Boukydis, C. Nador, B. Schill, A. LengyelABS 50. MACRO- AND MICROANALYSIS OF EARLY MOTHER-PRETERM INFANT INTERACTIONS: IMPLICATIONS FOR PREVENTIVE INTERVENTION • E. Kiepura, G. KmitaABS 51. ANXIETY AND DEPRESSION IN MOTHERS AND FATHERS OF A VERY PRETERM BORN CHILD AFTER HOSPITAL DISCHARGE • M. Jeukens-Visser, M. Husson, K. Koldewijn, A. Wassenaer-van Leemhuis, M. Flierman, D. Meijssen, P. van SchieABS 52. TRANSCRIPTIONAL REGULATION OF SEX-SPECIFIC GONADAL DIFFERENTIATION INVOLVES COOPERATION BETWEEN WT1 AND GATA4 ON FOXL2 AND SOX9 EXPRESSION • C. Dame, L.J. Rudigier, H. Scholz, K.M. KirschnerABS 53. BACTERIOLOGICAL SAFETY IN TRANSPORT, A CONTINUOUS CHALLENGE • G. Jourdain, P. Quentin, V. Derouin, A. Boet, J.L. Chabernaud, D. De LucaABS 54. GUIDELINES FOR NEONATAL SURGERY IN ITALY: WORK IN PROGRESS • I. Bernardini, M. Chiavarini, S. Tesoro, L. Marchesini, D. Bologni, W. Orlandi, M. PioppoABS 55. ADOPTION OF ASEPTIC NON

  18. 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

  19. 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

  20. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015; Session “Nutrition and gastroenterology”

    OpenAIRE

    Various Authors

    2015-01-01

    Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN), European Society for Paediatric Research (ESPR), Union of European Neonatal & Perinatal Societies (UENPS), European Foundation for the Care of Newborn Infants (EFCNI), with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (MPT),...

  1. Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015; Session “Circulation, O2 Transport and Haematology”

    OpenAIRE

    Various Authors

    2015-01-01

    Selected Abstracts of the 1st Congress of joint European Neonatal Societies (jENS 2015); Budapest (Hungary); September 16-20, 2015ORGANIZING INSTITUTIONSEuropean Society for Neonatology (ESN), European Society for Paediatric Research (ESPR), Union of European Neonatal & Perinatal Societies (UENPS), European Foundation for the Care of Newborn Infants (EFCNI), with the local host of Hungarian Society of Perinatology and Obstetric Anesthesiology, Hungarian Society of Perinatology (MPT),...

  2. Team skills training

    International Nuclear Information System (INIS)

    Numerous reports and articles have been written recently on the importance of team skills training for nuclear reactor operators, but little has appeared on the practical application of this theoretical guidance. This paper describes the activities of the Training and Education Department at GPU Nuclear (GPUN). In 1987, GPUN undertook a significant initiative in its licensed operator training programs to design and develop initial and requalification team skills training. Prior to that time, human interaction skills training (communication, stress management, supervisory skills, etc.) focused more on the individual rather than a group. Today, GPU Nuclear conducts team training at both its Three Mile Island (YMI), PA and Oyster Creek (OC), NJ generating stations. Videotaped feedback is sued extensively to critique and reinforce targeted behaviors. In fact, the TMI simulator trainer has a built-in, four camera system specifically designed for team training. Evaluations conducted on this training indicated these newly acquired skills are being carried over to the work environment. Team training is now an important and on-going part of GPUN operator training

  3. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  4. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-09-01

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

  5. Language Training: English Training

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. Language Training Françoise Benz tel. 73127 language.training@cern.ch General and Professional English Courses The next session will take place: from 1st March to 25 June 2004 (2 weeks break at Easter). These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mr. Liptow: tel. 72957.

  6. Language Training: English Training

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. LANGUAGE TRAINING Françoise Benz tel. 73127 language.training@cern.ch General and Professional English Courses The next session will take place: from 1st March to 25 June 2004 (2 weeks break at Easter). These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mr. Liptow: tel. 72957.

  7. The MNSR reactor

    International Nuclear Information System (INIS)

    This tank-in-pool reactor is based on the same design concept as the Canadian Slowpoke. The core is a right circular cylinder, 24 cm diameter by 25 cm long, containing 411 fuel pin positions. The pins are HEU-Aluminium alloy, 0.5 cm in diameter. Critical mass is about 900 g. The reactor has a single cadmium control rod. The back-up shutdown system is the insertion of a cadmium capsule in a core position. Excess reactivity is limited to 3.5mk. In both the MNSR and Slowpoke, the insertion of the maximum excess reactivity results in a power transient limited by the coolant/moderator temperature to safe values, independent of any operator action. This reactor is used primarily in training and neutron activation analysis. Up to 64 elements have been analyzed in a great variety of different disciplines. (author)

  8. Guide to good practices for training and qualification of instructors. DOE handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    Purpose of this guide is to provide contractor training organizations with information that can be used to verify the adquacy and/or modify existing instructor training programs, or to develop new training programs. It contains good practices for the training and qualification of technical instructors and instructional technologists at DOE reactor and non-reactor nuclear facilities. It addresses the content of initial and continuing instructor training programs, evaluation of instructor training programs, and maintenance of instructor training records.

  9. Training methods, tools and aids

    International Nuclear Information System (INIS)

    The training programme, training methods, tools and aids necessary for staffing nuclear power plants depend very much on the overall contractual provisions. The basis for training programmes and methods is the definition of the plant organization and the prequalification of the personnel. Preselection tests are tailored to the different educational levels and precede the training programme, where emphasis is put on practical on-the-job training. Technical basic and introductory courses follow language training and give a broad but basic spectrum of power plant technology. Plant-related theoretical training consists of reactor technology training combined with practical work in laboratories, on a test reactor and of the nuclear power plant course on design philosophy and operation. Classroom instruction together with video tapes and other audiovisual material which are used during this phase are described; as well as the various special courses for the different specialists. The first step of on-the-job training is a practical observation phase in an operating nuclear power plant, where the participants are assigned to shift work or to the different special departments, depending on their future assignment. Training in manufacturers' workshops, in laboratories or in engineering departments necessitate other training methods. The simulator training for operating personnel, for key personnel and, to some extent, also for maintenance personnel and specialists gives the practical feeling for nuclear power plant behaviour during normal and abnormal conditions. During the commissioning phase of the own nuclear power plant, which is the most important practical training, the participants are integrated into the commissioning staff and are assisted during their process of practical learning on-the-job by special instructors. Personnel training also includes performance of training of instructors and assistance in building up special training programmes and material as well

  10. NIPS–NORMA station—A combined facility for neutron-based nondestructive element analysis and imaging at the Budapest Neutron Centre

    Energy Technology Data Exchange (ETDEWEB)

    Kis, Zoltán, E-mail: kis.zoltan@energia.mta.hu; Szentmiklósi, László; Belgya, Tamás

    2015-04-11

    Neutron attenuation, scattering or radiative capture are used in various non-destructive methods to gain morphological, structural, elemental or isotopic information about the sample under study. The combined use of position-sensitive prompt gamma-ray detection (i.e. prompt gamma-ray activation imaging, PGAI) and neutron radiography/tomography (NR/NT) makes it possible to determine the 3D distribution of major elements and to visualize internal structures of heterogeneous objects in a non-destructive way. Based on earlier experience, the first ever permanent facility for this purpose, NIPS–NORMA, was constructed at the Budapest Neutron Centre, Hungary in 2012. The installation consists of a well-shielded, Compton-suppressed HPGe detector; a CCD-camera based imaging equipment and a motorized positioning system with sample support. Conventional PGAA measurements and NR/NT imaging using guided cold neutrons are the basic methods that form the basis of the more sophisticated experimental method called NR/NT-driven PGAI. The current status of the experimental station and its characteristics are described in the present paper.

  11. Elemental characterization of PM2.5 urban aerosol samples collected in Budapest (Hungary) by sector-field inductively coupled plasma mass spectrometry

    International Nuclear Information System (INIS)

    Complete text of publication follows. Nowadays, the investigation of PM10 urban aerosols in the EU member countries has become a daily routine task. The real challenge represents the characterization of aerosol particles with lower aerodynamic diameter than 10 micrometers as they do not deposit in the upper respiratory system and can even cause neoplasms. Considering the possible health effects, present investigation focuses on the PM2.5 fractions. This finer fraction is more characteristic for the anthropogenic pollutants originating from high temperature combustion processes. Therefore, PM2.5 urban aerosols were collected monthly for 96 consecutive hours on Whatmam QM-A quartz filters in a 3-month-long sampling campaign from three different representative points of Budapest (Szena Square, Gilice Square, nearby the urban waste incinerator of Kaposztasmegyer) with a Greenlab DHA-80 high-volume sampler at 500 m3/min. Twenty-three elements (Ag, Bi, Cd, Co, Cr, Cu, Fe, Ga, Li, Mn, Ni, Pt, Pb, Rb, Sb, Sn, Sr, Te, Tl, U, Mo, V, Zn) were determined after microwave-assisted aqua regia digestion by an Element2 sector-field inductively coupled plasma mass spectrometer (SF-ICP-MS). Since the bioavailability of elements is an important factor by studying their health effects, the water soluble part of the elements was also determined by SF-ICP-MS after sonication in a water bath. In addition, the TOC and TIC content of these urban aerosol fractions were determined with an TOC/N Analytik Jena equipment.

  12. NIPS–NORMA station—A combined facility for neutron-based nondestructive element analysis and imaging at the Budapest Neutron Centre

    International Nuclear Information System (INIS)

    Neutron attenuation, scattering or radiative capture are used in various non-destructive methods to gain morphological, structural, elemental or isotopic information about the sample under study. The combined use of position-sensitive prompt gamma-ray detection (i.e. prompt gamma-ray activation imaging, PGAI) and neutron radiography/tomography (NR/NT) makes it possible to determine the 3D distribution of major elements and to visualize internal structures of heterogeneous objects in a non-destructive way. Based on earlier experience, the first ever permanent facility for this purpose, NIPS–NORMA, was constructed at the Budapest Neutron Centre, Hungary in 2012. The installation consists of a well-shielded, Compton-suppressed HPGe detector; a CCD-camera based imaging equipment and a motorized positioning system with sample support. Conventional PGAA measurements and NR/NT imaging using guided cold neutrons are the basic methods that form the basis of the more sophisticated experimental method called NR/NT-driven PGAI. The current status of the experimental station and its characteristics are described in the present paper

  13. NIPS-NORMA station-A combined facility for neutron-based nondestructive element analysis and imaging at the Budapest Neutron Centre

    Science.gov (United States)

    Kis, Zoltán; Szentmiklósi, László; Belgya, Tamás

    2015-04-01

    Neutron attenuation, scattering or radiative capture are used in various non-destructive methods to gain morphological, structural, elemental or isotopic information about the sample under study. The combined use of position-sensitive prompt gamma-ray detection (i.e. prompt gamma-ray activation imaging, PGAI) and neutron radiography/tomography (NR/NT) makes it possible to determine the 3D distribution of major elements and to visualize internal structures of heterogeneous objects in a non-destructive way. Based on earlier experience, the first ever permanent facility for this purpose, NIPS-NORMA, was constructed at the Budapest Neutron Centre, Hungary in 2012. The installation consists of a well-shielded, Compton-suppressed HPGe detector; a CCD-camera based imaging equipment and a motorized positioning system with sample support. Conventional PGAA measurements and NR/NT imaging using guided cold neutrons are the basic methods that form the basis of the more sophisticated experimental method called NR/NT-driven PGAI. The current status of the experimental station and its characteristics are described in the present paper.

  14. 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)

  15. 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

  16. Reactor container

    International Nuclear Information System (INIS)

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  17. TAP 1, Training Program Manual

    International Nuclear Information System (INIS)

    Training programs at DOE nuclear facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs

  18. Pressurized water reactor simulator. Workshop material

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21 'WWER-1000 Reactor Simulator' (2002). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23 'Boiling Water Reactor Simulator' (2003). This report consists of course material for workshops using a pressurized water reactor simulator

  19. Practical course on reactor instrumentation

    International Nuclear Information System (INIS)

    This course is based on the description of the instrumentation of the TRIGA-reactor Vienna, which is used for training research and isotope production. It comprises the following chapters: 1. instrumentation, 2. calibration of the nuclear channels, 3. rod drop time of the control rods, 4. neutron flux density measurements using compensated ionization, 5. neutron flux density measurement with fission chambers (FC), 6. neutron flux density measurement with self-powered neutron detectors (SPND), 7. pressurized water reactor simulator, 8. verification of the radiation level during reactor operation. There is one appendix about neutron-sensitive thermocouples. (nevyjel)

  20. Simulator for materials testing reactors

    International Nuclear Information System (INIS)

    A real-time simulator for both reactor and irradiation facilities of a materials testing reactor, “Simulator of Materials Testing Reactors”, was developed for understanding reactor behavior and operational training in order to utilize it for nuclear human resource development and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR (Japan Materials Testing Reactor), and it simulates operation, irradiation tests and various kinds of anticipated operational transients and accident conditions caused by the reactor and irradiation facilities. The development of the simulator was sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. This report summarizes the simulation components, hardware specification and operation procedure of the simulator. (author)

  1. Training and training simulators for emergency situations in France

    International Nuclear Information System (INIS)

    The aim of this paper is to present principles and means set up by Electricite de France (E.D.F.) to provide the required tailor-made training. Today, recent advantages in computing capacities and software engineering along with the completion of Research and Development Training Division programs in the reactor safety (R+D) field (CATHARE, BETHSY..) give E.D.F. the opportunity to conceive and operate new tools for training which are described in the paper: RTGV-SEPIA: a simulator devoted to self training in SGTR field, thanks to a powerful expert system. SIPA: a 'generator of simulators' aiming at control and engineering studies and training, provided with a software able to give in real time a relevant description of complex topologies with diphasic flow patterns (up to a 12'' break in the primary coolant system of a reactor). (orig./DG)

  2. PUSPATI Triga Reactor - First year in operation

    International Nuclear Information System (INIS)

    First year operation of RTP reactor was mostly devoted to making in house training, setting up and testing the facilities in preparation for more routine operations. Generally the operations are categorized into 4 main purposes; experiment of research, teaching and training, demonstration, and testing and maintenance. These four purposes are elaborated in detail. Additions and modifications were performed in order to improve the safety of reactor operation. (A.J.)

  3. Integrated training support system for PWR operator training simulator

    International Nuclear Information System (INIS)

    The importance of operator training using operator training simulator has been recognized intensively. Since 1986, we have been developing and providing many PWR simulators in Japan. We also have developed some training support systems connected with the simulator and the integrated training support system to improve training effect and to reduce instructor's workload. This paper describes the concept and the effect of the integrated training support system and of the following sub-systems. We have PES (Performance Enhancement System) that evaluates training performance automatically by analyzing many plant parameters and operation data. It can reduce the deviation of training performance evaluation between instructors. PEL (Parameter and Event data Logging system), that is the subset of PES, has some data-logging functions. And we also have TPES (Team Performance Enhancement System) that is used aiming to improve trainees' ability for communication between operators. Trainee can have conversation with virtual trainees that TPES plays automatically. After that, TPES automatically display some advice to be improved. RVD (Reactor coolant system Visual Display) displays the distributed hydraulic-thermal condition of the reactor coolant system in real-time graphically. It can make trainees understand the inside plant condition in more detail. These sub-systems have been used in a training center and have contributed the improvement of operator training and have gained in popularity. (author)

  4. Development of technologies for nuclear reactors of small and medium sized

    International Nuclear Information System (INIS)

    This meeting include: countries presentations, themes and objectives of the training course, reactor types, design, EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, ATMEA 1, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR, React ores enfriados con metales liquidos, Hs, Prism,Terra Power, Hyper ion, appliance's no electric as de energia, Generation IV Reactors,VHTR, Gas Fast Reactor, Sodium Fast Reactor, Molten salt Reactor, Lfr, Water Cooled Reactor, Technology Assessment Process, Fukushima accident.

  5. Utilisation of British University Research Reactors.

    Science.gov (United States)

    Duncton, P. J.; And Others

    British experience relating to the employment of university research reactors and subcritical assemblies in the education of nuclear scientists and technologists, in the training of reactor operators and for fundamental pure and applied research in this field is reviewed. The facilities available in a number of British universities and the uses…

  6. Language training: French training

    CERN Multimedia

    Françoise Benz

    2005-01-01

    General and Professional French Courses The next session will take place from 30 January to 07 April 2006. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz : Tel. 73127. Writing Professional Documents in French The next session will take place from 30 January to 07 April 2006. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz : Tel. 73127. FORMATION EN LANGUES LANGUAGE TRAINING Françoise Benz 73127 language.training@cern.ch

  7. Language Training: French Training

    CERN Multimedia

    2004-01-01

    LANGUAGE TRAINING Françoise Benz tel. 73127 language.training@cern.ch General and Professional French Courses The next session will take place from 26 April to 02 July 2004. These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127. Writing Professional Documents in French The next session will take place from 26 April to 02 July 2004. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127.

  8. A computer based, interactive, multimedia training module for self-paced learning

    International Nuclear Information System (INIS)

    Disadvantages of traditional safeguards inspectors training methods are outlined. A computer based, interactive, multimedia, self-paced training programme, called the CANDU power reactor training module (CPRTM) is described. 1 ref., 2 figs

  9. Reactor building

    International Nuclear Information System (INIS)

    The whole reactor building is accommodated in a shaft and is sealed level with the earth's surface by a building ceiling, which provides protection against penetration due to external effects. The building ceiling is supported on walls of the reactor building, which line the shaft and transfer the vertical components of forces to the foundations. The thickness of the walls is designed to withstand horizontal pressure waves in the floor. The building ceiling has an opening above the reactor, which must be closed by cover plates. Operating equipment for the reactor can be situated above the building ceiling. (orig./HP)

  10. Heterogeneous reactors

    International Nuclear Information System (INIS)

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

  11. WWER-1000 reactor simulator. Workshop material

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series 12, 'Reactor Simulator Development' (2001). Course material for workshops using a pressurized water reactor (PWR) Simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication: Training Course Series No. 22 'Pressurized Water Reactor Simulator' (2003) and Training Course Series No. 23 'Boiling Water Reactor Simulator' (2003). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation. N. V. Tikhonov and S. B. Vygovsky of the Moscow Engineering and Physics Institute prepared this report for the IAEA

  12. Boiling water reactor simulator. Workshop material

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and workshop material and sponsors workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 simulator from the Moscow Engineering and Physics Institute, Russian Federation is presented in the IAEA publication: Training Course Series No. 21 'WWER-1000 Reactor Simulator' (2002). Course material for workshops using a pressurized water reactor (PWR) simulator developed by Cassiopeia Technologies Incorporated, Canada, is presented in the IAEA publication: Training Course Series No. 22 'Pressurized Water Reactor Simulator' (2003). This report consists of course material for workshops using a boiling water reactor (BWR) simulator. Cassiopeia Technologies Incorporated, developed the simulator and prepared this report for the IAEA

  13. Language Training: French Training

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. LANGUAGE TRAINING Françoise Benz tel. 73127 language.training@cern.ch General and Professional French Courses The next session will take place from 26 April to 02 July 2004. These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127. Writing Professional Documents in French The next session will take place from 26 April to 02 July 2004. This course is designed for people with a good level...

  14. Language Training: French Training

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. LANGUAGE TRAINING Françoise Benz tel. 73127 language.training@cern.ch General and Professional French Courses The next session will take place from 26 April to 02 July 2004. These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127. Writing Professional Documents in French The next session will take place from 26 April to 02 July 2004. This course is designed for people with a good level of s...

  15. IAEA activities in nuclear reactor simulation for educational purposes

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. Currently, the IAEA has simulation programs available for distribution that simulate the behaviour of BWR, PWR and HWR reactor types, only two available that simulate all three reactors. (authors)

  16. The intestinal parasite Pomphorhynchus laevis (Acanthocephala) from barbel as a bioindicator for metal pollution in the Danube River near Budapest, Hungary

    International Nuclear Information System (INIS)

    Concentrations of As, Al, Ag, Ba, Bi, Cd, Co, Cr, Cu, Fe, Ga, Mg, Mn, Ni, Pb, Sb, Sn, Sr, Tl, V and Zn were analyzed by inductively coupled mass spectrometry (ICP-MS) in the intestinal helminth Pomphorhynchus laevis and its host Barbus barbus. The fish were caught in the Danube river downstream of the city of Budapest (Hungary). Ten out of twenty one elements analyzed were found at higher concentrations in the acanthocephalan than in different tissues (muscle, intestine, liver and kidney) of barbel. Considering the fish tissues, most of the elements were present at highest concentrations in liver, followed by kidney, intestine and muscle. Spearman correlation analyses indicate that there is competition for metals between the parasites and the host. The negative relationships between parasite number and metal levels in organs of the barbel support this hypothesis. The bioconcentration factors for Ag, As, Ba, Bi, Cu, Ga, Mn, Pb, Sr, Tl, and Zn showed that the parasites concentrated metals to a higher degree than the fish tissues. They accumulated the metals As, Cd, Cu, Fe, Ni, Pb, Sr and Zn even better than established bioindicators such as the mussel Dreissena polymorpha as revealed by data from the literature. The results presented here emphasize that acanthocephalans of fish are very useful as sentinels for metal pollution in aquatic ecosystems. Ratio of metal concentrations in the parasites and the host tissues provide additional information. Not including acanthocephalans in accumulation bioindication studies with fishes (as still customarily done) may lead to false results. - Acanthocephalans of fish may be useful as sentinels of metal pollution in aquatic systems

  17. The intestinal parasite Pomphorhynchus laevis (Acanthocephala) from barbel as a bioindicator for metal pollution in the Danube River near Budapest, Hungary

    Energy Technology Data Exchange (ETDEWEB)

    Thielen, F.; Zimmermann, S.; Baska, F.; Taraschewski, H.; Sures, B

    2004-06-01

    Concentrations of As, Al, Ag, Ba, Bi, Cd, Co, Cr, Cu, Fe, Ga, Mg, Mn, Ni, Pb, Sb, Sn, Sr, Tl, V and Zn were analyzed by inductively coupled mass spectrometry (ICP-MS) in the intestinal helminth Pomphorhynchus laevis and its host Barbus barbus. The fish were caught in the Danube river downstream of the city of Budapest (Hungary). Ten out of twenty one elements analyzed were found at higher concentrations in the acanthocephalan than in different tissues (muscle, intestine, liver and kidney) of barbel. Considering the fish tissues, most of the elements were present at highest concentrations in liver, followed by kidney, intestine and muscle. Spearman correlation analyses indicate that there is competition for metals between the parasites and the host. The negative relationships between parasite number and metal levels in organs of the barbel support this hypothesis. The bioconcentration factors for Ag, As, Ba, Bi, Cu, Ga, Mn, Pb, Sr, Tl, and Zn showed that the parasites concentrated metals to a higher degree than the fish tissues. They accumulated the metals As, Cd, Cu, Fe, Ni, Pb, Sr and Zn even better than established bioindicators such as the mussel Dreissena polymorpha as revealed by data from the literature. The results presented here emphasize that acanthocephalans of fish are very useful as sentinels for metal pollution in aquatic ecosystems. Ratio of metal concentrations in the parasites and the host tissues provide additional information. Not including acanthocephalans in accumulation bioindication studies with fishes (as still customarily done) may lead to false results. - Acanthocephalans of fish may be useful as sentinels of metal pollution in aquatic systems.

  18. Reactor operations at SAFARI-1

    International Nuclear Information System (INIS)

    A vigorous commercial programme of isotope production and other radiation services has been followed by the SAFARI-1 research reactor over the past ten years - superimposed on the original purpose of the reactor to provide a basic tool for nuclear research, development and education to the country at an institutional level. A combination of the binding nature of the resulting contractual obligations and tighter regulatory control has demanded an equally vigorous programme of upgrading, replacement and renovation of many systems in order to improve the safety and reliability of the reactor. Not least among these changes is the more effective training and deployment of operations personnel that has been necessitated as the operational demands on the reactor evolved from five days per week to twenty four hours per day, seven days per week, with more than 300 days per year at full power. This paper briefly sketches the operational history of SAFARI-1 and then focuses on the training and structuring currently in place to meet the operational needs. There is a detailed step-by-step look at the operator?s career plan and pre-defined milestones. Shift work, especially the shift cycle, has a negative influence on the operator's career path development, especially due to his unavailability for training. Methods utilised to minimise this influence are presented. The increase of responsibilities regarding the operation of the reactor, ancillaries and experimental facilities as the operator progresses with his career are discussed. (author)

  19. Training and education

    International Nuclear Information System (INIS)

    The paper deals essentially with problems of training and education in a developing country that has made the decision to launch a nuclear programme. All teaching has a double aim: to transfer knowledge, and to form responsible individuals. In a state each pedagogic action has a relatively definite aim. In the nuclear field this aim can be construction of a research or power reactor (or participation in its construction) or the operation of these reactors. There are no well-defined borders between these various aims and for each aim the overall needs should be defined. The personnel needs can be expressed by a series of desired outlines for each function. The starting point should be the students or the active population (in particular those who have already been employed in a conventional power station). The means to proceed from the original state to the desired situation will be sought. The number of people trained should be at least twice that needed (accidents, holidays, resignations). For technicians and engineers a good basic knowledge of fundamental science is necessary in every case. It should be kept in mind that the government ought to be informed beforehand on the alternate choices by advisers trained in specialized courses, i.e. IAEA courses for decision-makers. First, the local educational means shall be used. For very specialized functions the supplier of the power station will provide an adequate training. Specialized teaching centres abroad will provide additional knowledge to those who already have the required fundamental education. Theoretical learning can be useful only after a long period of training in a reactor department in the country itself or abroad. This training should tend to actual integration in a team. A certain amount of information should be given preferably in situ, in particular in the field of health physics, as each member of the staff must be fully aware of its importance. (author)

  20. IAEA safeguards at research reactors

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency applies safeguards to almost 150 facilities classified as research reactors. From a safeguards point of view, these facilities present a spectrum of features that must be addressed both from the nuclear material and from the operational viewpoints. The nuclear fuel used by these reactors varies from high enriched uranium (NEU), up to 93 U-235, to natural uranium and the thermal power output from over 100 megawatt to less than ten watts. Research reactors are also used for a wide variety of purposes, including materials testing, radiosotope production, training and nuclear physics studies. The effort spent by the Agency in safeguarding these reactors is dependant upon the thermal power of the reactor and on the quantity and type of nuclear material present. On some research reactors, the Agency devotes more inspection effort than on a large power reactor. On others, very little effort is reguired. Safeguards that are applied are done so according to Agency State agreements and consist of a combiination of nuclear material accounting and containment and surveillance. In this paper, the safeguards activities performed by the State and by the Agency will be reviewed for a large (≤50MWt) and for a small (≥ 1 MWt) reactor according to the most common type agreement. (author)

  1. BOILER-SUPERHEATED REACTOR

    Science.gov (United States)

    Heckman, T.P.

    1961-05-01

    A nuclear power reactor of the type in which a liquid moderator-coolant is transformed by nuclear heating into a vapor that may be used to drive a turbo- generator is described. The core of this reactor comprises a plurality of freely suspended tubular fuel elements, called fuel element trains, within which nonboiling pressurized liquid moderator-coolant is preheated and sprayed through orifices in the walls of the trains against the outer walls thereof to be converted into vapor. Passage of the vapor ovcr other unwetted portions of the outside of the fuel elements causes the steam to be superheated. The moderatorcoolant within the fuel elements remains in the liqUid state, and that between the fuel elements remains substantiaily in the vapor state. A unique liquid neutron-absorber control system is used. Advantages expected from the reactor design include reduced fuel element failure, increased stability of operation, direct response to power demand, and circulation of a minimum amount of liquid moderatorcoolant. (A.G.W.)

  2. Training Accreditation Program

    International Nuclear Information System (INIS)

    In recent years increased attention has been given to all aspects of the operation of Department of Energy (DOE) nuclear facilities. Contributing to this is the finding that the severity of the accident at Three Mile Island in 1979 has, in large part, been attributed to personnel training deficiencies. Initially the impact of the Three Mile Island accident and the lessons learned were directed at DOE Category A reactor facilities. This resulted in numerous initiatives to upgrade the safety of operations and to improve the training of personnel responsible for operating these facilities

  3. Training report of the FBR cycle training facility in 2001

    International Nuclear Information System (INIS)

    The FBR Cycle Training Facility has been operating since Sep. 2000 for staff of FBR 'Monju' and ATR 'Fugen' and fireman of the local community, etc. In 2000, 6 courses of the sodium handling training were held 22 times and also eight courses of the maintenance training were 11 times and total participants were 305. In order to grade up the trainigs for providing restarting of 'Monju', the corresponding training course on sodium piping leakage accident was added as newly sodium handling training course and partial contents of some courses were devised based on some comments by the training discussing committee organized in our center. In 2001, seven sodium handling training courses were carried out 25 times and eight maintenance courses were conducted 11 times and total participated number was 220, i.e. 157 trainees for sodium training courses and 63 trainees for maintenance training courses. Additionally, since a new licensed sodium training course for sodium handling workers included head of worker will be introduced from next year owing to the fire accident of maintenance building in the experimental fast reactor 'JOYO' occurred Oct in 2001, which was coursed by sodium spontaneous combustion due to inefficient handling on tidy up of the sodium handling working, training curriculum, training text and questions for examination are provided as for preparing its course cooperated with Oarai Engineering Center. (author)

  4. Plasma reactor

    OpenAIRE

    Molina Mansilla, Ricardo; Erra Serrabasa, Pilar; Bertrán Serra, Enric

    2008-01-01

    [EN] A plasma reactor that can operate in a wide pressure range, from vacuum and low pressures to atmospheric pressure and higher pressures. The plasma reactor is also able to regulate other important settings and can be used for processing a wide range of different samples, such as relatively large samples or samples with rough surfaces.

  5. Reactor physics

    International Nuclear Information System (INIS)

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

  6. Training safely, Training safety

    Directory of Open Access Journals (Sweden)

    Jianjun Wu

    2014-09-01

    Full Text Available It is the basic requirement of maritime safety education to guarantee the safety of teaching operation while training the crew's occupation safety capability. Marine Training Center of Shanghai Maritime University has undertaken the practical teaching of "marine survival" for many years and come up with the whole safety procedures of training. Based on the requirements of SOLAS convention and regulations of STCW over crew training, this paper introduces the safety allocation, utilization and maintenance of teaching equipments. Through the investigation of the safety situation of students' practical operation, the safety teaching method named "four in one" has been put forward, which includes the pre-teaching safety precaution, the whole monitor during the teaching process, the post-teaching summary evaluation, and the reset and standby of teaching facilities. Finally, during the learning and training of "marine survival", crews and students are called on to place priority on personal safety rather than acquisition of knowledge and skills. Only in this way can they be capable of self-protection and protection of others in the career of seafaring.

  7. Physics and kinetics of TRIGA reactor

    International Nuclear Information System (INIS)

    This training module is written as an introduction to reactor physics for reactor operators. It assumes the reader has a basic, fundamental knowledge of physics, materials and mathematics. The objective is to provide enough reactor theory knowledge to safely operate a typical research reactor. At this level, it does not necessarily provide enough information to evaluate the safety aspects of experiment or non-standard operation reviews. The material provides a survey of basic reactor physics and kinetics of TRIGA type reactors. Subjects such as the multiplication factor, reactivity, temperature coefficients, poisoning, delayed neutrons and criticality are discussed in such a manner that even someone not familiar with reactor physics and kinetics can easily follow. A minimum of equations are used and several tables and graphs illustrate the text. (author)

  8. Updating reactor control: mini-computers

    International Nuclear Information System (INIS)

    An aging reactor control console and a limited operating budget have impeded many research projects in the TRIGA reactor facility at the University of Utah. The, University's present console is Circa 1959 vintage and repairs to the console are frequently required which present many electronic problems to a staff with little electronic training. As an alternative to a single function control console we are developing a TRIGA control system based upon a mini-computer. The system hardware has been specified and the hardware is currently being acquired. The software will be programmed by the staff to customize the system to the reactor's physical systems and technical specifications. The software will be designed to monitor and control all reactor functions, control a pneumatic sample transfer system, acquire and analyze neutron activation data, provide reactor facility security surveillance, provide reactor documentation including online logging of physical parameters, and record regularly scheduled reactor calibrations and laboratory accounting procedures. The problem of hardware rewiring and changing technical specifications and changing safety system characteristics can be easily handled in the software. Our TRIGA reactor also functions as a major educational resource using available reactor based software. The computer control system can be employed to provide on-line training in reactor physics and kinetics. (author)

  9. Advances in reactor physics education: Visualization of reactor parameters

    International Nuclear Information System (INIS)

    Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)

  10. Evaluating Training

    Institute of Scientific and Technical Information of China (English)

    Zhang Huanhai; Zhang Lei's

    2008-01-01

    @@ Clause 6.2.2: Competence, Awareness and Training in ISO9001:2000 standard sets the training requirements for organizations. Problems with evaluating the outcomes of training arise during examination and verification.

  11. RA nuclear reactor - revitalisation, renewal and applications

    International Nuclear Information System (INIS)

    This book is meant to give professional support in solving the problem of RA reactor, its revitalisation and renewal, as a special help for decision makers. Facts in favor of restarting RA reactor are prevailing. This report is made of six parts. First part includes an overview of basic properties of research reactors in the world and a discussion concerning their future development. RA reactor parameters are analyzed both with low enriched and highly enriched fuel and it has been concluded that the aim of RA reactor renewal should be to obtaining as high as possible thermal neutron flux density. The second part deals with possible applications of RA reactor in fundamental and applied research programs, commercial applications and its role in education and training programs. The third part discusses application of RA reactor as a source of thermal neutrons for fundamental and applied sciences, especially in the condensed matter physics and development of new materials. The role of RA reactor in development of radiation protection systems is emphasised in part four. Some possible commercial applications of Ra reactor are described in part five: isotope production, and their different applications. Part six deals with education and training of staff, with special accent on scientific international cooperation. Basic conclusions of this material meant for decision makers are: restarting RA reactor is the most reasonable and activities related to its revitalisation and renewal should be continued; this program should include solving the problems of education and training of the staff for reactor operation, improvement and different applications; renewal program should include renewal of the experimental devices as a condition of reactor efficient application immediately after its startup

  12. Status of the reactor TRIP in HANARO

    International Nuclear Information System (INIS)

    Unexpected reactor trip in HANARO since the first criticality in February, 1995 was investigated. The total numbers of the reactor trip events were 136 and it was 10.4 cases on average each year. During the early stage of the HANARO operation from 1995 to 1997, unexpected reactor trips were occurred frequently. 67% of the total unexpected reactor trips were occurred in that period, which were 91 cases. That duration was for a power ascension test as one of the reactor performance tests. The unexpected reactor trips were mainly caused by system problems and operators' error. Some cases were caused by electric power failure. The most frequent system problem was originated from fluctuation of the signal of the neutron power measuring system. To prevent the reactor trips by this phenomenon, the circuit of the reactor protection system was changed. Operators' error were occurred by mismatching of the neutron and thermal power, which was caused when the deviation of the neutron and thermal power is larger than 3 MW while the reactor power increases. To reduce reactor operators' error, operational procedure was revised and the operators have been trained with the revised one. That has on effect on reducing unexpected reactor trips dramatically. Reactor trips have been occurred by the class-IV power failure or a few problems of system error but never by operators' error since 2000. (author)

  13. Xi'an pulsed reactor

    International Nuclear Information System (INIS)

    Xi'an Pulsed Reactor (XAPR) Designed and constructed all by China is first research pulsed reactor with versatile applications. It is characterized with inherent safety, versatile application, structure simplicity and convenience for operation. It can be operated not only at stead-state but also at pulse mode as well as square wave mode. The rated power to the reactor under steady-state operation is 2 MW and the reactor is operated under pulsing state, its maximum peak power is about 4200 MW. XAPR is also equipped with many kinds of the experimental and irradiation facilities. The applications are radio-isotopes production, neutron activity analysis, neutron radiograph, monocrystalline silicon irradiation, material irradiation test, nuclear physics, neutron physics and nuclear chemistry studies, teaching and training. The XAPR has went into test operation and application for nearly two years that has shown its advantage and extensiveness

  14. Compact Reactor

    International Nuclear Information System (INIS)

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date

  15. Operational experience with research reactors in Trombay

    International Nuclear Information System (INIS)

    The research reactors Apsara and Cirus, located at the Bhabha Atomic Research Centre, Trombay, Bombay have recently completed 30 years and 26 years of successful operation respectively. Both reactors have been used extensively for research, isotope production and manpower training. Several measures have been taken towards achieving this long successful operation. These include preventive maintenance, meticulous control on chemistry of fluid systems, proper physics management, surveillance measures and modifications to system and equipment based on experience. Extensive training of O and M personnel has been another important factor contributing towards this. Major topics detailed in this paper include detection of one leaky reactor vessel lattice tube in Cirus and its successful plugging, replacement of old control system hardware consisting of vacuum tubes with modern solid state devices in both the reactors, installation of S.S.liner in Apsara reactor pool and certain modifications towards improving fuel performance in Cirus. Some aspects of preventive maintenance are also dealt with. (author)

  16. Language Training: English Training

    CERN Multimedia

    Françoise Benz

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. General and Professional English Courses The next session will take place from 04 October 2004 to 11 February 2005 (3 weeks break at Christmas). These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mr. Liptow, tel. 72957. Oral Expression This course is intended for people with a good knowledge of English who want to practise and maintain their speaking skills while extending their vocabulary. There will be approximately 8 participants in...

  17. Operation training for renovated JMTR

    International Nuclear Information System (INIS)

    JMTR once stopped its operation in August 2006. The subsequent refurbishment and the repair of the building block affected by the 2011 off the Pacific Coast of Tohoku Earthquake on March 11, 2011 have been completed, and it is preparing for the reoperation. As for the refurbishment of reactor facilities, taking into account the operation for further 20 years after the restart, and from the viewpoints of judging standards (aging deterioration of equipment, importance of safety function, and maintenance experience) for the safety ensuring against aging, the following facilities were replaced: (1) core of nuclear reactor body, (2) measurement and control system facilities, (3) reactor cooling system facilities, (4) emergency evacuation equipment of disposal facilities of gaseous waste, and (5) control facilities. In this remodeling, the operation methods for measurement and control system facilities (process instrumentation, nuclear instrumentation) have been changed. Therefore, regarding the reactor operation after the remodeling, examination was made on the methods to safely and reliably conduct important operations such as the criticality proximity of reactor and output increase, while monitoring the process instrumentation in the same way as before. Based on these examination results, the authors designed an operation manual, and have been performing operation training. This paper takes up the methods for reactor operation procedures that were changed by the refurbishment of the reactor, and summarizes the consideration points on the preparation of the operating manual, problems confirmed by practicing the operation training, and measures against those problems. (A.O.)

  18. Report of the reactor Operators Service - Annex F

    International Nuclear Information System (INIS)

    RA reactor operators service is organized in two groups: permanent staff (chief operator, chief shift operators and operators) and changeable group which is formed according to the particular operation needs for working in shifts. main activities during 1993 were concerned with repair and maintenance of the reactor systems and training of the reactor personnel. During the reporting period there have been no accidents nor incidents that could affect the reactor personnel

  19. Operation and Utilizations of Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    The reconstructed Dalat nuclear research reactor was commissioned in March 1984 and up to September 1988 more than 6200 hours of operation at nominal power have been recorded. The major utilizations of the reactor include radioisotope production, activation analysis, nuclear data research and training. A brief review of the utilization of the reactor is presented. Some aspects of reactor safety are also discussed. (author) 2 figs.; 5 refs.; 1 tab

  20. Impact of proposed research reactor standards on reactor operation

    International Nuclear Information System (INIS)

    A Standards Committee on Operation of Research Reactors, (ANS-15), sponsored by the American Nuclear Society, was organized in June 1971. Its purpose is to develop, prepare, and maintain standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training. Of the 15 original members, six were directly associated with operating TRIGA facilities. This committee developed a standard for the Development of Technical Specifications for Research Reactors (ANS-15.1), the revised draft of which was submitted to ANSI for review in May of 1973. The Committee then identified 10 other critical areas for standards development. Nine of these, along with ANS-15.1, are of direct interest to TRIGA owners and operators. The Committee was divided into subcommittees to work on these areas. These nine areas involve proposed standards for research reactors concerning: 1. Records and Reports (ANS-15.3) 2. Selection and Training of Personnel (ANS-15.4) 3. Effluent Monitoring (ANS-15.5) 4. Review of Experiments (ANS-15.6) 5. Siting (ANS-15.7) 6. Quality Assurance Program Guidance and Requirements (ANS-15.8) 7. Restrictions on Radioactive Effluents (ANS-15.9) 8. Decommissioning (ANS-15.10) 9. Radiological Control and Safety (ANS-15.11). The present status of each of these standards will be presented, along with their potential impact on TRIGA reactor operation. (author)

  1. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  2. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  3. Nuclear reactors

    International Nuclear Information System (INIS)

    This draft chart contains graphical symbols from which the type of (nuclear) reactor can be seen. They will serve as illustrations for graphical sketches. Important features of the individual reactor types are marked out graphically. The user can combine these symbols to characterize a specific reactor type. The basic graphical symbol is a square with a point in the centre. Functional groups can be depicted for closer specification. If two functional groups are not clearly separated, this is symbolized by a dotted line or a channel. Supply and discharge lines for coolant, moderator and fuel are specified in accordance with DIN 2481 and can be further specified by additional symbols if necessary. The examples in the paper show several different reactor types. (orig./AK)

  4. Neutrons for research and training

    International Nuclear Information System (INIS)

    The 250 kW TRIGA Mark-II reactor operates since March 1962 at the Atomic Institute in 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 co-ordinated and supervised by about 80 staff members with the aim of a master- or PhD degree in one of the above mentioned areas. During the past 15 years about 600 students graduated through the Atomic Institute. The paper focuses on the results in neutron- and solid state physics and the co-operation between the low power TRIGA reactor with high flux neutron sources in Europe. The use of the TRIGA reactor at the Atomic Institute in Vienna as an irradiation facility in neutron activation analysis has a remarkable history. Present research work includes the recent determination of the precise half-life of 182Hf and the participation in an archaeological long-term research programme. The TRIGA reactor operated by the Atomic Institute is now the only nuclear facility in Austria. Although Austria follows a dedicated anti-nuclear policy, the Atomic Institute enjoys a relatively undisturbed nuclear freedom in its nuclear activities. This allows us to use the research reactor not only for academic training but also for international training courses especially in nuclear technology. The presentation will outline typical training programmes and summarizes the experience with international training courses. (authors)

  5. Multifunctional reactors

    OpenAIRE

    Westerterp, K.R.

    1992-01-01

    Multifunctional reactors are single pieces of equipment in which, besides the reaction, other functions are carried out simultaneously. The other functions can be a heat, mass or momentum transfer operation and even another reaction. Multifunctional reactors are not new, but they have received much emphasis in research in the last decade. A survey is given of modern developments and the first successful applications on a large scale. It is explained why their application in many instances is ...

  6. NUCLEAR REACTOR

    Science.gov (United States)

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    In order to reduce neutron embrittlement of the pressue vessel of an LWR, blanked off elements are fitted at the edge of the reactor core, with the same dimensions as the fuel elements. They are parallel to each other, and to the edge of the reactor taking the place of fuel rods, and are plates of neutron-absorbing material (stainless steel, boron steel, borated Al). (HP)

  8. Breeder reactors

    International Nuclear Information System (INIS)

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

  9. Training organisation

    International Nuclear Information System (INIS)

    Slovenske elektrarne considers a specific training and education of experienced experts to be a key issue. The company gradually undergoes quite demanding change in the field of education and training of the nuclear power plants staff. We have an ambitious vision - to create one of the best training organisations in Europe by the means of systematic approach to the training. (author)

  10. Education and vocational training

    International Nuclear Information System (INIS)

    The Faculty Institute in Applied Health Physics started in the summer of 1974 in response to the nation's needs for persons trained at the bachelor's level in health physics technology. Surveys indicate that between 3300 and 6000 new trained technologists will be needed by 1985. They will be required for nuclear power reactors, fuel-cycle operations, nuclear medicine, regulatory activities, and as replacements for currently employed workers. The Faculty Institute program provides support for contacting college officials to make them aware of these forecasts and interest them in instituting undergraduate health physics course work at their institutions. In addition, the program provides support for ten faculty participants from different universities to spend ten weeks during the summer in the Health Physics Division. These participants have access to the staff and the diverse research and field facilities of the Division. They also utilize the facilities of the Special Training Division at ORAU

  11. Condition of research reactor spent nuclear fuel in wet storage

    International Nuclear Information System (INIS)

    is high, the pool liner should be replaced, as was done at the WWR-SM reactor in Budapest in 1986. (author)

  12. Condition of research reactor spent nuclear fuels in wet storage

    International Nuclear Information System (INIS)

    FSP failure is high, the pool liner should be replaced, as was done at the WWR-SM reactor in Budapest in 1986

  13. Language Training - French Training

    CERN Multimedia

    HR Department

    2008-01-01

    General and Professional French Courses The next session will take place from 26 January to 3rd April 2009. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Writing Professional Documents in French The next session will take place from 26 January to 3rd April 2009. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Nathalie Dumeaux Tel. 78144 mailto:nathalie.dumeaux@cern.ch

  14. Language Training - French Training

    CERN Multimedia

    HR Department

    2009-01-01

    General and Professional French Courses The next session will take place from 26 January to 3rd April 2009. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Writing Professional Documents in French The next session will take place from 26 January to 3rd April 2009. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Nathalie Dumeaux Tel. 78144 mailto:nathalie.dumeaux@cern.ch

  15. Language training: French training

    CERN Multimedia

    2008-01-01

    General and professional french coursesThe next session will take place from 14 April to 27 June 2008. These courses are open to all persons working on the CERN site and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs Nathalie Dumeaux: Tel. 78144. Writing Professional Documents in French The next session will take place from 14 April to 27 June 2008. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs Nathalie Dumeaux: Tel. 78144.

  16. U.S. Domestic Reactor Conversion Programs

    International Nuclear Information System (INIS)

    The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

  17. Sharing of Rensselaer Polytechnic Institute Reactor Critical Facility (RCF)

    International Nuclear Information System (INIS)

    The RPI Reactor Critical Facility (RCF) operated successfully over the period fall 1994 - fall 1995. During this period, the RCF was used for Critical Reactor Laboratory spring 1995 (12 students); Reactor Operations Training fall 1994 (3 students); Reactor Operations Training spring 1995 (3 students); and Reactor Operations Training fall 1995 (3 students). Thirty-two Instrumentation and Measurement students used the RCF for one class for hands-on experiments with nuclear instruments. In addition, a total of nine credits of PhD thesis work were carried out at the RCF. This document constitutes the 1995 Report of the Rensselaer Polytechnic Institute's Reactor Critical Facility (RCF) to the USNRC, to the USDOE, and to RPI management

  18. Development of BWR operator training simulator and training support systems

    International Nuclear Information System (INIS)

    This paper describes a BWR operator training simulator and training support systems that have been developed with the aim of providing support throughout operator training. The operator training simulator is needed in order to improve simulation fidelity and enlarge simulation scope. A 3-dimensional reactor core model has been developed in order to improve the understanding of operators respecting neutronics through realistic training. A severe accident model has been developed for training operators and technical support center teams respecting plant operation and for studying various phenomena. The severe accident is simulated by connecting the physical parameters continuously from the conventional model to the severe accident model. An emergency procedure guideline support system is adopted in order to improve efficiency of operation training for emergencies, since the emergency operation procedures are complicated and based on multiple parameter conditions. The operator training support system is also introduced so as to help training instructors to evaluate the operation and to give instructions to operators to improve operational accuracy. An instructor's burden is eased by automatically evaluating the operation errors based on signals of a simulator. The effects of these systems are evaluated and found to be effective in an actual training center and in engineers' examinations. (author)

  19. Research reactors - an overview

    Energy Technology Data Exchange (ETDEWEB)

    West, C.D.

    1997-03-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

  20. Small angle neutron scattering study of radiation damage in reactor vessel materials

    International Nuclear Information System (INIS)

    Complete text of publication follows. Nuclear radiation provides important changes in the microstructure of metallic components of nuclear power plant and research reactors, influencing their mechanical properties. The investigation of this problem has primary interest for the safety and life-time of such nuclear installations. For the characterisation of this kind of nanostructures small angle neutron scattering technique is a very useful tool. Experiments were carried out on samples of irradiated reactor vessel material and welded components of VVER-440 type reactors on the SANS instrument at the Budapest Research Reactor. In these measurements irradiated as well as non-irradiated samples were compared and magnetic field was applied for viewing the magnetic structure effects of the materials. A clear modification of the structure due to irradiation was obtained. The data sets were processed with the ITP92 code, the inverse Fourier transform programme of O. Glatter [1]. Our microstructural observations fit well to the hardness test results. [2]. (author) [1] O. Glatter (1997) J. Appl. Cryst. 10, 415-421.; [2] M. Grosse, J. Boehmert, H.W. Viehrig (1994) Journal of Nuclear Materials 211, 177-180

  1. Aspects of radiological protection for low power research reactor in the experimental teaching and learning

    International Nuclear Information System (INIS)

    It describes how learning by students and professional staff of nuclear facilities in the Czech Republic and Slovak Republic in the field of radiation protection within the reactor experiments at the school VR-1 Sparrow (CTU Faculty of Nuclear Sciences), where radiation protection is a natural essential part of every teaching and activities at the reactor. Reactor is presented and learning module 'Radiation Protection and Dosimetry' created for IAEA training courses - EERRI Group Fellowship Training Programme on Research Reactors (2010, 2011), which are intended for future training of personnel research reactors in IAEA Member States interested in the development of nuclear energy, but with little experience in this area. (authors)

  2. Reactor utilization

    International Nuclear Information System (INIS)

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel

  3. Reactor Neutrinos

    CERN Document Server

    Lasserre, T; Lasserre, Thierry; Sobel, Henry W.

    2005-01-01

    We review the status and the results of reactor neutrino experiments, that toe the cutting edge of neutrino research. Short baseline experiments have provided the measurement of the reactor neutrino spectrum, and are still searching for important phenomena such as the neutrino magnetic moment. They could open the door to the measurement of coherent neutrino scattering in a near future. Middle and long baseline oscillation experiments at Chooz and KamLAND have played a relevant role in neutrino oscillation physics in the last years. It is now widely accepted that a new middle baseline disappearance reactor neutrino experiment with multiple detectors could provide a clean measurement of the last undetermined neutrino mixing angle theta13. We conclude by opening on possible use of neutrinos for Society: NonProliferation of Nuclear materials and Geophysics.

  4. Interdisciplinary utilization of the Penn State Breazeale Reactor

    International Nuclear Information System (INIS)

    The Penn State Breazeale Reactor (PSBR) is in its 35th yr of service to researchers from all disciplines desiring reactor experiments. Most users come from Penn State University but researchers from numerous other universities have been assisted under the U.S. Department of Energy Reactor Sharing Program and other forms of support. Industries have also been served through research and training programs. The PSBR has been used extensively for many traditional applications, such as neutron activation analysis (NAA), gamma irradiations, isotope supply, utility reactor operator training, and academic instruction. In recent applications, innovative techniques have broadened capabilities in three specific areas: activatable tracers, neutron radiography, and radiation damage to semiconductors

  5. IAEA activities in nuclear reactor simulation for educational purposes

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. Currently, the IAEA has simulation programs available for distribution that simulate the behaviour of BWR, PWR and HWR reactor types. (authors)

  6. Arkansas Tech University reactor project

    International Nuclear Information System (INIS)

    The purpose of this paper is to describe the nuclear reactor project at Arkansas Tech University (ATU). The reactor will be a part of the Center for Energy Studies (CES) located on the ATU campus in Russellville, Arkansas. It will be used for education, training, and research. The Arkansas Tech University TRIGA Reactor (ATUTR) is a TRIGA Mark I that will be operated in two basic modes: steady state and pulsing. The maximum power level for steady-state operation is 250 kW(thermal), and the maximum step reactivity insertion will be 2.0$. The inherent safety of this reactor comes from the large negative temperature coefficient of the uranium-zirconium-hydride fuel-moderator elements. Principal design parameters for the reactor are summarized. The application for reactor construction and operating license was submitted to the US Nuclear Regulatory Commission in November 1989. The review process is continuing. ATU plans to continue to work with local industry and the public to provide a wide variety of services related to nuclear science and engineering

  7. Nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor has a large prompt negative temperature coefficient of reactivity. A reactor core assembly of a plurality of fluid-tight fuel elements is located within a water-filled tank. Each fuel element contains a solid homogeneous mixture of 50-79 w/o zirconium hydride, 20-50 w/o uranium and 0.5-1.5 W erbium. The uranium is not more than 20 percent enriched, and the ratio of hydrogen atoms to zirconium atoms is between 1.5:1 and 7:1. The core has a long lifetime, E.G., at least about 1200 days

  8. Nuclear reactors

    International Nuclear Information System (INIS)

    In a liquid cooled nuclear reactor, the combination is described for a single-walled vessel containing liquid coolant in which the reactor core is submerged, and a containment structure, primarily of material for shielding against radioactivity, surrounding at least the liquid-containing part of the vessel with clearance therebetween and having that surface thereof which faces the vessel make compatible with the liquid, thereby providing a leak jacket for the vessel. The structure is preferably a metal-lined concrete vault, and cooling means are provided for protecting the concrete against reaching a temperature at which damage would occur. (U.S.)

  9. Computer based training for the nuclear industry

    International Nuclear Information System (INIS)

    The PLATO Computer Based Education system is used to provide training for high technology subjects i.e., Nuclear Reactor Operations, Airline Pilots. This paper presents an overview of the history and development of the PLATO system, the current features and capabilities and discusses future trends. It also presents a review of its applicability to the training needs of the Nuclear Industry. The advantages for this are, one to one training capability, simulation capability and computer managed instruction. (author)

  10. Language Training: English Training

    CERN Document Server

    Françoise Benz

    2004-01-01

    La prochaine session se déroulera du 04 octobre 2004 au 11 février 2005 (interruption de 3 semaines à Noël). Ces cours s'adressent à toute personne travaillant au CERN ainsi qu'à leur conjoint. Pour vous inscrire et voir tout le détail des cours proposés, consultez nos pages Web : http://cern.ch/Training Vous pouvez aussi contacter M. Liptow, tél. 72957. General and Professional English Courses The next session will take place from 04 October 2004 to 11 February 2005 (3 weeks break at Christmas). These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mr. Liptow, tel. 72957. Oral Expression This course is intended for people with a good knowledge of English who want to practise and maintain their speaking skills while extending their vocabulary. There will be approximately 8 participants ...

  11. Language Training: English Training

    CERN Multimedia

    Françoise Benz

    2004-01-01

    General and Professional English Courses The next session will take place from 04 October 2004 to 11 February 2005 (3 weeks break at Christmas). These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mr. Liptow, tel. 72957. Oral Expression This course is intended for people with a good knowledge of English who want to practise and maintain their speaking skills while extending their vocabulary. There will be approximately 8 participants in a class. Speaking activities will include discussions, meeting simulations, role-plays etc. depending on the needs of the students. Duration: 20 hours (2 hours a week) Price: 440 CHF (for 8 students) For further information, please contact Mr. Liptow, tel. 72957. Date and timetable will be fixed when there are sufficient participants enrolled. FORMATION EN LANGUES LANGUAGE TRAINING Françoise Benz 73127 langua...

  12. Language Training: English Training

    CERN Document Server

    Françoise Benz

    2004-01-01

    General and Professional English Courses The next session will take place from 04 October 2004 to 11 February 2005 (3 weeks break at Christmas). These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mr. Liptow, tel. 72957. Oral Expression This course is intended for people with a good knowledge of English who want to practise and maintain their speaking skills while extending their vocabulary. There will be approximately 8 participants in a class. Speaking activities will include discussions, meeting simulations, role-plays etc. depending on the needs of the students. Duration: 20 hours (2 hours a week) Price: 440 CHF (for 8 students) For further information, please contact Mr. Liptow, tel. 72957. Date and timetable will be fixed when there are sufficient participants enrolled. FORMATION EN LANGUES LANGUAGE TRAINING Françoise Benz 73127 languag...

  13. Language Training - French Training

    CERN Multimedia

    2007-01-01

    General and Professional French Courses The next session will take place from 29 January to 30 March 2007. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz : Tel. 73127. Writing Professional Documents in French The next session will take place from 29 January to 30 March 2007. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registration, please consult our Web pages:   http://cern.ch/Training or contact Mrs. Benz : Tel. 73127. Writing Professional Documents in English The next session will take place from January to June 2007 (break at Easter). This course is designed for people with a good level of spoken English. Duration: 30 hours Price: 660 CHF (for 8 students) Timetable will be fixed after discussion with the students. For registratio...

  14. PREFACE: The first 21 years of reverse Monte Carlo modelling—a workshop held in Budapest, Hungary (1-3 October 2009) The first 21 years of reverse Monte Carlo modelling—a workshop held in Budapest, Hungary (1-3 October 2009)

    Science.gov (United States)

    Keen, David A.; Pusztai, László

    2010-10-01

    This special issue contains a collection of papers reflecting the content of the fourth workshop on reverse Monte Carlo (RMC) methods, held in a hotel on hills overlooking Budapest at the start of October 2009. At this meeting around sixty participants gathered to hear talks and discuss a broad range of science based on the RMC technique in very convivial surroundings. Reverse Monte Carlo modelling is a method for producing three-dimensional disordered structural models in quantitative agreement with experimental data. The method was developed in the late 1980s and has since achieved wide acceptance within the scientific community [1], producing on average over seventy papers and 1000 citations per year in the last five years. It is particularly suitable for studies of the structures of liquid and amorphous materials, as well as the structural analysis of disordered crystalline systems. The principal experimental data that are modelled are obtained from total x-ray or neutron scattering experiments, using the reciprocal space structure factor and/or the real space pair distribution function (PDF). Additional data might be included from extended x-ray absorption fine structure (EXAFS) spectroscopy, Bragg peak intensities or indeed any measured data that can be calculated from a three-dimensional atomistic model. It is this use of total scattering (diffuse and Bragg), rather than just the Bragg peak intensities more commonly used for crystalline structure analysis, which enables RMC modelling to probe the often important deviations from the average crystal structure, to probe the structures of poorly crystalline materials, and the local structures of non-crystalline materials where only diffuse scattering is observed. This flexibility across various condensed matter structure-types has made the RMC method very attractive in a wide range of disciplines, as borne out in the contents of this special issue. It is, however, important to point out that since the method is

  15. Safety analysis for non-power reactors

    International Nuclear Information System (INIS)

    Non-power reactors have been operating in Canada since 1945, with NRU (National Research Universal, 1957) being the oldest operating non-power reactor. Presently, there are five generic 'types' of non-power reactors: NRU, ZED-2, SLOWPOKE, MNR and MAPLE, the latter undergoing commissioning as the MDS Medical Isotope Reactor. These reactors range in thermal power from 200 Watts to more than 100 MW. Other non-power reactors are likely to be built for new applications and to replace older reactors. The uniqueness of each reactor, the wide range of power levels and the evolution of safety philosophy over time have lead to non-uniform practices for safety analysis. This non-uniformity may be a problem for the preparation by the licensee and review by the regulator of the safety analysis report required for licensing of the reactor facility. Clearly, there is no universally applicable practice, while at the same time, expectations for safety analyses have evolved in order to demonstrate higher levels of overall safety. This paper examines a new 'graded approach' to preparing the safety analysis report for reactors of diverse features but with a common standard of safety. It discusses necessary content, methods and the training and qualification of the safety analyst. (author)

  16. Refurbishment and activities at Tajoura reactor

    Energy Technology Data Exchange (ETDEWEB)

    Abutweirat, F.; Abusta, M. [Renewable Energies and Water Desalination Research Centre, Basic and Applied Research Dept., Tajoura (Libyan Arab Jamahiriya)

    2007-07-01

    The Tajoura Research Reactor was built in the late seventies by the former Soviet Union for Libya. The Tajoura Research Reactor is a 10 MW light water cooled and moderated, beryllium reflected, pool type reactor. Its design facilitates the production of radioisotopes and the performance of material testing experiments. The reactor is provided with a critical assembly that is an exact mockup of the reactor core to test and study neutron transport in the different core configurations. The utilization of the reactor suffered the most due to the hardship which had confronted Libya during the years 1985 - 2000. During that time the utilization was limited to the use of the reactor as an educational tool for university students, for training reactor operators and for capacity building in the field of radiation safety, radiation chemistry, isotope production and neutron activation analysis. Both the Critical Assembly and the reactor were recently converted from the high enrichment uranium (HEU) fuel (Type IRT-2M) to low enrichment (LEU) fuel (Type IRT-4M). The refurbishment of the control and safety systems of the reactor and the critical assembly is due to start in a near future.

  17. Refurbishment and activities at Tajoura reactor

    International Nuclear Information System (INIS)

    The Tajoura Research Reactor was built in the late seventies by the former Soviet Union for Libya. The Tajoura Research Reactor is a 10 MW light water cooled and moderated, beryllium reflected, pool type reactor. Its design facilitates the production of radioisotopes and the performance of material testing experiments. The reactor is provided with a critical assembly that is an exact mockup of the reactor core to test and study neutron transport in the different core configurations. The utilization of the reactor suffered the most due to the hardship which had confronted Libya during the years 1985 - 2000. During that time the utilization was limited to the use of the reactor as an educational tool for university students, for training reactor operators and for capacity building in the field of radiation safety, radiation chemistry, isotope production and neutron activation analysis. Both the Critical Assembly and the reactor were recently converted from the high enrichment uranium (HEU) fuel (Type IRT-2M) to low enrichment (LEU) fuel (Type IRT-4M). The refurbishment of the control and safety systems of the reactor and the critical assembly is due to start in a near future

  18. The development of NPP operational safety training courses

    International Nuclear Information System (INIS)

    The objective of the project is to develop a training course text for the betterment of reactor operation and assurance of its safety in general by providing training materials of the advanced compact nuclear simulator which will become operation in September 1988. Main scope and contents of the project are as follows: - compilation of basic data related to simulator operation and maintenance as well as the comparative analysis with respect to simulator materials in foreign countries - method of training by simulator - review the training status by simulator in foreign countries - development of training course in the field of reactor safety It is expected that the results will be reflected to the actual training and retraining of the reactor operating crew so as to improve and update their capabilities in training fashion. (Author)

  19. Need of reactor dosimetry preservation

    International Nuclear Information System (INIS)

    Full text: Today's nuclear renaissance in national and European aspect, expressed in building of new NPPs, as well as the development of Gen. IV nuclear reactors, meets new challenges of accuracy of the reactor analysis methods used for reliable operation and nuclear safety assessment. The nuclear safety requirements and philosophy have changed by the development of new nuclear systems and this imposes special research and development activity. Reactor Dosimetry (RD) which is applied for determination of neutron field parameters and neutron flux responses in different regions of the reactor system plays an important role in determining of consecutive effects from the irradiation. That is, for determination of radiation exposure on reactor system elements as reactor vessel, internals, shielding; dose determination for material damage study; determination of radiation field parameters for conditioning of irradiation; dose determination for medicine and industry application; induced activity determination for decommissioning purposes. The management of nuclear knowledge has emerged as a growing challenge in recent years. The need to preserve and transfer nuclear knowledge is compounded by recent trends such as ageing of the nuclear workforce, declining student numbers in nuclear related fields, and the threat of losing accumulated nuclear knowledge. Reinforcement of science and technology potential of many EU institutes is needed so to be able to support the nuclear operators and nuclear regulator in safety assessment as well as to strengthen the utilization of the research reactor for medicine and industry purposes. The ways to preserve and develop the RD knowledge could be asked in the good practice of the near past within the European Working Group for Reactor Dosimetry (EWGRD), members of which are research organizations of the countries in Europe operating VVER, PWR and BWR type reactors. Joint workshops and training, common intercomparisons will maintain the RD

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    In an improved reactor core for a high conversion BWR reactor, Pu-breeding type BWR type reactor, Pu-breeding type BWR type rector, FEBR type reactor, etc., two types of fuel assemblies are loaded such that fuel assemblies using a channel box of a smaller irradiation deformation ratio are loaded in a high conversion region, while other fuel assemblies are loaded in a burner region. This enables to suppress the irradiation deformation within an allowable limit in the high conversion region where the fast neutron flux is high and the load weight from the inside of the channel box due to the pressure loss is large. At the same time, the irradiation deformation can be restricted within an allowable limit without deteriorating the neutron economy in the burner region in which fast neutron flux is low and the load weight from the inside of the channel box is small since a channel box with smaller neutron absorption cross section or reduced wall thickness is charged. As a result, it is possible to prevent structural deformations such as swelling of the channel box, bending of the entire assemblies, bending of fuel rods, etc. (K.M.)

  1. Planning and management support for NPP personnel SAT-based training programmes

    International Nuclear Information System (INIS)

    Planning and management support for NPP personnel SAT-based training programmes is described for the following job positions: reactor operator; turbine operator; reactor maintenance worker; pump maintenance worker; chemistry foreman; health physics foreman; electric maintenance worker

  2. Training Visions

    Science.gov (United States)

    Training, 2011

    2011-01-01

    In this article, "Training" asks the 2011 winners to give their predictions for what training--either in general or specifically at their companies--will look like in the next five to 10 years. Perhaps their "training visions" will spark some ideas in one's organization--or at least help prepare for what might be coming in the next decade or so.

  3. Nuclear reactors and fuel cycle

    International Nuclear Information System (INIS)

    The Center for Nuclear Engineering has shown expertise in the field of nuclear and energy systems ad correlated areas. Due to the experience obtained over decades in research and technological development at Brazilian Nuclear Program personnel has been trained and started to actively participate in the design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in the production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. The Nuclear Fuel Center is responsible for the production of the nuclear fuel necessary for the continuous operation of the IEA-R1 research reactor. Development of new fuel technologies is also a permanent concern

  4. Utilization of Slovenian TRIGA Mark II reactor

    International Nuclear Information System (INIS)

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

  5. TRR-1/M1 reactor pool refurbishment

    International Nuclear Information System (INIS)

    The pool refurbishment of the TRR-1/M1 is intended to maintain the pool and irradiation facilities in the operable condition prior to the next decade before making decision whether the reactor will be shutdown and decommissioning or used for other purposes. What ever reason the TRR-1/M1 will serve as a training tool for scientists or engineers, and isotopes production or other analytical works for a period of time until the new research reactor will be established. (orig.)

  6. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

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

  7. TAP 2, Performance-Based Training Manual

    Energy Technology Data Exchange (ETDEWEB)

    1991-07-01

    Training programs at DOE nuclear facilities should provide well- trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two comparison manuals provide additional information to assist contractors in their efforts to accredit training programs.

  8. TAP 3, Training Program Support Manual

    Energy Technology Data Exchange (ETDEWEB)

    1991-07-01

    Training programs at DOE facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs.

  9. TAP 3, Training Program Support Manual

    International Nuclear Information System (INIS)

    Training programs at DOE facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs

  10. TAP 2, Performance-Based Training Manual

    International Nuclear Information System (INIS)

    Training programs at DOE nuclear facilities should provide well- trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two comparison manuals provide additional information to assist contractors in their efforts to accredit training programs

  11. Perspectives on reactor safety. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  12. Perspectives on reactor safety. Revision 1

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  13. Training report of the FBR cycle training facility for Monju Restarting

    International Nuclear Information System (INIS)

    The FBR Cycle Training Facility consists of the sodium handling training facility and the maintenance training facility has been used since September in 2000. At the sodium handling training facility, the trainees are able to study widely sodium handling technologies, which are inherent technologies of fast reactors, such as sodium fire extinguishing, chemical and physical properties of sodium, sodium loop operating skill, counter training for sodium piping leakage, etc.. On the other hand, maintenance training courses not only for 'MONJU' related inherent maintenance technologies but also for general maintenance skills are conducted at the maintenance training facility. So far, 77 eight-unit sodium training courses and 39 nine-unit maintenance training courses have been performed in preparation of Monju restarting and the total number of trainees is 888. (author)

  14. Un nuovo periodico di studi italiani «Nuova Corvina», Rivista di Italianistica dell'Istituto Italiano di Cultura per l'Ungheria, num. 1, Budapest 1993, 144 pagine.

    Directory of Open Access Journals (Sweden)

    Pavao Tekavčić

    2015-09-01

    Full Text Available Siamo lieti di poter presentare ai lettori di «Linguistica» la nuova rivista dilin­ gua, letteratura e cultura italiana, «Nuova Corvina», apparsa nella vicina Ungheria.Inapertura del primo numero si legge che ilperiodico «intende promuovere gli studidiitalianistica,favorendol'interscambioelacircolazionedelpensierotragliitalianistiungheresi ed i colleghi operanti negli altri paesi» [p. 2].  Prevista per adesso come anuale,con la speranza che possa diventare per lo meno semestrale [p.7],«Nuova Corvina» èl' organo del citato Ente culturale, ed il comitato di redazione è costituito da quat­tro eminenti studiosi ungheresi: Lajos Antal (Istituto Superiore di Magistero di Szom­bathely,Gyula Herczeg (Università di Pécs, József Pál(Università di Szeged e Győző Szabó (Università di Budapest.

  15. Laboratory instrumentation modernization at the WPI Nuclear Reactor Facility

    International Nuclear Information System (INIS)

    With partial funding from the Department of Energy (DOE) University Reactor Instrumentation Program several laboratory instruments utilized by students and researchers at the WPI Nuclear Reactor Facility have been upgraded or replaced. Designed and built by General Electric in 1959, the open pool nuclear training reactor at WPI was one of the first such facilities in the nation located on a university campus. Devoted to undergraduate use, the reactor and its related facilities have been since used to train two generations of nuclear engineers and scientists for the nuclear industry. The low power output of the reactor and an ergonomic facility design make it an ideal tool for undergraduate nuclear engineering education and other training. The reactor, its control system, and the associate laboratory equipment are all located in the same room. Over the years, several important milestones have taken place at the WPI reactor. In 1969, the reactor power level was upgraded from 1 kW to 10 kW. The reactor's Nuclear Regulatory Commission operating license was renewed for 20 years in 1983. In 1988, under DOE Grant No. DE-FG07-86ER75271, the reactor was converted to low-enriched uranium fuel. In 1992, again with partial funding from DOE (Grant No. DE-FG02-90ER12982), the original control console was replaced

  16. Pressurized water reactor simulator. Workshop material. 2. ed

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development. And the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21, 2nd edition, 'WWER-1000 Reactor Simulator' (2005). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23, 2nd edition, 'Boiling Water Reactor Simulator' (2005). This report consists of course material for workshops using a pressurized water reactor simulator

  17. Development of an educational nuclear research reactor simulator

    International Nuclear Information System (INIS)

    This paper introduces the development of a research reactor educational simulator based on LabVIEW that allows the training of operators and studying different accident scenarios and the effects of operational parameters on the reactor behavior. Using this simulator, the trainee can test the interaction between the input parameters and the reactor activities. The LabVIEW acts as an engine implements the reactor mathematical models. In addition, it is used as a tool for implementing the animated graphical user interface. This simulator provides the training requirements for both of the reactor staff and the nuclear engineering students. Therefore, it uses dynamic animation to enhance learning and interest for a trainee on real system problems and provides better visual effects, improved communications, and higher interest levels. The benefits of conducting such projects are to develop the expertise in this field and save costs of both operators training and simulation courses.

  18. IAEA activities in nuclear reactor simulation for educational purposes

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. Two simulation programs are presented at this workshop: the Classroom-based Advanced Reactor Demonstrators package, and the Advanced Reactor Simulator. Both packages simulate the behaviour of BWR, PWR and HWR reactor types. For each package, the modeling approach and assumptions are broadly described, together with a general description of the operation of the computer programs. (author)

  19. Development of an educational nuclear research reactor simulator

    Energy Technology Data Exchange (ETDEWEB)

    Arafa, Amany Abdel Aziz; Saleh, Hassan Ibrahim [Atomic Energy Authority, Cairo (Egypt). Radiation Engineering Dept.; Ashoub, Nagieb [Atomic Energy Authority, Cairo (Egypt). Reactor Physics Dept.

    2014-12-15

    This paper introduces the development of a research reactor educational simulator based on LabVIEW that allows the training of operators and studying different accident scenarios and the effects of operational parameters on the reactor behavior. Using this simulator, the trainee can test the interaction between the input parameters and the reactor activities. The LabVIEW acts as an engine implements the reactor mathematical models. In addition, it is used as a tool for implementing the animated graphical user interface. This simulator provides the training requirements for both of the reactor staff and the nuclear engineering students. Therefore, it uses dynamic animation to enhance learning and interest for a trainee on real system problems and provides better visual effects, improved communications, and higher interest levels. The benefits of conducting such projects are to develop the expertise in this field and save costs of both operators training and simulation courses.

  20. The future role of research reactors

    International Nuclear Information System (INIS)

    The decline of neutron source capacity in the next decades urges for the planning and construction of new neutron sources for basic and applied research with neutrons. Modern safety precautions of research reactors make them competitive with other ways of neutron production using non-chain reactions for many applications. Research reactors consequently optimized offer a very broad range of possible applications in basic and applied research. Research reactors at universities also in the future have to play an important role in education and training in basic and applied nuclear science. (orig.)