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Bosevski, T.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] An initial core calculation procedure for the total power form factor required is presented. To get an initial core similar to the equilibrium one, with zero reactivity, depleted uranium has been used. Both homogeneous and heterogeneous methods have been applied and their agreement regarding the macroscopic distributions was found to be quite satisfactory (author)
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Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 11 p; Also available from the Institute of nuclear sciences Vinca; 9 figs, 1 tabs
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Zerdin, F.; Grabovsek, Z.; Klinc, T.; Solinc, H.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] Gold foils were placed at different positions in the TRIGA reactor core and in the experimental devices. Absolute values of the thermal neutron flux at these positions were obtained by coincidence method. Preliminary fast neutron spectrum was measured by threshold detector and by 'Li6 sandwich' detector. A short description of the applied method and obtained measurements results are included
[sl]
Na razlicitih mestih sredice in v nekaterih eksperimentalnih napravah reaktorja TRIGA so bile obsevane zlate folije. Absolutne vrednosti termicnega fluksa na teh mestih so bile dolocene s koincidencno metodo. Preliminarno je bil izmerjen spekter hitrih nevtronov s pragovnimi detektorji in z 'Li6 sandwich' polvodniskim spektrom. Na kratko so opisane metode in podani rezultati meritev (autor)Original Title
Meritve fluksa termicnih in hitrih nevtronov v reaktorju TRIGA
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Secondary Subject
Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 12 p; Also available from the Institute of nuclear sciences Vinca; 8 refs, 6 figs, 2 tabs
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BARYONS, ELEMENTARY PARTICLES, ENRICHED URANIUM REACTORS, FERMIONS, HADRONS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, ISOTOPES, LIGHT NUCLEI, LITHIUM ISOTOPES, MEASURING INSTRUMENTS, NEUTRON DETECTORS, NEUTRONS, NUCLEI, NUCLEONS, ODD-ODD NUCLEI, RADIATION DETECTORS, RADIATION FLUX, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, STABLE ISOTOPES, THERMAL REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Grabovsek, Z.; Bernot, N.; Klopcic, F.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] Following measurement were done during operation of the TRIGA mark II reactor: loading of the core with fuel elements and critical experiment; calibration of the control rods, measurement of the built-in reactivity, calibration of reactor power and verification of the instrumentation linearity. Before these measurement reactor was operating for 16 hours at full power of 250 kW. At the same time, gamma radiation doses were measured at different positions in the reactor biological shield. Applied methods are briefly describes, and the obtained results are given
[sl]
Med zagonom reaktorja TRIGA Mark II so bile izvrsene sledece meritve: polnjenje sredice z gorvnimi elementi in kriticni eksperiment, kalibracija kontrolnih palic, merjenje presezne reaktivnosti, kalibracija moci reaktorja in ugotovitev linearnosti instrumentacije. Poleg tega je pred prevzemom reaktor obratoval 16 ur na polni moci 250 kW. Istocasno so bile izmerjene doze zarkov gama in nevtronov na razlicitih mestih ob bioloskem scitu reaktorja. Na kratko so opisane uporabljene metode in podani rezultati meritev (author)Original Title
Meritve pri zagonu reaktorja TRIGA
Primary Subject
Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 15 p; Also available from the Institute of nuclear sciences Vinca; 13 figs, 2 tabs
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DOSIMETRY, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SHIELDS, SOLID HOMOGENEOUS REACTORS, THERMAL REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Vdovic, J.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] This paper defines the quantitative safety, description of the safety analysis, estimation of the safety and relation between safety and economics of reactor operation
Original Title
Matematicno obravnavanje varnosti reaktorskih sistemov
Primary Subject
Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 36 p; Also available from the Institute of nuclear sciences Vinca; 17 refs, 3 figs
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Bosevski, T.; Spiric, V.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] In this paper we modified the well known source jerk method (1) thus obtaining a method for experimental determination of negative reactivities of reactor systems by which, based on the basic idea of the source jerk method, a new experimental procedure and an exact analysis were developed. The analysis and numerical preparation allows direct application of the method to heavy water and graphite systems. Compared with the source jerk method the experimental procedure and the interpretation of results is faster, simpler and more exact (author)
Primary Subject
Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 13 p; Also available from the Institute of nuclear sciences Vinca; 4 refs, 3 figs, 9 tabs
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Mitrovic, S.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] This report is an attempt of statistical analysis of the failures occurred during RA reactor operation. A list of failures occurred on the RA equipment during 1965 is included. Failures were related to the following systems: dosimetry system (22%), safety and control system (7%), heavy water system (2%), technical water (4%), helium system (2%), measuring instruments (30%), transport, ventilation, power supply systems (32%). A review of safety shutdowns from 1962 to 1966 is included as well, as a comparison with three similar reactors. Although the number of events used for statistical analysis was not adequate, it has been concluded that RA reactor operation was stable and reliable
Original Title
Sigurnosna zaustavljanja i kvarovi opreme na reaktoru RA
Primary Subject
Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 19 p; Also available from the Institute of nuclear sciences Vinca; 6 refs, 5 figs, 8 tabs
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Miscellaneous
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ATMOSPHERES, CONTROLLED ATMOSPHERES, COOLING SYSTEMS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, EQUIPMENT, FLUIDS, GASES, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, INERT ATMOSPHERE, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTOR SHUTDOWN, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, SHUTDOWN, TANK TYPE REACTORS, THERMAL REACTORS
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AbstractAbstract
[en] Radiation impact on the nuclear power plant environment is a very important problem which has to be solved during design and construction. Damage that could be caused by release of radioactive material into the environment should be estimated and the magnitude of nuclear and radiation risk of the power plant should be evaluated. In general the accuracy of estimation is rather poor due to statistical fluctuations of the conditions which influence radioactivity expansion in the environment, especially in the air. Different uncertainties and unresolved problems influence the inaccuracy. Since any real risk should be extremely small compared to potential risk i.e. risk induced by nuclear power plant without any safety measures, even inaccurate estimations are very useful. Method for environmental radiation risk assessment is based on relatively simple models of radiation expansion in the environment and in the air. These models are theoretically solved but they are based on relatively limited number of experimental data. Assessment of the radiation effects on the population health and mortality is an important problem
[sl]
Radiacijska nevarnost za okolico nuklearne elektrarne je zelo vazen problem, ki ga je treba resiti ze pri projektiranju in gradnji. Treba je oceniti skodo, ki bi jo povzrocila v okolici neka dolocena sprostitev radioaktivnosti in na osnovi tega dimenzionirati ukrepe nuklearne in radiacijske varnosti same elektrarne. Natancnost ocenjevanja je v splosnem zelo slaba. Temu so v precejsnji meri krive statisticne fluktuacije pogojev, ki vplivajo na razsirjanje radioaktivnosti v okolici, ziasti po zraku. Na nenatancnost pa vplivajo tudi razne nejasnosti in se nereseni problemi. Ken pa mora biti dejanska nevarnost izredno majhna v primerjavi s potencialne nevarnostjo oziroma z nevannostjo, ki bi jo predstavjala nuklearna elektrarna, ce bi zanemarili vse varnostne ukrepe, so tudi taksne nenatancne ocene zelo koristne. Metode ocenjevanja radiacijske nevarnosti za okolico nuklearne elektrarne slonijo predvsem na razmeroma enostavnih modelih razsirjanja radioaktivnosti v okolici po zraku. Ti modeli so nekoliko teoreticno obdelani vendar slonijo predvsem na razmeroma omejenem stevilu eksperimentalnih podatkov. Vazen problem predstavlja tudi vrednotenje skode zaradi zdravstvenih posledic za prebivalstvo okolice in cloveskih zrtev (author)Original Title
Pregled problematike in metodologije ocenjivanja radijacijske nevarnosti za okolico nuklearne elektrane
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Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 17 p; Also available from the Institute of nuclear sciences Vinca; 11 refs
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AbstractAbstract
[en] This Volume 2 of the Proceedings of 2. Yugoslav symposium on reactor physics includes eight papers dealing with the following topics: method for measuring high anti reactivities of a reactor system; integration method for thermal reaction rate calculation; Determination of initial core configuration for BHWR-200 MWe; safety shutdowns and failures of the RA reactor equipment; determining the reactivity of absorption rods; measurements of thermal and fast neutron fluxes at the TRIGA reactor and other measurements during operation of the TRIGA reactor; mathematical modelling of the reactor safety; review of problems and methods for radiation risk assessment in the environment of a nuclear power plant
Original Title
2. Jugoslovenski simpozijum iz reaktorske fizike, Deo 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Primary Subject
Source
1966; 157 p; Also available from the Institute of nuclear sciences Vinca; 52 refs, 46 figs, 22 tabs
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Miscellaneous
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ABSTRACTS, BARYONS, ELEMENTARY PARTICLES, ENRICHED URANIUM REACTORS, FERMIONS, HADRONS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, NEUTRONS, NUCLEONS, RADIATION FLUX, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, SOLID HOMOGENEOUS REACTORS, TANK TYPE REACTORS, THERMAL REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Bosevski, T.; Fredin, B.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] An advanced multi-group cell calculations a lot of data information is very often necessary, and hence the data administration will be elaborate, and the spectrum calculation will be time consuming. We think it is possible to reduce the necessary data information by using an effective reaction rate integration method well suited for U- and Pu-absorptions (author)
Primary Subject
Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 14 p; Also available from the Institute of nuclear sciences Vinca; 5 figs, 5 tabs
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Jaksic, B.
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966
AbstractAbstract
[en] Calculation of the control rods reactivity could be done by either heterogeneous or supercell method. The method described in this paper is called 'homogeneous' due to the fact that the active region is homogenized, and the reactivity is calculated by superposition of solutions for uncontrolled reactor core and solution for each absorber. This is a simplified procedure compared to the heterogeneous method but the relations between absorbers are kept. This paper describes the problem of one-zone reactor and the related computer code and includes a proposal for solving the problem of two-zone reactor
Original Title
Odredjivanje reaktivnosti absorpcionih sipki
Primary Subject
Source
Institute of Nuclear Sciences 'Boris Kidric', Vinca, Belgrade (Yugoslavia); 157 p; 1966; 20 p; Also available from the Institute of nuclear sciences Vinca; 6 refs, 2 figs
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