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Sample records for elektrodinamicheskikh kharakteristik kanala

  1. Change of I-V characteristics of SiC diodes upon reactor irradiation; Modification des caracteristiques I-V de jonctions p-n au SiC du fait d'une irradiation dans un reacteur; Izmeneniya kharakteristik I-V vyrashchennogo v SiC perekhoda tipa p-n posle oblucheniya ego v reaktore; Modificaciones que sufren por irradiacion en un reactor las caracteristicas I-V de uniones p-n en SiC

    Energy Technology Data Exchange (ETDEWEB)

    Heerschap, M; De Coninck, R [Solid State Physics Dept., SCK-CEN, Mol (Belgium)

    1962-04-15

    distintas procedencias. Las uniones se obtuvieron en el horno de Lely. Midieron las caracteristicas directa e inversa durante la irradiacion, y despues de esta, hasta la temperatura de 150{sup o}C. Se estan realizando mediciones hasta 500{sup o}C. Han encontrado que uno de los tipos de diodo es resistente a los neutrones del BR-1 hasta un flujo integrado de 10{sup 15} neutrones/cm{sup 2}, mientras que el otro soporta hasta 10{sup 17} neutrones/cm{sup 2}. La memoria indica los cambios de las caracteristicas, asi como los resultados de algunos experimentos de recocido. (author) [Russian] V poiskakh poluprovodnikov, kotorye mogli by byt' ispol'zovany v reaktorakh s vysokoj plotnost'yu nejtronnogo potoka dlya izmereniya raspredeleniya potokov, my obluchali v bel'gijskom reaktore BR-1 perekhody tipa p-n v SiC. Byli oblucheny dva tipa diodov SiC razlichnogo proiskhozhdeniya. EHti perekhody vyrashchivayutsya v pechi Loli. Izmeneniya pryamoj i obratnoj kharakteristik byli izmereny posle i vo vremya oblucheniya vplot' do temperatury 150{sup o}C; v nastoyashchee vremya proizvodyatsya izmereniya vplot' do temperatury 500{sup o}C. Bylo ustanovleno, chto odin tip dioda vyderzhivaet nejtronnoe obluchenie reaktora BR-1 vplot' do integrirovannogo potoka 10{sup 15} nejtronov na kv. sm, togda kak drugoj tip vyderzhivaet obluchenie vplot' do potoka 10{sup 17} nejtronov na kv. sm. Dayutsya izmeneniya kharakteristik, a takzhe rezul'taty nekotorykh ehksperimentov otzhiga. (author)

  2. Influence of the temperature distribution on the reactivity of the reactor channel; Uticaj aksijalne raspodele temperature na reaktivnost kanala

    Energy Technology Data Exchange (ETDEWEB)

    Stojadinovic, A; Pop-Jordanov, J; Zivkovic, Z [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1964-07-01

    For calculating the reactivity in the reactor channel, it was estimated that there is a linear increase of the neutron temperature along the channel. The channel is divide into 5 regions. Reactivity of the channel was calculated by using the reactivity curves for each region. it has been compared to the reactivity values obtained for different mean temperature values. The calculations were done on the digital computer Zuse-Z-23.

  3. Spatial distribution of reactor radiation around the horizontal experimental hole of the RA Reactor at Vinca; Prostorna raspodela reaktorskog zracenja oko horizontalnog eksperimentalnog kanala reaktora RA u Vinci

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    Ninkovic, M; Paligoric, D; Vujisic, B [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1964-10-15

    A survey is given of the measurement of the spatial distribution of thermal and fast neutrons and gamma radiations inside and around the reactor radiation beam which is carried through the experimental channel outside the reactor biological shield thus being a potential danger for the personnel in the reactor hall. The results obtained are used to determine the optimal distribution of the shielding elements around the free radiation beam. The activation method was used to determine the distribution of slow and fast neutrons. The detectors were Au{sup 197} and In {sup 115} for slow, and the S{sup 32} (n,p) P{sup 32} reaction for fast neutrons. The relative distribution of slow and fast neutrons along the beam axis in the space outside the reactor, and evaluation of the absolute value of the flux at the place where the beam comes out from the biological shield are given (author)

  4. Experimental operation of the RA reactor with 4 fuel channels containing 80% enriched dispersion fuel - Operational Report; Radni izvestaj - Eksperimentalna kampanja reaktora RA sa 4 kanala sa 80% obogacenim disperzionim gorivom

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    Martinc, R; Milosevic, M; Cupac, S; Kozomara, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    Start of utilization of the new 80% enriched dispersion nuclear fuel is underway in the RA reactor core. Both economic and technical analyses were in favor of introducing the new fuel elements gradually into the RA reactor core. Thus overall theoretical and experimental analyses as well as other preparations are directed to transition regime based on gradual introducing of new fuel into the core, i.e. reactor core with two types of fuel. The objective of these analyses and preparation is establishment of conditions for safe reactor operation during transition period. The analyses and preparations are almost completed. The experimental data about fuel burnup during a time period of operation at nominal power i.e. daily decrease of excess reactivity is missing. This data is needed for planning the refueling (quantity of fresh fuel and frequency of refueling) during the transient period. This data can be obtained only by normal operation of the reactor during a period of time significantly longer than the period of attaining equilibrium poisoning, as time between two D{sub 2}O condensate overflows into the RA reactor core. Thus a ten day experimental campaign was planned to be done in December 1976. This report presents the most important results of safety analyses and preparation which show that, during this experimental period, the reactor operation is absolutely safe taking into account the most important parameters influencing reactor safety, as reactivity, thermal and temperature limits for fuel and the reactor, etc. Data to be obtained during this experimental campaign are significant because they would enable definition of future supply of fresh fuel during the transition period. [Serbo-Croat] Predstoji pocetak koriscenja novog 80% obogacenog uranskog disperzionog goriva u reaktoru RA. Ekonomske i tehnicke analize dale su prednost postupku postepenog uvodjenja novog goriva u reaktor RA. Prema tome, obimne teorijske i eksperimentalne analize i druge pripreme usmerene su na prelazni rezim na bazi parcijalnog uvodjenja novog goriva u reaktor, tj. na reaktorsko jezgro sa dve vrste goriva. Cilj ovih analiza i priprema jeste obezbedjivanje svih uslova za siguran rad reaktora RA u prelaznom rezimu. Ove analize i pripreme su uglavnom kompletirane. Medjutim, nedostaje jos eksperimentalni podatak o utrosku goriva za odredjeni rad reaktora na nominalnoj snazi tj. o dnevnom padu ugradjenog viska reaktivnosti. Ovaj podatak neophodan je kod planiranja izmena goriva (kolicine svezeg goriva i ucestanosti izmena) u prelaznom rezimu. Do ovog podatka moze se doci samo putem normalnog rada reaktora u toku vremena znatno duzeg od vremena u kome se uspostavlja ravnotezno zatrovanje, kao vremena izmedju dva prelivanja D{sub 2}O kondenzata u aktivnu zonu RA. U tom smislu je planirana desetodnevna eksperimentalna kampanja u decembru 1976. U ovom izvestaju izlozeni su oni najznacajniji rezultati sigurnosnih analiza i priprema koji ukazuju na potpunu sigurnost rada reaktora tokom ove eksperimentalne kampanje, sa aspekta postovanja ogranicenja najvaznijih parametara koji uticu na sigurnost reaktora, kao sto su reaktivnost, toplotna i temperaturska ogranicenja za gorivo i za reaktor, itd. Podaci koji budu dobijeni iz ove eksperimentalne kampanje su od znacaja jer ce se na osnovu njih konacno definisati dalji protok svezeg novog goriva, tokom prelaznog rezima (author)

  5. Tasks related to increase of RA reactor exploitation and experimental potential, 03. Crane for handling the vertical experimental channels of the RA reactor - design project; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 03. Kran za opsluzivanje vertikalnih eksperimentalnih kanala reaktora RA - izrada projekta

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    Within the work related to improvement of experimental potential of the RA reactor, this document describes the design project of the new crane for handling the vertical experimental channels of the RA reactor, engineering drawings of the crane main elements, mechanical part, design project of the electrical part of the crane and cost estimation.

  6. Tasks related to increase of RA reactor exploitation and experimental potential, 04. Device for transport of radioactive reactor channels and semi channels of the RA reactor, design project (I-III) Part II, Vol. II; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 04. Uredjaj za transport aktivnih tehnoloskih kanala I semikanala reaktora RA - izrada projekta (I-III), II Deo, Album II

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    This second volume includes calculations of the main components of the transporter, description of the mechanical part of the transporter and the engineering drawing of the device for transport of radioactive reactor channels and semi channels of the RA reactor.

  7. Avangardi kanalast sai moodne biodiislitehas / Nils Niitra

    Index Scriptorium Estoniae

    Niitra, Nils, 1975-

    2006-01-01

    Vennad Ergo ja Elvo Themas on endises Avangardi kolhoosi kanalas sisse seadnud biodiislitehase, mille turuks saavad esialgu Saksamaa ja Rootsi kütuse hulgimüüjad. Kaart: Biodiislitehas alustab märtsis

  8. Technical realization of the VISA-2 Project, contract: 2.01/ I phase, Volume No. I; Tehnicka realizacija projekta VISA-2, ugovor: 2.01/I faza, Album br. I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-12-15

    Cooperation between the Institutes in Vinca and Saclay has started by carrying out the task 'Technical realization of the VISA-2 project' which should enable: obtaining new experimental spaces in the RA reactor with high fast neutron flux for sample irradiation; obtaining experience in reactor continual operation for few months at nominal power of 6.5 MW and increase of RA reactor utilization; solving the problem of activated channels and samples transport, problems of working in hot cells; obtaining irradiated samples for examining radiation effects first in Saclay and later in Vinca. The project is divided in three phases. Phase one covers the reconstruction of the RA reactor fuel channels according to the VISA-2 project demands. The second phase includes the activities related to measuring devices for measuring the temperatures at the incoming and outgoing heavy water in 5 VISA-2 channels, as well as temperature of the samples (55 thermocouples) and testing the channels and capsules after their insertion in the reactor. The third phase includes activities are related to problems of transport of radioactive channels and VISA-2 capsules, problems of cutting as well as packing and transporting of irradiated samples from Vinca to Saclay. This volume includes all the relevant documents for completing the task including contracts, needed preliminary calculations as well as safety analysis. [Serbo-Croat] Saradnja izmedju Instituta u Vinci i Saclay-u zapoceta je realizacijom zadatka 'Tehnicka realizacije projekta VISA-2' koji treba da omoguci: dobijanje novih eksperimentalnih prostora u reaktoru RA sa visokom vrednoscu fluksa brzih neutrona za ozracivanje uzoraka; sticanje pogonskih iskustava u visemesecnom kontilualnom radu na nominalnoj snazi od 6,5 MW i povecanje stepena koriscenja reaktora RA; resenje pitanja transporta aktivnih kanala i uzoraka, problema rada u vrucim celijama; dobijanje ozracenih uzoraka za izucavanje, u prvo vreme u Saclay-u, a kasnije i u Vinci

  9. Applicability of the Electrodynamic Approximation in the Theory of Liquid-Metal, Induction MHD Converters; O primenimosti ehlektrodinamicheskogo priblizheniya v teorii zhidkometallicheskikh induktsionnykh mgd preobrazovatelej ehnergii

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    Lielpeter, Ja. Ja. [Institut Fiziki AN Latvijskoj SSSR Riga, SSSR (Latvia)

    1966-11-15

    The paper deals with the present status of theoretical work on this problem and describes the results of a number of new experiments designed, to clarify the theory of MHD phenomena. The possibilities of using the electrodynamic approximation are discussed. Induction MHD machines with constant channel cross-section in the working zone are considered. (author) [Russian] Daetsja harakteristika sostojanija teorii voprosa, opisyvajutsja rezul'taty nekotoryh novyh jeksperimentov, postavlennyh s cel'ju utochnenija teorii MGD javlenij i obsuzhdajutsja vozmozhnosti ispol'zovanija jelektrodinamicheskogo priblizhenija. Rassmatrivajutsja indukcionnye MGD mashiny s postojannym po dline secheniem kanala v rabochej zone. (author)

  10. Nuclear Reactor RA Safety Report, Vol. 12, Accidents during reactor operation; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 12, Akcidenti u dosadasnjem radu reaktora

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    This volume includes description and analysis of typical accidents occurred during operation of RA reactor in chronological order, as follows: contamination of primary coolant circuit; leakage of heavy water from the primary coolant loop; contamination of vertical experimental channel; air contamination in the reactor building and loss of circulation of the primary coolant; failures of the vacuum pump and spent fuel packaging device; rupture of the spent fuel element cladding; dethronement's of capsule for irradiation of fuel element; rupture of the vertical experimental channel and contamination of the surroundings; swelling of a fuel element; appearance of deposits on the surface of the fuel elements cladding. The last chapter describes similar accidents occurred on nuclear reactors in the world. [Serbo-Croat] Ova knjiga sadrzi hronoloski pregled i analizu karakteristika akcidenata u dosadasnjem radu reaktora RA: kontaminacija primarnog kola hladjenja; isticanje teske vode is primarnog kola hladjenje; kontaminacija eksperimentalnog vertikalnog kanala; kontaminacija vazduha u hali reaktora i prestanak cirkulacije primarnog hladioca; otkaz vakum pumpe i uredjaja za prepakivanje ozracenog goriva; proboj kosuljice ozracenog gorivnog elementa; dehermetizacija kapsule za ozracivanje nuklearnog goriva; proboj eksperimentalnog vertikalnog kanala i kontaminacija prostorija; bubrenje gorivnog elementa; pojava taloga na kosuljicama gorivnih elemenata. Poslednje poglavlje opisuje udese na koji su se dogodili na nuklearnim reaktorima u svetu.

  11. Program of critical experiment and measurements at the RA reactor; Program kriticnih eksperimenata i merenja na reaktoru RA

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    NONE

    1960-04-14

    Program described in this document describes in detail the following experiments: critical experiments with two reactor core lattices with 38 and 44 fuel channels, initial heavy water level being 1300 mm, criticality is achieved by adding heavy water; preliminary analysis of heavy water quality and verification of the fuel isotopic contents; experiment with the initial core which contains 56 fuel channels with maximum heavy water level according to the Russian proposal; measurement of neutron flux by Dy and In foils; measurement of reactivity excess dependent on the heavy water level and number of fuel rods; measurement of reactor period for determined reactivity change; measurement of moderator temperature coefficient; measurement of absolute flux. [Serbo-Croat] Program sadrzan u ovom dokumentu opisuje detaljno sledece eksperimente: kriticni eksperiment sa dve konfiguracije jezgra reaktora, sa 38 i 44 gorivna kanala, pocetni nivo teske vode je 1300 mm, kriticnost se dostize dodavanjem teske vode; prethodno izvrsenom analizom teske vode i proverom izotopskog sastava goriva; eksperiment sa pocetnom resetkom koja prema ruskom predlogu sadrzi 56 gorivnih kanala i maksimalnom visinom teske vode; merenje raspodele neutronskog fluksa folijama Dy i In; kalibracija regulacionih sipki; merenje viska reaktivnosti sa promenom visine nivoa teske vode i promenom broja sipki; merenje periode reaktora za odredjenu promenu reaktivnosti; merenje temperaturnog koeficijenta za vodu; merenje apsolutnog fluksa.

  12. Measurements at the RA Reactor related to the VISA-2 project - Part 2, Measurement of neutron flux in VISA-2 channels; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - II deo, Merenje fluksa neutrona u kanalima VISA - 2

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    This report describes the task concerned with measurements of neutron flux in four experimental channels, called VISA-2 channels. All the channels are made of aluminium tubes, one is sealed to prevent contact of foils with heavy water, and are placed in the regular reactor lattice next to the central experimental channel VK-5. Measuring results, i.e. absolute values of neutron flux and flux distribution are needed for realisation of the VISA-2 project. Measurements of neutron flux are done by activation method. Activation foils are placed in cylindrical aluminium tubes specially prepared for this purpose and placed in VISA-2 channels. Foils are irradiated simultaneously for 5 hours at reactor power of 150 kW. Neutron flux distribution is determined by measuring the relative activity of cobalt foils. [Serbo-Croat] Ovaj izvestaj opisuje merenja neutronskog fluksa u cetiri eksperimentalna kanala VISA-2. Svi VISA-2 kanali nacinjeni su od aluminijuma, jedan je hermeticki zatvoren da folije koje se ozacuju ne dodju ukontakt sa teskom vodom i svi su smesteni neposredno pored centralnog eksperimentalnog kanala VK-5. Rezultati merenja, odnosno apsolutne vrednosti neutronskog fluksa i reposdele fluksa potrebni su za realizaciju projekta VISA-2. Mrerenja neutronskog fluksa izvreseno je aktivacionom tehnikom. Aktivacione folije smestene su u prethodno napravljene aluminijumske cevcice. Folije su ozracivane istovremeno pri snazi od 150 kW pe casova. Raspodela neutronskog fluksa odredjena je merenjem relativne aktivnosti folija od kobalta.

  13. Marketing on social networks

    OpenAIRE

    Stanojević, Marija

    2011-01-01

    Marketing na društvenim mrežama je posljednjih godina sve popularniji i sve se više razvija, a u ovom radu su pojašnjeni osnovni pojmovi kao što su marketing, marketinški splet koji možemo smatrati temeljima marketinga te marketinške strategije, zatim su objašnjeni pojmovi interneta i društvenih mreža u smislu komunikacijskih kanala kojima možemo poslati marketinšku poruku ciljanoj skupini. Prikazani su načini oglašavanja preko najpopularnijih društvenih mreža. Provedeno je i istraživanje o s...

  14. Task 08/41, Low temperature loop at the RA reactor, Review IV - Maximum temperature values in the samples without forced cooling; Zadatak 08/41, Niskotemperaturna petlja u reaktoru 'RA', Pregled IV - Maksimalne temperature u uzorcima bez prinudnog hladjenja

    Energy Technology Data Exchange (ETDEWEB)

    Zaric, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    The quantity of heat generated in the sample was calculated in the Review III. In stationary regime the heat is transferred through the air layer between the sample and the wall of the channel to the heavy water of graphite. Certain value of maximum temperature t{sub 0} is achieved in the sample. The objective of this review is determination of this temperature. [Serbo-Croat] Kolicina toplote generisana u uzorku, izracunata u pregledu III, u ravnoteznom stanju odvodi se kroz vazdusni sloj izmedju uzorka i zida kanala na tesku vodu odnosno grafit, pri cemu se u uzorku dostize izvesna maksimalna temperatura t{sub 0}. Odredjivanje ove temperature je predmet ovog pregleda.

  15. Definition of task (Phase II) B, 'Leak testing'; Definicija zadatka (II faza) B, 'Ispitivanje hermeticnosti'

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    In order to ensure safe Ra reactor operation and fulfilling the conditions for performing irradiation experiments it was necessary to test and verify the leak tightness of the sample containers and thermocouples, as well as the irradiation capsule before it was placed in the VISA-2 channel. Leak testing of VISA-2 channel with capsules and thermocouples was done before and after it was built-in the reactor. [Serbo-Croat] U cilju bezbednosti i sigurnosti rada reaktora RA i ispunjavanja uslova ozracivanja izvrsena je provera hermeticnosti kenera sa uzorcima i termoparovima, kao i hermeticnost kapsule pre ugradjivanja kapsule u kanal VISA-2. Izvrseno je i ispitivanje hermeticnosti kanala VISA-2 sa kapsulama i termoparovima pre ugradjivanja u reaktor i posle montaze.

  16. Technical realisation of the VISA-II Project, Phase II, Chapter X, Vol. VI; Tehnicka realizacija projekta VISA-II, II faza, Glava X, Album VI

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    The second phase of the 'Project VISA-2 described in this chapter of Vol. VI includes the project specifications and technical drawings of the 'measuring system of VISA-2 for testing the VISA-2 channels outside and in the reactor'. In addition to the task objective, description of the measuring system, action plan, description of the work done it contains the definition of the task 'Leak testing' and instructions for the instrumentation personnel on duty. [Serbo-Croat] Druga faza zadatka {sup T}ehnicka realizacija projekta VISA-2' opisana u ovom poglavlju Albuma VI, sadrzi tehnicki opis i crteze 'Mernog sistema VISA-2 i ispitivanje kanala VISA-2 van reaktora i u reaktoru'. Pored definicije zadatka, opisa mernog sistema VISA-2, razrade zadatka, tekstualnog dela projekta i opisa izvedenih radova, ovo poglavlje obuhvata definiciju i razradu podzadatka 'Ispitivanje hermeticnosti' i dodatak sa instrukcijama za dezurne instrumentatore u vezi eksperimenta VISA-2.

  17. DINAMIKA PEMAHAMAN ULAMA TENTANG HADIS DAJJAL (Dari Interpretasi Tekstual Ke Interpretasi Kontekstual

    Directory of Open Access Journals (Sweden)

    Pipin Armita

    2017-12-01

    Full Text Available Artikel ini bermaksud menggambarkan figur Dajjal yang disebutkan di beberapa hadis dalam kutub al-sittah dan menjelaskan bagaimana interpretasi tekstual dan kontekstual tentang hadis-hadis yang berbicara tentang masa lalu. Dalam beberapa hadis, Dajjal itu digambarkan sebagai fitnah besar yang Allah datang pada akhir masa, tetapi dia juga merupakan simbol dari wahyu yang akan datang. Dengan demikian manusia mengetahui bagaimana ciri-ciri akhir zaman, dan mengetahui tanda-tanda kedatangannya adalah suatu hal yang penting. Pada artikel ini penulis akan menjelaskan dan melakukan pelacakan terhadap hadis yang membahas secara spesifik tentang figur Dajjal secara tematik dengan metode deskriptif-analitis; dengan melakukan pelacakan tentang tradisi, takhrij al-hadis, analisis sanad, analisis muru’ah, syarah hadis secara tekstual dan kontekstual sebagai objek dari analisis yang dilakukan oleh penulis. Berdasarkan analisa penulis ada beberapa periwayat dari jalur Bukhari, terdapat wahyu dari Allah yang mengatakan Dajjal adalah seseorang yang gemuk bertubuh kemerahan, rambut keriting, salah satu matanya buta dan matanya seperti buah anggur yang matang (tidak bercahaya. Pemahaman secara tekstual tentang figur Dajjal itu adalah sesuai dengan apa yang digambarkan oleh hadis. Secara kontekstual, para ulama memahami kharakteristik seperti mata yang disebut dalam hadis merupakan sebuah simbol/metafora untuk menjelaskan kontrol terhadap apa yang terjadi hari ini, dan sebagai sebuah konspirasi untuk menguasai dunia, dan sebagai sebuah yang terkait dengan budaya Barat dan Yahudi yang penuh tipu daya, pemimpin yang salah, dan pemikiran yang cenderung duniawi

  18. Possibilities for power reactor structural material and fuel testing in reactor RA; Mogucnosti reaktora RA za testiranje konstrukcionih materijala i goriva energetskih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Lazarevic, Dj; Stefanovic, D; Cupac, S; Pesic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-05-15

    Nuclear reactor RA at Vinca has been designed as a high flux general purpose research reactor. Among other it was intended to play a role of material testing reactor. A scope of activities of Material Laboratory and Reactor RA Department of Boris Kidric Institute is presented in this report. Reactor RA capacity for reactor structural material and fuel irradiation is also described. The increase of RA reactor irradiation capacity is based on the improvement of VISA type fuel channel for fast neutron irradiations, as well as on the general neutron flux increase, due to introduction of highly enriched uranium fuel into reactor core and the advanced in-core fuel management. The irradiation capacities described allow for the reactor material and fuel testing to the considerable extent. Istrazivacki reaktor RA u Vinci je projektovan kao visokofluksni istrazivacki reaktor opste namene. Pored ostalog, on je namenjen i za testiranje reaktorskih konstrukcionih materijala i goriva. U radu je dat pregled aktivnosti Laboratorije za materijale IBK i reaktora RA na tom podrucju, kao i opis povecanih mogucnosti reaktora RA za ozracivanje reaktorskih materijala i goriva u cilju njihovog testiranja. Povecanje mogucnosti reaktora RA zasniva se na usavrsavanju specijalnog gorivnog kanala tipa VISA (za ozracivanje materijala brzim neutronima), kao i na opstem povecanju neutronskog fluksa na osnovu uvodjenja i nacina koriscenja visokoobogacenog uranskog goriva u reaktoru RA. Opisane mogucnosti reaktora RA dozvoljavaju u znatnoj meri ispitivanje konstrukcionih materijala i goriva energetskih reaktora.

  19. Analysis of accident caused by temperature increase at the RA reactor in Vinca; Analiza udesa usled povisenja temperature na reaktoru RA u Vinci

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    Afgan, N; Kulundzic, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1964-06-15

    The objective of this work was to determine the maximum time interval without accident due to mechanical failures. The following accidents caused by mechanical failures are taken into account: loss of moderator flow, moderator leaking with or without circulation, and accidents caused by removal of fuel channels from the reactor vessel. Obtained numerical and experimental results are presented. Experimental device installed at the reactor was used for verification of calculation results. The analysis was done for the most damaging conditions and thus the obtained results represent the lowest boundary values. [Serbo-Croat] Rad je baziran na pronalazenju maksimalnih vremena pri kojima i pored mehanickih kvarova nece doci do udesa. Posmatrani su slucajevi: prestanak cirkulacije moderatora, curenje moderatora uz i bez postojece cirkulacije, kao i udesi pri vadjenju tehnoloskih kanala iz reaktorskog suda. Dobijeni su rezultati numerickom i eksperimentalnom metodom. Eksperimentalna aparatura je postavljena da bi se dobila potvrda numerickih rezultata. U radu se vodilo racuna da se uvek analiziraju najnepovoljniji slucajevi pa su zato i dobijeni rezultati donje granice resenja (author)

  20. Dosimetry and radiation shielding at the RA reactor, Annual report 1975, Annex 5; Prilog 5 - Dozimetrija i tehnicka zastita

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    In the working environment at the RA reactor, the level of gamma radiation is measured continuously by the built-in stationary system. According to the needs, measurement are done in the reactor hall every day. The level of gamma radiation is measured separately in typical points when the reactor is operated at nominal power and during intervals between two operating campaigns. The level of neutron radiation is measured according to the needs by means of a mobile spherical neutron detector. These measurements are done in the reactor hall around the horizontal experimental channels. Measured values of neutron radiation are three times lower than the relevant levels of gamma radiation. [Serbo-Croat] Na reaktoru RA vrsi se stalna kontrola nivoa gama zracenja po tehnoloskim i radnim prostorijama, pomocu ugradjenog stacionarnog sistema. Svakodnevno se vrse merenja u reaktorskoj hali, prema ukazanim potrebama. Posebno se mere nivoi gamma zracenja u karakteristicnim tackama pri radu reaktora na nominalnoj snazi i u pauzama izmedju dva kampanje. Merenje nivoa neutronskog zracenja vrsi se diskontinualno pomocu mobilnog sfernog neutronskog dozimetra. Merenja se obavljaju u hali oko horizontalnih eksperimentalnih kanala. Izmerene vrednosti su u proseku tri puta manje od odgovarajucih nivoa gama zracenja.

  1. Operation and maintenance of the RA nuclear reactor for 1977, Report Annex I; Rad i iskoriscenost reaktora RA u 1977. godini, izvestaj Prilog I

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1977-12-15

    RA reactor operation plan was fulfilled, meaning 28583 MWh. In addition to 183 days of operation at full power, during 1977 the reactor was operated for 14 days at lower power level according to the demand of users. The utilization level of rector irradiation capability (neutron flux and time of operation) was 14%. This annex includes detailed statistical data about reactor operation, utilization, power level, savings concerned with new 80% enriched fuel. All the 9 vertical experimental channels were used for irradiation in the reactor core. Digression from the action plan were caused by refueling and demand od the users. There have been 11 safety shutdowns, of which 6 caused by power cuts, 4 due to failure of the instruments, and 1 due to earthquake in March 1977. [Serbo-Croat] Planirani rad reaktora na nominalnoj snazi ostvaren je u iznosu od 28583 MWh. U toku 1977. godine reaktor je radio 14 dana na manjim snagama i u posebnom eksperimentalnom rezimu na zahtev korisnika. Iskoriscenost kapaciteta reaktora za ozracivanje uzoraka (na bazi neutronskog fluksa i vremena rada reaktora) bila je 41%. Ovaj izvestaj sadrzi detaljne statisticke podatke o radu i iskoriscenosti reaktora, podatke o ustedi goriva prelaskom na 80% obogaceno gorivo. Korisceno je svih 9 vertikalnih eksperimentalnih kanala u aktivnoj zoni. Uzroci odstupanja od plana rada osim zamene goriva bili su zahtevi korisnika. Bilo je 11 sigurnosnih zaustavljanja, 6 usled nestanka napona, 4 usled kvarova opreme i instrumentacije, i 1 put usled zemljotresa u martu.

  2. KONYA ANA TAHLİYE KANALINDA KLORLU BİLEŞİKLERİN BELİRLENMESİ

    Directory of Open Access Journals (Sweden)

    Mehmet Emin AYDIN

    2000-03-01

    Full Text Available Konya ana tahliye kanalı Konya ovasının drenaj sularını toplayarak tuz gölüne boşaltmaktadır. Konya ovasında Konya şehri atık sularının tabi bir drenaj noktası bulunmaması sebebiyle kent atıksuları da bu kanala deşarj edilmektedir. Kanal güzergahı boyunca bu drenaj suları ve atık sular sulama suyu olarak kullanılmaktadır. Bazı klorlu organik bileşikler toksik ve kanserojen oldukları bilinen bileşiklerdir. Bu çalışmada Konya atıksularının deşarj edildiği ana tahliye kanalından alınan saatlik, günlük ve aylık numuneler gaz kromotoğraf (GC ile analiz edilerek klorlu organik bileşik içerikleri araştırılmıştır.

  3. KARAKTERISTIK DAN PROFIL INULIN BEBERAPA JENIS UWI (Dioscorea spp. Characteristic and Inulin Profil of Wild Yam (Dioscorea spp.

    Directory of Open Access Journals (Sweden)

    Sri Winarti

    2012-05-01

    Full Text Available Wild yams (Dioscorea spp. grow well in Indonesia known as Uwi, is the kind of tubers that grow in the community,but they have not been used optimally. Publicity about the characteristics and types has been limited. The tubers contain inulin, but also there have been no publication related.The purpose of this study was to uncover the characteristics of wild yam and inulin profiles contained in the tubers.The yams were obtained from various regions in East Java, among others Pacet Mojokerto, Karang Ploso and Kawi Mountains in Malang, Nganjuk, and traditional markets in Surabaya.The tubers were characterized for shape and size of tubers, skin color and flesh tubers, average weight and texture of the tuber, moisture content, ash content and levels of inulin, texture and flavor. The data were analyzed using Analysis of Variance (ANOVA and further test Duncan’t Multiple Range Test (DMRT.Based on the characteristics of tubers, there were 10 types of wild yams, namely D1 (Dioscororea alata/ white yam, D2 (Dioscorea pinthaphylla/frog yam, D3 (Dioscorea hispida /Gadung, D4 (Dioscorea alata /purple yam with yellow skin, D5 (Dioscorea alata /purple yam, D6 (Dioscorea esculenta/gembili, D7 (Dioscorea alata/yellow yam, D8 (Dioscorea opposita/white yam with yellow skin, D9 (Dioscorea bulbifera/gembolo and D10 (Dioscorea rotundata/ white yam with brown skin. The highest levels of inulin obtained in Dioscororea esculenta (gembili ie 14.77 % (db. The water content rangedbetween 71.89- 85.07 % (wb, ash content 0.59- 1.83 % and texture between 0.012 to 0.055 (mm/g.dt. Organoleptic score was 2.75 to 4.55 texture and taste is from 3.20 to 5.00. ABSTRAK Uwi merupakan jenis umbi-umbian yang tumbuh di Indonesia, namun belum dimanfaatkan secara optimal dan belumbanyak publikasi mengenai kharakteristik dan jenis-jenisnya. Uwi mengandung inulin, namun belum banyak publikasi yang mengungkap kadar inulin pada berbagai jenis umbi uwi tersebut.Tujuan dari penelitian ini

  4. The Electric Field in an MHD Duct with Permeable Electrodes when the Hall Effect is Present in the Flow of the Moving Medium; 042d 041b 0414

    Energy Technology Data Exchange (ETDEWEB)

    Emec, Ju. P.; Panasevich, L. L. [Institut Elektrodinamiki AN USSR, Kiev, USSR (Ukraine)

    1968-11-15

    raspredelenie toka v okrestnosti provodjashhih stenok kanala. Putem vybora zakona vduva (otsosa) jelektroprovodnoj sredy-podavljajutsja koncevye javlenija na jelektrodah (obuslovlennye jeffektom Holla dvizhushhegosja potoka i geometriej kanala) i raspredelenie toka na nem vyravnivaetsja . Vyvodjatsja neobhodimye i dostatochnye uslovija, pri kotoryh plotnost' toka prinimaet ogranichennye znachenija vblizi oboih koncov pronicaemogo jelektroda. Zakon raspredelenija skorosti na provodjashhej stenke pri jetom, kak pravilo, znakoperemennyj: na otdel'nyh uchastkah jelektroda neobhodimo proizvodit' vduv, a na drugih - otsos provodjashhej sredy. Drugoe obstojatel'stvo, kotoroe projavljaetsja blagodarja pronicaemym jelektrodam, svjazano s integral'nymi harakteristikami MGD-preobrazovatelej. Tak, pri anizotropii provodimosti (obuslovlennoj jeffektom Holla) v linejnom magnitogidrodinamicheskom kanale s dvumja pronicaemymi jelektrodami v sluchae, kogda cherez odin jelektrod vduvaetsja, a cherez vtoroj otsasyvaetsja jelektroprovodnaja sreda, sovmeshheny svojstva hollovskogo i faradeevskogo preobrazovatelej jenergii. Jeta shema techenija izuchaetsja v dannoj rabote. Matematicheski nahozhdenie jelektricheskogo polja privodit k resheniju neodnorodnoj kraevoj zadachi Rimana-Gil'- berta s razryvnymi kojefficientami. Jeta zadacha reduciruetsja k kraevoj zadache Rimana (v sluchae polosy v klasse-avtomorfnyh funkcij) i ee reshenie, opirajushheesja na svojstva integralov tipa Koshi, polucheno v zamknutoj forme. (author)

  5. Report on results of the Experts from the Boris Kidric Institute to the Institute for theoretical and experimental physics in Moscow - Operational Report; Radni izvestaj - Izvestaj o rezultatima posete strucnjaka iz IBK Institutu za teorijsku i eksperimentalnu fiziku u Moskvi

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Petrovic, M; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    .) upoznavanje eksploatacionih karakteristika reaktora TVRS sa 80% obogacenim gorivom, kao i iskustva u vezi sa koriscenjem tog goriva u reaktoru TVRS u Moskvi; b.) upoznavanje sa elementima sigurnosnih analiza u vezi sa uvodjenjem i kriscenjem tog goriva u reaktoru TVRS kao i c.) razmena gledista o programu prevodjenja reaktora RA na novo 80% obogaceno gorivo. U izvestaju su prikazani rezultati ove posete. Osnovni zakljucci do kojih se doslo jesu: a.) poseta je bila korisna i pored toga sto na neka pitanja nije dobijen odgovor; b.) posle obrade dobijenih informacija, posle sticanja prvih iskustava o koriscenju novog goriva u reaktoru RA kao i posle donosenja definitivnog suda o ravnoteznom rezimu reaktora RA sa novim gorivom, bilo bi veoma korisno da se izvrsi jos jedna poseta Institutu u Moskvi; c.) novo disperziono gorivo je mnogo pouzdanije u eksploataciji od starog 2% obogacenog metalnog goriva (kakvo je sada u reaktoru RA); d.) nije bilo primedbi sa aspekta sigurnosti na nas program prevodjenja (prelazni rezim) reaktora RA na novo gorivo; e.) zatrazice se dopunske informacije o maksimalnom dopustivom stepenu izgaranja 80% obogacenog disperzionog goriva i po potrebi izvrsice se blagovremena revizija predvidjenog optimalnog ravnoteznog rezima izgaranja za reaktor RA (baziranog na maksimalnom izgaranju goriva koje omogucuju parametri reaktora RA); f.) metodologija termickog proracuna gorivnih kanala, koja se primenjuje na reaktor RA ocenjena je kao ekvivalentna postupku koji se primenjuje za proracun kanala reaktora TVRS u Moskvi (author)

  6. Operation and maintenance of the RA reactor, RA Research reactor. Annual report 1976; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1976. godini

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    remonta do kojih je dolazilo zbog kvarova (nastalih zbog neizvrsavanja investicionog odrzavanja u toku poslednjih 6 godina) zatim nemogucnost ranijeg pocetka koriscenja novog goriva u reaktoru RA i istrosenosti rezervi starog 2% obogacenog goriva i na kraju zbog obimnog programa eksperimenata u oblasti sigurnosnih analiza vezanih za uvodjenje novog visokoobogacenog goriva u reaktor RA. Na reaktoru RA uspesno su izvrseni eksperimentalni i teorijski radovi u oblasti sigurnosnih analiza za prevodjenje reaktora RA na novo 80% obogaceno gorivo, krunisani eksperimentalnom kampanjom reaktora RA u decembru 1976, kojom se zavrsava 17-to godisnji period koriscenja 2% obogacenog goriva i otpocinje period koriscenja novog 80% obogacenog goriva u reaktoru RA. Ovaj uspeh je od izuzetnog znacaja za reaktor RA i njegove korisnike, jer ce rezultovati u povecanju osnovne proizvodnje neutronskog fluksa od 50%, pri porastu cene kostanja rada reaktora od oko 4%. Podnet je zahtev za konacno odobrenje prelaznog rezima za uvodjenje ovog goriva, kojim se postize usteda od najmanje 2 200 000 dinara. Ovim se obezbedjuje da u 1977. godini i dalje, rad reaktora ne bude vise ometan ''kriticnim'' ili drugim eksperimentima u vezi sa uvodjenjem novog goriva u reaktor. Izvrsen je obiman program remontnih i drugih radova veoma akutne prirode, koji takodje omogucuju nesmetan rad u 1977. godini. Neki od ovih radova nisu radjeni nikad ranije, a drugi nisu radjeni u proteklih 6 godina. Najzacajniji zahvati ove vrste bili su: nabavka Al-cevi od specijalne legure, izrada i montiranje tehnoloskoh kanala; obimno ispitivanje uzroka curenja spoljasnjeg suda; remont teskovodne pumpe; zamena dva vertikalna tehnoloska kanala. Nabavljena je osnovna oprema za izgradnju sistema za hladjenje u slucaju udesa. Izvrseno je opremanje vrucih komora reaktora RA.

  7. Temperature measurement of the reactor materials samples irradiated in the fuel channels of the RA reactor - Annex 16; Prilog 16 - Merenje temperature uzoraka reaktorskih materijala ozracivanih u gorivnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M; Djalovic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    Reactor materials as graphite, stainless steel, magnox, zirconium alloys, etc. were exposed to fast neutron flux inside the fuel elements specially adapted for this purpose. Samples in the form ampoules were placed in capsules inside the fuel channels and cooled by heavy water which cools the fuel elements. In order to monitor the samples temperature 42 thermocouples were placed in the samples. That was necessary for reactor safety reasons and for further interpretation of measured results. Temperature monitoring was done continuously by multichannel milivoltmeters. This paper describes the technique of introducing the thermocouples, compensation instruments, control of the cold ends and adaptation of the instruments for precision (0.5%) temperature measurement in the range 30 deg - 130 deg C; 30 deg - 280 deg C and 30 deg - 80 deg C. Ozracivanje uzoraka materijala za izgradnju reaktora kao sto su grafit, nerdjajuci celik, magnox, legure cirkonijuma, aluminijuma itd. vrseno je u fluksu brzih neutrona unutar samih gorivnih elemenata koji su specijalno adaptirani za ovu svrhu. Uzorci u vidu ampula smesteni su u kapsulu od aluminijuma i postavljeni unutar kanala gde su hladjeni cirkulacijom teske vode koja hladi same gorivne elemente. U cilju kontrole temperature uzoraka radi bezbednosti samog reaktora, kao i radi kasnije interpretacije rezultata ispitivanja radijacionog ostecenja materijala, ugradjeno je 42 termopara u uzorke. Kontrola temperature je vrsena kontinualno visekanalnim registratorima. U radu je prikazana tehnika izvodjenja termoparova, kompenzacionih vodova, kontrola hladnih krajeva i prilagodjenje instrumentacije za merenje i registraciju temperature sa tacnoscu 0,5% u opsezima 30 deg - 130 deg C; 30 deg - 280 deg C i 30 deg - 80 deg C (author)

  8. Measurements at the RA Reactor related to the VISA-2 project - Part 1, Start-up of the RA reactor and measurement of new RA reactor core parameters; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - I deo, Pustanje u rad reaktora RA i merenje fizickih parametara novog jezgra reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    The objective of the measurements was determining the neutron flux in the RA reactor core. Since the number of fuel channels is increased from 56 to 68 within the VISA-2 project, it was necessary to attain criticality of the RA reactor and measure the neutron flux properties. The 'program of RA reactor start-up' has been prepared separately and it is included in this report. Measurements were divided in two phases. First phase was measuring of the neutron flux after the criticality was achieved but at zero power. During phase two measurements were repeated at several power levels, at equilibrium xenon poisoning. This report includes experimental data of flux distributions and absolute values of the thermal and fast neutron flux in the RA reactor experimental channels and values of cadmium ratio for determining the neutron epithermal flux. Data related to calibration of regulatory rods for cold un poisoned core are included. [Serbo-Croat] Svrha merenja je odredjivanje neutronskog fluksa u reaktoru RA. S obzirom na uvecani broj tehnoloskih kanala of 56 na 68 u vezi projekta VISA-2, bilo je potrebno ponovo dovesti reaktora RA do kriticnosti i izvrsiti merenja karakteristika fluksa neutrona. Posebno je pripremljen 'program pustanja u pogon reaktora RA', koji je sadrzan u ovom dokumentu. Program merenja bio je podeljen na dve faze. Prva faza je merenje fluksa pre podizanju reaktora na nominalnu snagu. Slicna merenja vrsena su i na vecim snagama u drugoj fazi, pod uslovima ravnoteznog zatrovanja reaktora ksenonom, jer se tada pokazuju izvesne promene u odgovarajucim karakteristikama fluksa neutrona. Ovaj izvestaj sadrzi merene vrednosti raspodele fluksa i apsolutne vrednosti termalnih i brzih neutrona kao i kadmijumskih odnosa koji su korisceni za odredjivanje fluksa epitermalnih neutrona. Opisana je kalibracija regulacionih sipki za hladan nezatrovan reaktor.

  9. Ra reactor operation plan for 1976 - Annex 6; Prilog 6 - Plan rada reaktora RA za 1976. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    Contrary to previous years the RA reactor operation plan for 1976 is conditioned by more uncertainties than ever for the following reasons. It is planned for February to repair the components in order to eliminate the consequences of leaking from the vertical experimental channel VK-4 which happened in december 1975. Apart from this, measurements related to transfer of the core to highly enriched fuel under minimum power are foreseen to be performed in February. In April, it would be indispensable to locate the point of He gas leaking and its prevention. Core transfer to highly enriched fuel is planned for April for testing of the fuel elements under operating conditions and step by step increase of the power density up to the nominal power. Complete plan for core transfer would be available by the end of February 1976. It is planned to make-up for the mentioned delays from May-December 1976. [Serbo-Croat] Za razliku od prethodnih godina izrada plana rada reaktora RA za 1976. godinu vezana je za mnogo vise neizvesnosti nego ikada ranije iz sledecih razloga. U februaru se vrsi remont opreme i uklanjanja posledica procurivanja vertikalnog eksperimentalog kanala VK-4, koje se dogodilo decembra 1975. Sem toga u februaru se vrse merenja na minimalnim snagama u sklopu priprema za prelazak na novo gorivo. U aprilu ce biti neophodno lociranje mesta gde istice He gas kao i otklanjanje uzroka ovog curenja. Planirano je da se u aprilu ubaci novo gorivo u jezgro u cilju testiranja pod radnim uslovima uz postepeno povecanje snage do nominalne. Planirano je da se smanjeni obim rada usled navedenih uslova nadoknadi u potpunosti u periodu maj-decembar 1976.

  10. Detection of tritium in the air surrounding the heavy water reactors; Elementi detekcije tricijuma u vazduhu kod teskovodnih nuklearnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Matic-Vukmirovic, Z; Hadzisehovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1967-03-15

    This paper contains the study of the literature concerned with physical properties of the tritium, problems of detection control of the tritium level in the atmosphere in the vicinity of heavy water reactors. It is stated that a complete and efficient control of tritium activity, from radiation protection point of view can be achieved only by simultaneous triple measurements: direct measurement of tritium in the air by stationary or movable instruments; air sampling and measurement of activity by laboratory instrumentation; and measurement of tritium in the bio-material of the personnel who have inhaled air contaminated with tritium. Laboratory equipment was adapted for tritium detection in air samples. A method for measuring the specific tritium activity was developed and implemented. The tritium level and distribution in the air were measured during exchange of the fuel channel in the RA reactor. The obtained results indicate that tritium could be dangerous for the staff involved. Proucena je literatura u kojoj se tretiraju osnovne fizicke karakteristike tricijuma, kao i problemi detekcije i kontrole u vazduhu kod teskovodnih nuklearnih reaktora. Utvrdjeno je da kompletna i efikasna kontrola aktivnosti tricijuma, sa aspekta zastite od zracenja, moze biti ostvarena samo ako se vrse istovremeno trostruka merenja: merenje aktivnosti tricijuma u vazduhu direktno, prenosnim ili stacioniranim instrumentima; uzimanje uzoraka vazduha i merenje aktivnosti na laboratorijskoj aparaturi; i merenje aktivnosti tricijuma u biomaterijalu osoblja koje je udisalo vazduh kontaminiran tricijumom. Izvrsena je adaptacija laboratorijske aparature za potrebe detekcije tricijuma u uzorcima vazduha. Razradjen je i uhodan postupak merenja koncentracije aktivnosti tricijuma u uzorcima vazduha. Izvrsena su merenja i dobijeni su rezultati o nivou i raspodeli tricijuma u vazduhu pri operaciji zamene kanala sa gorivom na reaktoru RA u Vinci. Dobijeni rezultati ukazuju na opasnost koju po radno

  11. Nuclear Reactor RA Safety Report, Vol. 15, Analysis of significant accidents; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 15, Analiza znacajnih akcidenata

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Power excursions of the RA reactor a mathematical model of reactor kinetic behaviour was formulated to describe power and temperature coefficients for both reactor fuel and moderator. Computer code TM-1 was written for analysis of possible reactor accidents. Power excursions caused by uncontrolled control rod removal and heavy water flow into the central vertical experimental channel were analyzed. Accidents caused by fuel elements handling were discussed including possible fuel element damage. Although the probability for uncontrolled radioactive materials release into the environment is very low, this type of accidents are analyzed as well including the impact on the personnel and the environment. A separate chapter describes analysis of the loss of flow accident. Safety analysis covers the possible damage of the outer steel Ra reactor vessel and the water screens which are part of the water biological shield. [Serbo-Croat] Radi analize dinamickog ponasanja reaktora RA u toku ekskurzije snage formulisan je matematicki model koji opisuje promene snage i temperature goriva i moderatora. Za analizu predpostavljenih akcidenata realizovan je racunarski program TM-1. Analizirane su ekskurzije snage usled nekontrolisanog izvlacenja kontrolnih sipki i punjenja centralnog vertikalnog eksperimentalnog kanala teskom vodom. Analizirani su akcidenti pri rukovanju nuklearnim gorivom ukljucujuci ostecenje nuklearnog goriva. Iako je verovatnoca za nekontrolisano rasturanje radioaktivnog materijala mala, analizirani su i ovakvi moguci akcidenti koji mogu uticati kako na osoblje reaktora tako i na okolinu. Posebno poglavlje obuhvata analizu akcidenta u slucaju prestanka cirkulacije primarnog hladioca. Analiza sigurnosti reaktora obuhvata i moguce ostecenje spoljasnjeg celicnog suda reaktora RA kao i vodenih ekrana koji su deo vodenog bioloskog stita.

  12. Report on the activity of the RA reactor operation for the period from July 1 1961 - Sept. 30 1961; Tromesecni izvestaj za period od 1.VII do 30.IX 1961. g

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Laboratorija za eksploataciju reaktora RA, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-09-15

    During the reporting period the reactor was permanently ready for operation and responding to the demands of the experimenters. The reactor was operating for 408.5 hours at power levels from 50 - 5000 kW, or 1985 MWh in total, burnup of the first batch of fuel was 22.55%. Reactor core was made of 56 fuel channels. Activities related to construction of new and improvement of the existing equipment was continued in order to enable safe operation and successful utilization of the RA reactor. Exchange of the electronic tubes was continued in order to increase the stability of the reactor control and reactor protection systems. About 65% of tubes planned to be exchanged this year was done. Cooperation with the CEN Saclay, France related to construction of experimental loops VISA-1 and VISA-2 was continued as well as cooperation with Poland concerned with exchange of experts. The problem of lack of properly trained staff was nor solved. [Serbo-Croat] U izvestajnom periodu reaktor je uvek bio spreman za rad i odgovarao je zahtevima eksperimentatora. Reaktor je radio 408,5 casova na snagama od 50-5000 kW, odnosno ukupno 1985 MWh, pri cemu je ukupan utrosak prve sarze goriva bio 22,55%. Jezgro reaktora bilo je sacinjeno od 56 tehnoloskih kanala. Radi bezbednijeg pogona i sto uspesnije eksploatacije reaktora RA nastavljeno je sa radovima na realizaciji novih i poboljsanju postojecih uredjaja. U cilju povecanja stabilnosti elektronskih instrumenta u sistemu upravljanja i zastiti reaktora nastavljeno je sa zamenom elektronskih cevi, do sada je zamenjeno oko 65% radova predvidjenih za ovu godinu. Nastavljena je saradnja sa nuklearnim centrom u Saclay, Francuska na izradi petlje VISA-1 i VISA-2 i saradnja sa Poljskom u razmeni strucnjaka. Problem nedostatka kadrova nije resen.

  13. Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Cupac, S; Vukadin, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    This annex covers: description of the organisational structure of the service, safeguard activities, increase of reactor operation capability, dosimetry and radiation protection tasks and an overview of the the activities of this Service. During 1992, there have been 12 safeguard IAEA inspections. Each time inspection covered fresh fuel, every third inspection included control of the spent fuel storage pool, and once during the fuel inventory control the reactor core was included. With the aim of increasing the operating capabilities besides improvement of experimental devices, construction of the experimental loop with separate cooling system was started. It is planned, as well to improve operating capabilities of horizontal experimental channels by purchasing neutron diffractometer, constructing three-crystal neutron spectrometer, application of three-crystal neutron spectrometer from Krakow, and using the time-of flight spectrometer constructed in the Institute. This Annex describes the possible activities for neutron radiography and isotope production, and includes radiation protection data. [Serbo-Croat] Ova prilog sadrzi opis organizacije tehnoloske sluzbe, 'safeguard' aktivnosti, moguce poboljsanje eksploatacionih mogucnosti reaktora, tehnicke zastite od zracenja i dozimetrije, kao i pregled svih poslova Sluzbe. Tokom 1992. bilo je 12 'safeguard' IAEA inspekcija. Tokom svake inspekcije kontrolisano je sveze gorivo, svaka treca je ukljucila kontrolu bazena za odlezavanje ozracenog goriva, a jednom je kontrolisano i jezgro reaktora RA. Sa ciljem da se poboljsaju operativne mogucnosti reaktora, pored poboljsanja eksperimentalnih uredjaja, pocela je i izgradnja reaktorske petlje sa sopstvenim hladjenjem. Planirano je da se poboljsaju i operativne mogucnosti horizontalnih eksperimentalnih kanala, sto je ucinjeno kupovinom neutronskog difraktometra, izgradnjom trikristalnog neutronskog spektrometra, koriscenjem trikristalnog neutronskog spektrometra koji je

  14. RA Research reactor Annual report 1982 - Part 1, Operation, maintenance and utilization of the RA reactor; Istrazivacki nuklearni reaktor RA - Deo 1 - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1982. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Radivojevic, J; Stamenkovic, D; Skoric, M; Miokovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1982-12-15

    outdated spare parts. Project concerning renewal of the reactor equipment was initiated during the past year according to the contract with the Soviet Atomenergoexport and IAEA which has planned to spend 1 000 000 of rubles for this project. [Serbo-Croat] Probni rad reaktora zapocet septembra 1981. godine na snazi od 2 MW sa 80% obogacenim gorivom nastavljen je u celoj 1982. prema prethodno napravljenom planu. Pocetno jezgro formirano ja sa 44 gorivna kanala sa po deset gorivnih elemenata. Prva polovina godine iskoriscena je za neophodna merenja i ispitivanja radnih parametara rektora i funkcionisanje sistema i opreme u radnim uslovima. U drugoj polovini godine zapocet je program probnog rada na visim snagama. Utvrdjeno je da ugradjeni visak reaktivnosti i kapacitet kontrolnih sipki zadovoljava sigurnosne kriterijume MAAE, ugradjeni visak reaktivnosti moze da omoguci rad na snazi od 4,7 MW u 4 mesecne kampanje sa po 15-20 dana rada, postoje povoljni uslovi za hladjenje jezgra pri pocetnoj konfiguraciji. Izmeren je efekat pocetnog zatrovanja na reaktivnost i raspodelu snage, izmerena je pocetna prostorna raspodela neutronskog fluksa koja iznosi 3,9 10{sup 13} cm{sup -2} s{sup -1} pri znazi od 2 MW. Odredjena je promena kalibracionog koeficijenta u sistemu za automatsko odrzavanje snage. Svi rezultati ukazuju da ce pri nominalnoj snazi od 4,7 Mw biti zadovoljeni svi kriterijum sigurnosti i postovana ogranicenja u odnosu na koriscenje goriva. Po dobijanju dozvole za rad na punoj snazi morace da se izvrsi dopunski probni rad na snagama od 3, 4, i 4,7 MW. Prelaz od pocetne konfiguracije sa 44 gorivna kanala u jezgru vrsice se postupno da bi se dostigla ravnotezna konfiguracija sa 72 gorivna kanala sa po 10 elemenata. Reaktor nije radio u septembu mesecu zbog radova na zameni dela cevovoda koji povezuje pumpnu stanicu na Dunavu sa horizontalnim taloznikom. Kontrola i odrzavanje opreme izvrsavani su redovno u granicama raspolozivosti rezerbinh delova. Teskocu pricinjava

  15. Two-dimensional selector type 2X3; Selecteur bidimensionnel type 2X3; Dvukhmernyj selektor tipa 2X3; Selector bidimensional tipo 2X3

    Energy Technology Data Exchange (ETDEWEB)

    Amram, Y [Centre d' Etudes Nucleaires de Saclay (France)

    1962-04-15

    la lecture: possibilite de lire un spectre de temps de vol dans une bande d'amplitude comprise entre deux limites quelconques. Une operation analogue peut etre effectuee simultanement pour quatre spectres d'amplitudes. (author) [Spanish] Se trata de un selector distinado al estudio de reacciones n, {gamma}, que contiene 2{sup 16} canales (1024 canales de tiempo x 64 canales de amplitud). Las caracteristicas (tiempo de llegada y amplitud) de cada suceso interesante son codificadas y se registran en una cinta magnetica de dieciseis pistas. Los datos contenidos en la cinta se pasan por partes a un bloque de explotacion de los resultados que contiene una memoria de 1024 canales; dicho bloque totaliza los sucesos que presenten las mismas caracteristicas dentro de limites de amplitud y duracion establecidos por el experimentador. Las caracteristicas generales del aparato son las siguientes. Seleccion de tiempo, 1024 canales de anchos comprendidos entre 0,1 y 6,4 {mu}s, agrupados en ocho zonas de interes de 128 canales; seleccion de amplitud, 64 canales de 0,25 a 1 V de ancho; tiempo muerto medio, 7 {mu}s; tiempo de resolucion del conjunto del aparato, < 20 {mu}s; acondicionamiento en la lectura: posibilidad de leer un espectro de tiempos de vuelo en una banda de amplitud comprendida entre dos limites cualesquiera. Se puede realizar una operacion analoga simultaneamente para 4 espectros de amplitudes. (author) [Russian] EHtot selektor, prednaznachennyj dlya izucheniya reaktsij n, {gamma} sostoit iz 2{sup 16} kanalov (1024 kanalov vremeni i 64 amplitudnykh kanala). KHarakteristiki (vremya poyavleniya i amplituda) kazhdogo interesuyushchego sobytiya registriruyutsya posle kodirovaniya na magnitoj lente s 16 dorozhkami. Obrabotka soderzhaniya magnitnoj lenty osushchestvlyaetsya po chastyam na bloke pol'zovaniya rezul'tatami, soderzhashchimi zapominayushchee ustrojstvo s 1024 kanalami, kotoroe obobshchaet sobytiya, imeyushchie odinakovye kharakteristiki v sfere amplituda

  16. Pencemaran merkuri di perairan dan karakteristiknya: suatu kajian kepustakaan ringkas

    Directory of Open Access Journals (Sweden)

    M. Adlim

    2016-05-01

    Full Text Available Abstract. The issue of mercury pollution in Aceh waters, Indonesiadue to gold mining activities hasbeen a polemic in local media and Aceh Local Government and the communities have much concern on this case. The impact of mercury pollution in the Teunom and Tangse (Acehrivers was often assumed that it has similarity with Minamatapollution in Japan. This article intends to enlighten the characteristic mercury either as elements or compounds including methyl mercury which is highly toxic. Gold mining using elemental mercury is poorly soluble in water, the solubility is only 0.06 g per ton of mercury but the solubility can increase indark the sea-bed and ina lot of dissolved oxygen. Based on the properties of solubility, it is understood that the mercury levels in the Teunom and Tangse rivers still below the tolerance limit, but the gold mining activities still bringsthe risk of environmental damage especially inadequate supervision. Many researchers were trying to prove the natural conversionfrom mercury into methyl mercury (biomethylation but they usedthe salt instead of the elemental mercury in their experiments. Methyl mercury is found in nature, but the process mercury conversion into methyl mercury compound is still controversial and it has not obtained adequate evidence for the natural alteration,therefore gold pollution which is due to releasing elemental mercury into environment might not be analogue to Minamata case. Keywords: Aceh; Methyl-mercury; Minamata; Mining; Gold   Abstrak. Informasi pencemaran merkuri di perairan Aceh dan kaitannya dengan aktivitas pertambangan emas telah menjadi polemik sehingga menjadi perhatian Pemda Aceh dan Masyarakat. Dampak pencemaran merkuri di Sungai Teunom dan Tangse sering dianalogikan dengan kasus pencemaran merkuri di teluk Minamata, Jepang. Artikel ini bermaksud memberi pencerahan kharakteristik merkuri baik sebagai unsur maupun sebagai senyawa seperti metil merkuri yang sangat beracun. Penambangan

  17. Status of computational and experimental correlations for Los Alamos fast-neutron critical assemblies; Correlation entre les calculs et les experiences sur les ensembles critiques a neutrons rapides de Los Alamos; Sostoyanie vychislitel'nykh i ehksperimental'nykh korrelyatsij dlya Los-Alamosskoj kriticheskoj sistemy na bystrykh nejtronakh; Conjuntos criticos de neutrones rapidos de Los Alamos; correlacion entre resultados calculados y experimentales

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, G E [Los Alamos Scientific Laboratory, University of California, Los Alamos, NM (United States)

    1962-03-15

    conjuntos de {sup 233}U en geometria esferica sin reflector o con un reflector constituido por una espesa capa de uranio. El autor expondra correlaciones directas entre los datos experimentales, para indicar que existe a priori la posibilidad de alcanzar correlaciones satisfactorias con los datos calculados. Tambien presentara, para diversos conjuntos tipicos y a fin de establecer los detalles de calculo necesarios la sensitividad de los espestros calculados y de los tamanos criticos a los modelos de transporte nsutronico (aproximaciones de transporte e hipotesis de proporcionalidad) y a las aproximacione s aritmeticas (hipotesis de la segmentacion angular finita y representacione s de grupos multiples). Las comparaciones entre los resultados experimentales y las evaluasiones se refieren a los indices espectrales y a los tamanos criticos, asi como a los periodos de semidesintegracion y a las razones correspondientes a los neutrones retardados. (author) [Russian] Novye sistemy i uluchshennaya izmeritel'naya tekhnika predusmatrivayu t periodicheskij peresmotr sostoyaniya vychislenij v zavisimosti ot ehksperimenta. Sleduet podcherknut' vazhnost' nejtronno-spektral'nykh kharakteristik iz-za osobenno trudnorazreshimykh problem, svyazannykhs absolyutnym izmereniem spektral'nykh indeksov i neobkhodimost'yu proverok vychislenij sverkh prostogo kriticheskogo razmera. Postoyannoe uluchshenie izmereniya spektral'nykh indeksov vmeste s uvelicheniem tochnosti kak mikroskopicheskikh dannykh dlya detektora i materialov sborok, tak i vychislitel'noj tekhniki, privodit k postepennomu proyasneniyu kharakteristik gruppy kriticheskikh sistem na bystrykh nejtronakh. Ehta gruppa sejchas vklyuchaet aktivnye zony s U{sup 233} bez otrazhatelya i s tolstym uranovym otrazhatelem. Pryamaya korrelyatsiya sredi ehksperimental'ny kh dannykh budet predstavlena s tsel'yu ukazat' predshestvuyushchi e vozmozhnosti dlya uspeshnykh korrelyatsij s vychisleniem. Budet predstavlena chuvstvitel

  18. A 256-channel measuring and recording system; Un systeme de mesure et d'enregistrement a 256 canaux; Sistema izmerenij i registratsii na 256 kanalov; Sistema de medicion y registro de 256 canales

    Energy Technology Data Exchange (ETDEWEB)

    Krasheninnikov, I S; Kuronkin, S S; Pasechnikova, I P; Safonovi, O A; Tuchina, A S

    1962-04-15

    sistema izmeritel'nykh i registriruyushchikh blokov, prednaznachennaya dlya shirokogo kruga fizicheskikh ehksperimentov. Osnovoj sistemy yavlyaetsya 256 kanal'nyj blok registratsii s emkost'yu kanala 2{sup 16} i blok upravleniya, vypolnennye na ferritakh i tranzistorakh. Arifmeticheskoe ustrojstvo bloka registratsii obespechivaet rabotu kak v rezhime summirovaniya, tak i v rezhime vychitaniya. Vremya polnogo tsikla obrashcheniya k pamyati - 20 mksek. V ustrojstve upravleniya osnovnye komandy, takie kak ustanovka registrov, schityvanie, zapis' i t.d., mogut kombinirovat'sya v lyuboj posledovatel'nosti, chto pozvolyaet znachitel'no rasshirit' funktsii pribora po sravneniyu s izvestnymi priborami. Taktovaya chastota ustrojstva upravleniya zadaetsya kvartsevym generatorom na 4 mggts. V kachestve izmeritel'nykh blokov v sisteme ispol'zuyutsya sleduyushchie: preobrazovatel' amplitud impul'sov v tsifrovoj kod so vremenem preobrazovaniya 0,25 mksek na kanal, integral'noj nelinejnost'yu luchshe {approx} 0,1%, differentsial'noj nelinejnost'yu menee 4%, drejfom nulya menee 0,2 v i nestabil'nost'yu shiriny kanalov menee 0,4% v techenie dlitel'nogo vremeni. Skhema preobrazovatelya vypolnena na lampakh. Vremennoj selektor imeet shirinu kanala ot 1 do 64 mksek. Nestabil'nost' shiriny kanalov menee 10{sup -4}. Logika skhemy dopuskaet registratsiyu nepolnykh impul'sov v kanal pri shirine kanala bolee 8 mksek. Skhema vypolnena na tranzistorakh. Preobrazovatel' malykh vremennykh intervalov (10{sup -9} - 10{sup -7} sek) v edinichnyj tsifrovoj kod imeet vremennoe razreshenie {approx} 2 . 10{sup -5} sek i stabil'nost' shiriny kanala luchshe 10{sup -2}. Vyvod informatsii iz bloka pamyati vozmozhgn v analogovoj forme na ostsillograficheskuyu trubku i v tsifrovom vide na pechatayushchuyu mashinku i indikatsionnye lampochki. (author)

  19. Dosimetry and radiation protection at the RA reactor in 1972; Dozimetrija i zastita kod reaktora RA u 1972. godini

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1973-07-01

    Dosimetry results collected within radiation protection of the RA reactor during this year are presented. Neutron and gamma radiation data were measured at characteristic control points. Statistical review of the total number of measurement is given as well. The report includes contents of radioactive gasses and aerosols in the air, as well as the contamination data of surfaces, clothes and uncovered body parts of the personnel. Particular accident which occurred during dismantling of the experimental channel containing the capsule with the new fuel element was analysed. This accident occurred at the RA reactor at the beginning of this year. It was found that that the maximum individual external dose was 2.2 R, and that only one individual was exposed to this dose. About 15% of the personnel was exposed to doses between 1 and 2 R, the remaining 85% was exposed to doses less than 1 R. Base on the frequency of activities undertaken in the contaminated regions, safety and control measures and expected internal exposure of the personnel, it was evaluated that the internal exposure could be neglected compared to the external exposure of the personnel. Prikazani su rezultati sakupljani u toku godine u okviru dozimetrijske kontrole i zastite kod reaktora. Dati su podaci o nivoima neutrona i gama zracenja na karakteristicnim kontrolnim mestima, kao i statisticki pregledi ukupnog broja merenja. Navedeni su rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela radnog osoblja. Analiziran je specifican akcident koji se odigrao na reaktoru pocetkom godine, pri demontazi eksperimentalnog kanala sa kapsulom novog gorivog elementa. Na kraju, izlozena je analiza ozracivanja radnog osoblja. Konstatovano je da je maksimalna individualna doza spoljasnjeg ozracivanja bila 2,2 (R), i da je ovoj dozi bilo izlozeno samo jedno lice. Oko 15% osoblja bilo je izlozeno dozama izmedju 1 i 2 (R), a ostalih 85

  20. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1983; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1983. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Raickovic, N; Radivojevic, J; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1983-12-15

    After regular shutdown in November 1982, inspection of the fuel elements from the RA reactor core which was done from December 1982 - February 1983 has shown that there are deposits of aluminium oxides on the surface of the fuel cladding. After restart The RA reactor was operated at power levels from 1.8 - 2 MW, with 80% enriched uranium dioxide fuel elements. It was found that there was no corrosion of the fuel element cladding and that it was not possible to find the cause of surface deposition on the cladding surfaces without further operation. It was decided to purify the heavy water permanently during operation and to increase the heavy water flow by operating two pumps. This procedure was adopted in order to decrease the possibility of corrosion. The Safety committee of the Institute has approved this procedure for operating the RA reactor in 1983. The core was made of 80% enriched fuel, critical experiments were done until June 1983, and after that the operation was continued at power levels up to 2 MW. [Serbo-Croat] Pregledom nuklearnog goriva iz tehnoloskih kanala reaktora RA koji je izvrsen u periodu decembear 1982-feburuar 1983. godine nakon zaustavljanja reaktora po isteku novembarske kampanje 1982. godine, ustanovljeno je da ponovo dolazi do stvaranja taloga u obliku hidratisanih oksida aluminiuma na kosuljicama gorivnih elemenata. Nakon ponovnog pustanja u rad, reaktor je do novembra 1981. godine neprekidno bio u pogonu na snagama 1,8 - 2 MW. Jezgro je bilo formirano iskljucivo sa od gorivnih elemenata sa 80% obogacenim uran dioksidom. Utvrdjeno je da kosuljica gorivnog elementa nije korodirala, i da se bez nastval rada ne moze utvrditi uzrok pojave taloga na povrsini kosuljice. Da bi se mogucnost korozije aluminjumskih komponenti u primarnom kolu raktora svela na sto manju meru odluceno je da se vrsi neprekidno preciscavanje teske vode i da se istovremeno poveca protok teske vode radom dve pumpe, Komitet za sigurnost Instituta odobrio je ovakav nacin

  1. 16-channel analyser with high time-resolution for multiple coincidence experiments; Selecteur a 16 canaux a temps de resolution eleve pour experiences de coincidences multiples; Ispol'zovanie shestiadtsatikanal'nogo analizatora s bol'shoj razreshayushchej sposobnost'yu po vremeni dlya opytov s mnogokratnymi sovpadeniyami; Analizador de 16 canales de elevado poder temporal de resolucion para experimentos de coincidencias multiples

    Energy Technology Data Exchange (ETDEWEB)

    Brandt, B; Cappeller, U [University of Marburg, Marburg, Federal Republic of Germany (Germany)

    1962-04-15

    promezhutki vremeni posle narastaniya issleduemogo impul'sa. Opisyvaetsya shestikanal'nyj amplitudnyj analizator impul'sov, pozvolyayushchij proizvodit' signaly amplitudy impul'sa cherez 2,5 x 10{sup -6} sekundy posle narastaniya impul'sa s predelom pogreshnosti menee, chem {+-} 2 x 10{sup -8} sekundy. Vremya razresheniya ne prevyshaet 5 x 10{sup -6} sekund; vo izbezhanie iskazheniya v rezul'tate nakopleniya impul'sov ehto vremya reguliruetsya kontrol'nym konturom. SHirina kanala reguliruetsya usilitelem s oknom, kotoryj mozhet regulirovat'sya v intervale ot 1 v do 7 v. Vysota kanala mozhet vybirat'sya cherez kazhdye 0,5 v v intervale ot 7 v do 103 v. (author)

  2. Problems raised by pulse analysers - functional multi-dimensional analysers; Problemes poses par les analyseurs en impulsions - Analyseurs multidimensionnels fonctionnels; Problemy, voznikayushchie v svyazi s ispol'zovaniem analizatorov impul'sov - funktsional'nye mnogorazmernye analizatory; Problemas planteados por los analizadores de impulsos - Analizadores multidimensionales funcionales

    Energy Technology Data Exchange (ETDEWEB)

    Pages, A [Centre d' Etudes Nucleaires de Saclay (France)

    1962-04-15

    hace imposible el experimento; ademas, al estar concebidos en un solo ''bloque'', son poco adaptables a los diversos modos de empleo. En 1958-59, se estudio y construyo en Saclay un aparato multidimensional limitado a 2 vias de 63 canales. Se establecio una separacion entre las diversas funciones esenciales: analisis, transferencia (que funciona en multidimensional) y elaboracion de los resultados. Los Sres. Amram, Guillon y Thenard estan estudiando y construyendo en la SEG un analizador multidimensional de 1023 x 63 canales (destinado al grupo de medicion de velocidades neutronicas de la SPNBE). A fln de superar las limitaciones formuladas mas arriba, en el laboratorio de electronica de la SPNBE, se esta construyendo un analizador multidimensional funcional, en el cual la funcion de transferencia esta a su vez subdividida en unidades (ritmador, memoria no integradora, acondicionador y calculadora). Igual que los limites que definen las vias, los tipos de unidades elegidas varian segun las necesidades y la complejidad del experimento (idioma normal interfuncional). (author) [Russian] Vse chashche ehksperimentatory pol'zuyutsya analiticheskimi sistemami, dayushchimi vozmozhnost' poluchit' funktsiyu mnogikh para- metrov (chislo parametrov mozhet izmenyat'sya v zavisimosti ot kharaktera opyta, a takzhe ot tochnosti ego provedeniya). Sovremennye analizatory nedostatochno sootvetstvuyut vse vozrastayushchej slozhnosti opytov, i ehto proiskhodit po mnogim prichinam: chislo vozmozhnykh parametrov slishkom neznachitel'no (deblokirovanie proizvoditsya tol'ko v analizatory so 100 i 256 kanalami). EHto ogranichenie znachitel'no uvelichivaet vremya ispol'zovaniya uskoritelya. Inogda provedenie opyta stanovitsya nevozmozhnym iz-za plokhoj ''otdachi'' ehtikh analizatorov. Inogda iz-za ikh sborki v odin edinstvennyj ''blok'' im ne khvataet ''gibkosti'' v ispol'zovanii. Avtory izuchilii postroili v 1958-1959 godakh mnogorazmernuyu ustanovku, ogranichennuyu dvumya putyami po 63 kanala

  3. Notes on the Start-Up of the Latina Power Station; Notes concernant le demarrage de la centrale nucleaire de Latina; Zapusk ehlektrostantsii Latina; Notas sobre la puesta en marcha de la central electrica de Latina

    Energy Technology Data Exchange (ETDEWEB)

    Calabria, G.; Gualtieri, G. [AGIP Nucleare, Milano (Italy)

    1963-10-15

    desarrollo de los ensayos finales, sobre la carga del combustible y el orden en que se ejecutaron las operaciones de puesta en marcha y sobre las determinaciones y maniobras de regulacion posteriores al estado critico. Se resenan asimismo las operaciones iniciales de generacion y conexion de la central con la red electrica. Por ultimo, se mencionan los problemas de organizacion derivados de la explotacion de la central, incluyendo la preparacion y formacion profesional del personal y las medidas de seguridad adoptadas. (author) [Russian] Privoditsya informatsiya o zapuske pervoj ital'yanskoj atomnoj ehlektrostantsii Latina moshchnost'yu 200 mgvt. Reaktor rabotaet na prirodnom urane s grafitovym zamedlitelem i gazovym okhlazhdeniem. Posle kratkogo opisaniya osnovnykh kharakteristik ehlektrostantsii privodyatsya podrobnye dannye otnositel'no provedeniya zaklyuchitel'nykh ispytanij stantsii'', toplivnoj zagruzki i poryadka ehkspluatatsii, izmerenij i upravleniya s dovedeniem do kriticheskogo sostoyaniya. Daetsya ob''yasnenie raboty po zapusku i vklyucheniyu stantsii v ehlektroset'. Izlagayutsya takzhe problemy, svyazannye s ehkspluatatsiej stantsii, v tom chisle podgotovka personela i ego kvalifikatsiya, mery po bezopasnosti. (author)

  4. Transistor precision pulse-shaper with short recovery time; Dispositif de haute precision pour la mise en forme des impulsions, a transistors et a faible temps de recuperation; Tranzistornyj tochnyj formirovatel' impul'sov s korotkim vremenem vosstanovleniya; Formador de impulsos de precision, transistorizado, de corto tiempo de recuperacion

    Energy Technology Data Exchange (ETDEWEB)

    Lotto, I De [European Atomic Energy Community, CCR, Ispra (Italy)

    1962-04-15

    anchura de los impulsos superior al 2%, sin necesidad de ajustes sucesivos y 2) una estabilidad de la anchura de los impulsos superior al 1%, para variaciones de 20{sup o}C en la temperatura. Las caracteristicas del circuito son tales que se pueden utilizar transistores de baja tension inversa base-emisor, por lo que pueden emplearse la mayor parte de los tipos de transistores rapidos. (author) [Russian] Formirovatel' impul'sov s korotkim vremenem vosstanovleniya chasto neobkhodim v yadernoj ehlektronike. Formirovatelem impul'sov s naibolee korotkim vremenem vosstanovleniya yavlyaetsya korotkij mul'tivibrator so skhemoj khronirovaniya RC. Pro-analizirovany dannyj vid skhemy khronirovaniya i vliyanie kharakteristik tranzistora na rabotu ehtoj skhemy. Predlozheny neskol'ko izmenenij skhemy dlya dostizheniya 1) tochnosti shiriny impul'sa bol'she, chem na 2%, bez neobkhodimosti individual'nykh prisposoblenij i 2) stabil'nosti shiriny impul'sa bol'she, chem na 1%, pri temperature svyshe 20{sup o}C. Skhema rasschitana takim obrazom, chto dopuskaetsya ispol'zovanie tranzistorov s obratnym napryazheniem ehmittera s nizkoj osnovoj podobno tomu, kak ehto nablyudaetsya u bol'shej chasti tranzistorov. (author)

  5. A review of calculation methods for fast and intermediate reactors; Expose des methodes pour le calcul de reacteurs a neutrons rapides et intermediaires; Obzor metodov rascheta reaktorov na promezhutochnykh i bystrykh nejtronakh; Estudio panoramico de los metodos de calculo de los reactores rapidos e intermedios

    Energy Technology Data Exchange (ETDEWEB)

    Marchuk, G I [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    de ecuaciones fundamentales y conjugadas de la teoria de los multigrupos. Expone luego diversas aplicaciones de la teoria de la perturbacion a los problemas del calculo fisico del reactor. Examina los metodos numericos de resolucion de las ecuaciones fundamentales y conjugadas que expresan el funcionamiento del reactor sobre la base del metodo de los armonicos esfericos. Explica asimismo como se utiliza el metodo de las caracteristicas en la solucion de problemas relativos a la masa critica del reactor. Describe los metodos de calculo de los reactores con moderadores que contienen hidrogeno y, por fin, expone las bases de un modelo efectivo fundado en la teoria de un solo grupo, aplicable al reactor. (author) [Russian] Obsuzhdaetsya razvitie metodov rascheta yadernykh reaktorov na promezhutochnykh i bystrykh nejtronakh. Rassmatrivayuts ya razlichnye postanovki zadach fizicheskogo rascheta. Obsuzhdaetsya uchet rezonansnykh ehffektov. Vvodyatsya v rassmotrenie mnogogruppovy e sistemy 'osnovnykh i sopryazhennykh uravnenij. Daetsya razlichnoe primenenie teorii vozmushchenij k zadacham fizicheskogo rascheta reaktora. Rassmatrivayuts ya chislennye metody resheniya osnovnykh i sopryazhennykh uravnenij reaktora v priblizhenii metoda sfericheskikh garmonik. Daetsya primenenie metoda kharakteristik k resheniyu zadach na kriticheskuyu massu reaktora. Izlagayutsya metody rascheta reaktorov s vodorodsoderzhashchim i zamedlitelyami . Izlagayutsya osnovy ehffektivnoj odnogruppovoj modeli reaktora. (author)

  6. Self-Absorption Studies with a 4 {pi} {beta}-Proportional Flow Counter; Etudes sur l'autoabsorption avec un compteur {beta} 4 {pi} proportionnel a courant; Izuchenie samopogloshcheniya pri pomoshchi {beta} proportsional'no-potochnogo 4 {pi} schetchika; Estudios sobre autoabsorcion con un contador de flujo proporcional {beta}4 {pi}

    Energy Technology Data Exchange (ETDEWEB)

    Yaffe, L; Fishman, J B [Radiochemistry Laboratory, Dept. of Chemistry, McGill University, Montreal, Quebec (Canada)

    1960-06-15

    entre 0,018 y 1,7 MeV) recogiendolos sobre finas peliculas de resina vinilica (VYNS) y han determinado las caracteristicas de autoabsorcion. Presentan una serie de curvas, obtenidas experimentalmente, que relacionan la E{sub max} el espesor de la fuente y la autoabsorcion. Les datos referentes a la autoabsorcion han sido sometidos a un analisis teorico, para contadores de angulo pequeno y 4 {pi}. Las curvas de autoabsorcion determinadas experimentalment e para contadores 4 {pi} estan comprendidas entre las curvas teoricas que corresponden a los angulos solidos pequenos y las curvas determinadas mediante contador de geometria 4 {pi}. (author) [Russian] Izuchenie samopogloshcheni {beta} izluchatelej provodilos' pri pomoshchi priemov, izlozhennykh Pejtom i YAffe v kanadskom khimicheskom zhurnale [Can. J. Chem. 34, 265 (1956]. Letuchie soedineniya H{sup 3}, S{sup 14}, So{sup 60}, Hg{sup 203}, As{sup 77} i P{sup 32} (E{sub max} ot 0,018 do 1,7 MeV) peregonyalis' na tonkie VYNS ustanovki i opredelyalas' kharakteristik a samopogloshcheniya . Privodyatsya serii s ehmpiri- cheskim opredeleniem krivykh, otnosyashchikhsya k E{sub max}, tolshchine istochnika i samopogloshchenie . Dannye samopogloshcheni ya podvergalis' teoreticheskom u analizu na schetchikakh s malym uglom i na 4 {pi} geometricheski kh schetchikakh. EHksperi- mental'no opredelennye krivye samopogloshcheni ya s pomoshch'yu 4 {pi} geometricheskikh schetchikov nakhodyatsya mezhdu krivymi, poluchennymi s pomoshch'yu schetchikov s teoreticheski malymi uglami i s pomoshch'yu 4 {pi} geometricheskikh schetchikov. (author)

  7. Algoritmi selektivnog šifrovanja - pregled sa ocenom performansi / Selective encryption algorithms: Overview with performance evaluation

    Directory of Open Access Journals (Sweden)

    Boriša Ž. Jovanović

    2010-10-01

    Full Text Available Digitalni multimedijalni sadržaj postaje zastupljeniji i sve više se razmenjuje putem računarskih mreža i javnih kanala (satelitske komunikacije, bežične mreže, internet, itd. koji predstavljaju nebezbedne medijume za prenos informacija osetljive sadržine. Sve više na značaju dobijaju mehanizmi kriptološke zaštite slika i video sadržaja. Tradicionalni sistemi kriptografske obrade u sistemima za prenos ovih vrsta informacija garantuju visok stepen sigurnosti, ali i imaju svoje nedostatke - visoku cenu implementacije i znatno kašnjenje u prenosu podataka. Pomenuti nedostaci se prevazilaze primenom algoritama selektivnog šifrovanja. / Digital multimedia content is becoming widely used and increasingly exchanged over computer network and public channels (satelite, wireless networks, Internet, etc. which is unsecured transmission media for ex changing that kind of information. Mechanisms made to encrypt image and video data are becoming more and more significant. Traditional cryptographic techniques can guarantee a high level of security but at the cost of expensive implementation and important transmission delays. These shortcomings can be exceeded using selective encryption algorithms. Introduction In traditional image and video content protection schemes, called fully layered, the whole content is first compressed. Then, the compressed bitstream is entirely encrypted using a standard cipher (DES - Data Encryption Algorithm, IDEA - International Data Encryption Algorithm, AES - Advanced Encryption Algorithm etc.. The specific characteristics of this kind of data, high-transmission rate with limited bandwidth, make standard encryption algorithms inadequate. Another limitation of traditional systems consists of altering the whole bitstream syntax which may disable some codec functionalities on the delivery site coder and decoder on the receiving site. Selective encryption is a new trend in image and video content protection. As its

  8. Data about operation and utilization of the RA in 1976 - Report, Annex I; Prilog I - Podaci o radu i iskoriscenosti reaktora RA u 1976. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    During 1976 there were significant discrepancies in RA reactor operation in comparison with the operating plan made at the end of 1975. Some discrepancies were planned but not all could be foreseen due to the following reasons: no possibility to estimate the precise schedule of aluminium tubes for fuel channels delivery from the; USSR; no means to estimate precise time for repairs that were never performed or were not done during previous 6 years; inability to estimate the time needed for experiments within the program of transfer to highly enriched fuel (which was successfully finished) since some of these experiments were never done before. Some repairs were not planned since unpredicted failures occurred. Six fuel exchanges were planned, but they were somewhat delayed. Detailed data about the planned and achieved reactor operation are shown in this annex as well as interruptions. There were 12 shorter interruptions and safety shutdowns which was in total for 64 hours. Reactor was operated at nominal power of 6.5 MW. There have been no significant accidents, but two cases could be characterised as accidental according to their occurrence not according to the effects. The first was break of the tube next to the heavy water pump, and the second was contamination of the reactor hall and corridor during preparation of the fuel exchange machine (spill of heavy water). This annex covers the data concerned with utilization of experimental facilities and reactor utilization. [Serbo-Croat] Reaktor RA je u toku 1976. godine radio sa znatnijim odstupanjima od plana rada za 1976. godinu, donetom krajem 1975. godine. Medjutim, ni ova procena mogucih odstupanja nije mogla biti korektna iz sledecih, razloga: nemogucnost da se predvidi tacan rok isporuke cevi od specijalne aluminijumske legure iz SSSR za izradu tehnoloskih kanala, nemogucnost da se predvidi tacno vreme potrebno za remonte kakvi ili nisu radjeni ranije ili su radjeni pre vise od 6 godina pod povoljnijim uslovima

  9. Observations of Mercury Flowing along a Trough in a Transverse Magnetic Field; Nekotorye nablyudeniya techeniya rtuti v lotke v poperechnom magnitnom pole

    Energy Technology Data Exchange (ETDEWEB)

    Vulis, L. A.; Jaglenko, V. T. [Akademija Nauk SSSR, Moskva, SSSR (Russian Federation)

    1966-11-15

    diverging duct when certain relationships held. Limitations associated with the superposition of a magnetic field were established, in addition to the usual hydro-gas analogy. (author) [Russian] Privodjatsja nekotorye rezul'taty nabljudenija stacionarnogo techenija rtuti v gorizontal'nom lotke pri nalichii poperechnogo magnitnogo polja. Izuchenie takogo vida dvizhenija provodjashhej sredy so svobodnoj poverhnost'ju v magnitnom pole predstavljaet dvojakij interes - dlja sopostavlenija rezul'tatov opytov i rascheta MGD techenij neszhimaemoj zhidkosti, s odnoj storony, i v kachestve priblizhennoj modeli dvizhenija plazmy v svete izvestnoj gidrogazovoj analogii dlja MGD techenij, s drugoj storony. Rassmotreny rezul'taty opytov, ohvatyvajushhih dokriticheskie i sverhkriticheskie techenija rtuti v oblasti znachenija chisel Fruda OD -3,0 pri ves'ma malyh znachenijah magnitnogo chisla Rejnol'dsa i bol'shih znachenijah chisla Gartmana (svyshe 100). Osnovnye parametry ustanovki sledujushhie: razmery kanala 40x 200 mm, skorost' techenija rtuti do 1,2 m/sek, magnitnaja indukcija do 1,2 tl. Dlja nepreryvnyh (dokriticheskih i sverhkriticheskih) techenij v kanalah postojannogo i peremennogo sechenija sravnivajutsja opytnye dannye po izmeneniju mestnoj i polnoj vysoty urovnja zhidkosti s raschetom, vypolnennym v odnomernom priblizhenii. Polucheny podrobnye harakteristiki gidravlicheskogo pryzhka v poperechnom pole, ego struktury i modifikacii, poter' polnoj vysoty i dr. V opytah izuchalos' dvizhenie rtuti v kanale s izolirovannymi stenkami i pri nalichii jelektrodov s vneshnim soprotivleniem. Osnovnoj metod nabljudenija - fotograficheskij, narjadu s jetim proizvodilis' izmerenija jelektricheskih (raspredelenie potenciala i dr.) i gidravlicheskih harakteristik. V rezul'tate issledovanija pokazano, chto odnomernaja raschetnaja shema udovletvoritel'no opisyvaet nepreryvnoe techenie v kanale (osobenno postojannogo sechenija). Vyjavlen rjad osobennostej, prisushhih rassmatrivaemym javlenijam i

  10. The Measurement of Natural Tritium Levels in Geiger Counters; Determination quantitative du tritium naturel par compteurs Geiger; Izmerenie urovnej estestvennogo tritiya v schetchikakh Gejgera; Medicion de concentraciones naturales de tritio mediante contadores Geiger

    Energy Technology Data Exchange (ETDEWEB)

    O' Brien, B J [Institute of Nuclear Sciences, Gracefield (New Zealand)

    1962-01-15

    -argona v kachestve gaza dlya gasheniya. Pologaya chast' kharakteristiki skorosti otscheta nesovpadenij byla neudovletvoritel'noj pri nizkikh skorostyakh scheta, chto ob{sup y}asnyaetsya plokhim gasheniem, a poehtomu byli provedeny poiski gazov s bolee ehffektivnym gasheniem. Rassmatrivaetsya nakonl pologoj chasti kharakteristiki skorosti otscheta istochnika Fona, a takzhe ukazyvayutsya neobkhodimye svojstva podkhodyashchego gasyashchego gaza dlya otscheta vodoroda. Privodyatsya rezul'taty izucheniya kharakteristik podscheta vodoroda, kotoryj gasitsya s pomoshch'yu benzola, bromistogo ehtila, prostogo ehtilovogo ehfira, izopropilovogo amina, geksana, ehtil-amina i izoprena. V chastnosti, ehtil-amin i ehfir dayut ves'ma udovletvoritel'nye gasyashchie kharakteristiki. Soderzhitsya opisanie schetnoj sistemy, ispol'zuyushchej schetchik, napolnennyj do 40 cm vodorodom i gasimyj ehtil-aminom. Koehffitsient fona sostavlyaet 3 otscheta v minutu pri sravnitel'no ploskom fone pologoj chasti kharakteristiki . (author)

  11. Construction and Operation of a Commercial Gamma-Ray Package-Sterilizing Plant; Construction et fonctionnement d'une installation industrielle pour la sterilisation d'articles sous emballage par les rayons gamma; Razrabotka i ehkspluatatsiya sbornoj ustanovki gamma-izlucheniya promyshlennogo tipa dlya sterilizatsii meditsinskikh materialov; Construccion y funcionamiento de una instalacion industrial para la esterilizacion gamma de articulos medicos empaquetados

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, C. G. [Johnson' s Ethical Plastics Ltd., Slough (United Kingdom)

    1963-11-15

    Upravlenii po atomnoj ehnergii Soedinennogo Korolevstva), nastoyashchaya ustanovka byla sproektirovana spetsial'no dlya sterilizatsii plastmassovykh shpritsev i drugikh meditsinskikh materialov analogichnoj plotnosti. Ustanovka nachala funktsionirovat' s noyabrya 1962 goda. Dano opisanie osnovnykh kharakteristik i osobennostej e konstruktsii, priborov, obespechivayushchikh zashchitu obsluzhivayushchego personala, i metoda zagruzki sterzhnej. Opisan opyt ehkspluatatsii, vklyuchaya dozimetriyu, vklyuchenie ustanovki v edinyj tekhnologicheskij tsikl; privedeny rezul'taty bakteriologicheskikh issledovanij. Kratko obsuzhdeny ehkonomicheskie pokazateli pri sterilizatsii gamma-izlucheniem; dana otsenka vozmozhnosti primeneniya ustanovok podobnogo tipa v budushchem. (author)

  12. A transistorized 1024-channel neutron time-of-flight analyser; Selecteur transistorise de temps de vol pour neutrons, a 1024 canaux; Nejtronnyj analizator vremeni proleta s 1024 kanalami i s perevodom skhemy na tranzistory; Aparato transistorizado de 1024 canales para analizar tiempos de vuelo de neutrones

    Energy Technology Data Exchange (ETDEWEB)

    Giannelli, G [European Atomic Energy Community, CCR, Ispra (Italy)

    1962-04-15

    adaptabilidad y que sea posible modificar o ampliar si lo precisaran los experimentadores. (author) [Russian] Daetsya opisanie nejtronnogo analizatora vremeni proleta s 1024 kanalami i s perevodom skhemy na tranzistory. EHtot pribor byl razdelen na dve absolyutno nezavisimye chasti: analog k tsifrovomu preobrazovatelyu (ATSP), kotoryj izmeryaet vremya proleta, i 1024-kanal'noe nakopitel'noe ustrojstvo na ferritovykh serdechnikakh. Takim putem vykhodnye signaly, postupayushchie iz ATSP, mogut byt' zaregistrirovany na magnitnoj lente vmeste s vykhodnymi signalami iz drugikh ATSP, izmeryayushchikh drugie fizicheskie kolichestva, otnosyashchiesya k tomu zhe yadernomu prevrashcheniyu pri obshchem kolichestve kanalov, prevyshayushchem moshchnost' nakopitel'nogo ustrojstva. Analog tsifrovogo preobrazovatelya snabzhen vremennym zapominayushchim ustrojstvom, kotoroe blagodarya svoemu regulirovaniyu skorosti signalov: 1) pozvolyaet dostich' velichiny mertvogo vremeni lish' 0,5 {mu} v sekundu, kogda analog tsifrovogo preobrazovatelya svyazan neposredstvenno s 1024-kanal'nym nakopitel'nym ustrojstvom; i 2) sposobstvuet luchshemu ispol'zovaniyu samoj magnitnoj lenty, kogda analog tsifrovogo preobrazovatelya privodit v dejstvie magnitofon. Vremennoe zapominayushchee ustrojstvo obladaet sposobnost'yu zapominat' s chetyrekhkratnoj tochnost'yu (vplot' do shestnadtsati dvoichnykh razryadov). SHirina kanala analizatora kolebletsya ot 0,5 do 48 {mu}s. 1024 kanala mogut byt' razdeleny na dve odinakovye gruppy po 512 kanalov, kazhdaya iz kotorykh soedinyaetsya s dvumya detektorami. Vremennoe zapominayushchee ustrojstvo dopuskaet odnovremennuyu zapis' signalov dvumya gruppami. Kanaly mogut byt' takzhe podrazdeleny po vremeni proleta na dve gruppy, iz kotorykh pervaya gruppa (16 kanalov) ispol'zuetsya dlya zapisi chisto nulevogo vremeni proleta, togda kak vtoraya gruppa mozhet byt' ispol'zovana v lyuboj pozitsii po obshchim intervalam vremeni mezhdu proletami. CHislo kanalov, ispol'zuemykh dlya zapisi

  13. RA Research reactor, Annual report 1970 - Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1970. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1970-12-15

    specijalnih televizijskih kamera i teleskopa ustanovljeno je da je unutrasnjost suda u odlicnom stanju, nisu uoceni nikakvi tragovi korozije. Istovremeno su napravljeni prikljucci na cevovodu teske vode u cilju realizacije projekta sistema za udesno hladjenje reaktorskog jezgra. Tokom 1970. godine isluzeno gorivo prepakovano je iz tahnoloskih kanala u specijalne sudove od aluminjuma. U bazen br. 4 odlozeno je 4 suda sa ukupno 660 elemenata, tako da se sada u bazenu nalazi 18 sudova sa 2951 gorivnim elementom. Izvrsene su tri izmene goriva i to mesanjem starog sa 5 ili 6 novih gorivnih elemenata. Poslovi u toku stajanja reaktora bili su skopcani cesto sa radom u polju visokog zracenja, sto je uzrokovalo vece totalne doze doze ozracivanja ljudstva. Maksimalna doza zracenja po coveku nije bila veca od 3,5 R. Nastavljena je saradnja sa francuskim partnerom na polju izucavanja mogucnosti koriscenja 93% obogacenog urana umesto sadasnjeg niskoobogacenog kako bi se postigao fluks reda velicine 10{sup 14} n/cm{sup 2} sec. Napominje se da je ostvarenje plana rada za 1971. godinu dovedeno u pitanje usled nedostatka finansijskih sredstava.

  14. Preparation of Uranium Dioxide by Electrochemical Reduction in Ammonium Carbonate Solutions and Subsequent Precipitation; Preparation de bioxyde d'uranium par reduction electrochimique dans des solutions de carbonate d'ammonium et precipitation; Prigotovlenie dvuokisi urana metodom ehlektrokhimicheskogo vosstanovleniya v rastvore karbonata ammoniya s posleduyushchim osazhdeniem; Preparacion de dioxido de uranio por reduccion electroquimica en soluciones de carbonato amonico u precipitacion subsiguiente

    Energy Technology Data Exchange (ETDEWEB)

    Pravdic, V.; Branica, M.; Pucar, Z. [Department of Physical Chemistry, Rudjer Boskovic Institute, Zagreb, Yugoslavia (Serbia)

    1963-11-15

    dvumya 50-litrovymi rezervuarami i podavalsya k intensivno peremeshivaemomu rtutnomu katodu. Rabochij potentsial rtuti proveryalsya po ehlektrodu sravneniya Ag/AgCl/KCl (Sat.). Potentsial podderzhivalsya postoyannogo znacheniya - 1,5 vol't. Proizvoditel'nost' po toku byla okolo 90%, dlya protsessa vosstanovleniya potreblyaemaya ehnergiya sostavlyala okolo 0,8 kvt-chas/kg dvuokisi urana. Po okonchanii ehlektroliza osazhdenie initsiirovali tol'ko pri pomoshchi nagreva temnozelenogo, prozrachnogo rastvora do temperatury 70 deg. C v spetsial'nom steklyannom sosude ob''emom 60 1. Iz 50 1 katalicheskogo rastvora poluchili 1 kg tsentrifugirovannogo produkta (soderzhanie vody okolo 20%). Kulonometricheskij analiz otnosheniya O/U daval vsegda rezul'taty, lezhashchie v predelakh ot 2,04 do 2,0. Opisannym sposobom gidrookis' urana (IV) osazhdaetsya selektivno. Ustanovleno, chto otnoshenie O/U v osadke ne zavisit ot polnoty vosstanovleniya. Pri pomoshchi rentgenoskopii produkt identifitsirovan kak al'fa-faza dvuokisi urana. Opyty po spekaniyu i kharakteristike poluchennoj takim obrazom dvuokisi urana, prigodnoj dlya keramicheskogo yadernogo topliva, prodolzhayutsya. (author)

  15. Measurement of resonance parameters of cross-sections affecting fast-neutron propagation in various media; Mesure des parametres de resonance de sections efficaces lies a la propagation des neutrons dans differents milieux; Izmerenie parametrov rezonansnoj struktury sechenij, vliyayushchikh na rasprostranenie bystrykh nejtronov v sredakh; Medicion de los parametros de resonancia de las secciones eficaces que afectan a la propagacion de los neutrones rapidos en distintos medios

    Energy Technology Data Exchange (ETDEWEB)

    Nikolaev, M N; Filippov, V V; Bondarenko, I I [Academy of Sciences, Moscow, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    , prostiraetsya vplot' do neskol'kikh desyatkov kehv dlya tyazhelykh yader i do neskol'kikh Mehv dlya yader srednego vesa. Dlya ucheta rezonansnykh ehffektov pri vychislenii gruppovykh parametrov neobkhodimo znat' ne tol'ko srednie secheniya vzaimodejstviya nejtronov s veshchestvami, no i takie velichiny, kak (1/{Sigma}{sub t}), (1/{Sigma}{sub t}{sup 2}) i drugie - skobki oznachayut usrednenie po ehnergeticheskoj gruppe. Imeyushchiesya v nastoyashchee vremya svedeniya o rezonansnykh parametrakh v oblasti bystrykh nejtronov nedostatochny dlya togo, chtoby ukazannye velichiny mogli byt' vychisleny s neobkhodimoj tochnost'yu. V svyazi s ehtim predstavlyaet interes neposredstvenno e izmerenie velichin (1/{Sigma}{sub t}), (1/{Sigma}{sub t}{sup 2}) i drugikh analogichnykh kharakteristik. V doklade privodyatsya rezul'taty izmerenij ryada parametrov takikh kak ({Sigma}{sub t}), ({Sigma}{sub t}{sup 2}), (1/{Sigma}{sub t}), (1/{Sigma}{sub t}{sup 2}), (1/{Sigma}{sub t}{sup 3}) i drugie, kharakterizuyushchi kh strukturu sechenij ryada yader srednego vesa v oblasti ot 300 kehv do 3 Mehv. Ukazannye velichiny byli polucheny putem analiza krivykh propuskaniya, snyatykh v khoroshej geometrii vplot' do propuskanij {approx}10{sup -2}. Poluchennye dannye ukazyvayut na sil'noe vliyanie rezonansnykh ehffektov na diffuzionnye kharakteristiki veshchestva. (author)

  16. The Development of Materials for Application to Control Rod Systems in Graphite moderated Reactors; Mise au Point de Materiaux pour les Dispositifs de Controle a Barres, Utilbes dans les Reacteurs Ralentis au Graphite; Razrabotka materialov , primenyaemykh v sistemakh upravlyayushchikh sterzhnej v reaktorakh s grafitovym zamedlitelem; Perfeccionamiento de Materiales Aplicables a las Barras de Control en los Reactores Moderados por Grafito

    Energy Technology Data Exchange (ETDEWEB)

    Wade, G. E.; Kempf, F. J. [Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1964-06-15

    polozhenija kanala. Dlja izgotovlenija takih rubashek neobhodimy materialy, obladajushhie ustojchivost'ju protiv iznosa i udarnyh vozdejstvij, vysokoj prochnost'ju i nizkim poperechnym secheniem zahvata pri uslovijah jekspluatacii bez ohlazhdenija. Dlja jetoj celi ispol'zovalis' piroliticheskij grafit, soedinenija piroliticheskogo grafita, okis' aljuminija i karbid kremnija. Dannye po fizicheskim povrezhdenijam i povrezhdenija v rezul'tate obluchenija svidetel'stvujut o tom, chto nekotorye iz jetih materialov prigodny dlja izgotovlenija rubashek sterzhnevyh kanalov. (author)

  17. Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

    Energy Technology Data Exchange (ETDEWEB)

    Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

    1963-10-15

    entonces de comportarse como reactor de agua hirviente de ciclo directo; en cierto modo, funciona como reactor de ciclo doble y circulacion natural. (author) [Russian] 25 maya 1962 goda Argonnskaya natsional'naya laboratoriya poluchila razreshenie KAEH SSHA na ehkspluatatsiyu reaktora EBWR na moshchnosti 100 mgvt. Administrativnoe razreshenie na ehkspluatatsiyu reaktora bylo predostavleno sistemoj garantij. Mezhdunarodnogo agentstva po atomnoj ehnergii 11 iyulya 1961 goda. 15 noyabrya 1962 goda byl dostignut uroven' moshchnosti v 100 mgvt. 6 dekabrya 1962 goda ehksperimental'naya programma byla zakonchena. Odnoj iz osnovnykh tselej ee byla tshchatel'naya proverka reaktora dlya polucheniya dannykh i informatsii rabochej kharakteristiki ehtogo tipa reaktora. Ehta programma byla pervoj programmoj takogo roda i pervoj vypolnennoj programmoj. Dlya polucheniya nuzhnykh dannykh neobkhodimo bylo razrabotat' mnogie novye pribory. TSel' byla dostignuta, polucheno mnogo novykh dannykh o rabochej kharakteristike kipyashchego reaktora s estestvennoj tsirkulyatsiej. Tak,naprimer, poluchena informatsiya otnositel'no skorosti potoka tsirkulyatsii v zamknutom tsikle, predelov separatsii zhidkogo para (vydelenie para v osadok v spusknoj trube i unos zhidkosti ehflu- entom para), nedogreva, lokalizatsii dejstvitel'noj poverkhnosti razdela v reaktore i ee svyazi s urovnem vodnoj kolonki, skorosti razrusheniya para v spusknoj trube, pustotnykh koehffitsientov, reaktivnoj sposobnosti H{sub 3}BO{sub 3}, temperaturnykh koehffitsientov, ispol'zovaniya sterzhnej iz bora dlya tselej kontrolya, ispol'zovaniya svezhikh toplivnykh ehlementov, peredatochnykh funktsij,analiza shuma, nekotorykh izmerenij potoka, stabil'nosti i t.d. Krome togo, byli polucheny dannye o povedenii i tselostnosti nekotorykh reaktornykh komponentov i sistem, takikh, kak bornokislaya kontrol'naya reaktsiya, urovni radiatsii, raspredelenie produktov korrozii, vykhod iz stroya oborudovaniya, toplivo i reguliruyushchie sterzhni i t

  18. Integral physics data for fast-reactor design; Donnees de physique integrale intervenant dans les etudes de reacteur a neutrons rapides; Integral'nye fizicheskie dannye dlya raschetov reaktorov na bystrykh nejtronakh; Datos fisicos integrales para el diseno de reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Loewenstein, W B; Meneghetti, D [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    dannye po fakticheskim ehnergeticheskim reaktoram-razmnozhitelya m na bystrykh nejtronakh. EHti sistemy slishkom slozhny dlya prove- deniya prostogo teoreticheskogo analiza. Oni svidetel'stvuyut o slozhnosti fakticheskogo reaktora po sravneniyu s bolee idealizirovanny m i legko analiziruemym kriticheskim opytom. Integral'nye fizicheskie dannye dlya rascheta reaktora polucheny v rezul'tate provedennykh na reaktornykh sistemakh kriticheskikh ili nekriticheskikh izmerenij, razlichnykh velichin reaktornoj fiziki, imeyushchikh prakticheskoe j teoreticheskoe znacheniya, ili to ili drugoe znachenie. Oni kharakterizuyut i pozvolyayut ponyat' sistemu. Dany izmereniya kriticheskoj massy, koehffitsienta formy aktivnoj zony, koehffitsientov detektorov, spektrov nejtronov, opytov s zamenoj materiala, otrazhatel'noj dobavki, vremeni zhizni nejtronov, Rossi-{alpha} i podobnykh kharakteristik i velichin. V doklade rassmatrivayuts ya ehti dannye i opisyvayutsya oblasti ikh primeneniya. Pokazano, chto sushchestvuyut ogranicheniya i v ehksperimental'ny kh i v analiticheskikh rezultatakh pri analizakh spektra i kritichnosti sistemy. Dany nametki budushchikh ehksperimental'ny kh i analiticheskikh issledovanij. Ehti issledovaniya pomogut umen'shit' razryv mezhdu teoriej i opytom dlya 'izvestnykh' sistem. Namechayutsya takzhe issledovaniya po 'podkrepleniyu' dannykh fiziki krupnykh ehnergeticheskikh reaktorov-razmnozhitelej na bystrykh nejtronakh. (author)

  19. Radiation-pulse transmission via a long cable without a preamplifier and/or a pulse transformer; Transmission d'impulsions de rayonnement par cable long sans l'adjonction d'un preamplificateur ou d'un transformateur d'impulsions; Peredacha impul'snykh izluchenij no kabelyu na dal'nie rasstoyaniya bez predvaritel'nogo usileniya i/ili bez preobrazovaniya impul'sov; Transmision de impulsos por cables de gran longitud sin preamplificador y/o transformador de impulsos

    Energy Technology Data Exchange (ETDEWEB)

    Miwa, H; Tohyama, T [Kobe Kogyo Corporation, Okubo, Akashi, Hyogo (Japan)

    1962-04-15

    kompleksnoe soprotivlenie usilitelya No. 2 budet sootvetstvovat' kharakteristike kabelya pri pomoshchi vklyuchennogo kompleksnogo i menyayushchegosya soprotivleniya. Takim obrazom, ustrojstvo vida No. 2 bylo v shirokoj mere prisposobleno k nashemu yadernomu pribornomu oborudovaniyu, kak naprimer k nejtronnomu izmeritelyu vlazhnosti pochvy (schetchik BF{sub 3}) analizatoru sostava pochvy (stsintillyatsionnyj spektrometr), tolshchinomeru snega (schetchik Gejgera-Myullera) i distantsionnym kontrol'nym dozimetricheskim priboram. Otsutstvie predvaritel'nykh usilitelej i preobrazovatelej impul'sov delaet vozmozhnym primenenie ehtikh detektorov na mestnosti v osobykh usloviyakh, kak naprimer, pri vysokikh ili nizkikh temperaturakh, bystrom potoke nejtronov (gamma-izluchenij) i t.d. Nalichie tol'ko odnogo koaksial'nogo kabelya uproshchaet rabotu detektorov na dal'nem rasstoyanii. Peredacha impul'sov po kabelyu na dal'nie rasstoyaniya svyshe 500 metrov ne povliyala na stsintillyatsionnuyu spektroskopiyu gamma-izluchenij. (author)

  20. A Comparison of Radioisotope Methods for River Flow Measurement; Comparaison de methodes radioisotopiques de mesure du debit des cours d'eau; Sravnenie radioizotopnykh metodov izmereniya rechnykh stokov; Comparacion de los metodos radioisotopicos para medir el caudal de los rios

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, C. G.; Smith, D. B. [Wantage Research Laboratory Atomic Energy Research Establishment Wantage, Berks (United Kingdom)

    1963-08-15

    indikatornykh metodov izmereniya stoka rasstoyanie mezhdu tochkoj izmereniya i tochkoj vvedeniya indikatora dolzhno byt' dostatochno bol'shim, poskol'ku dolzhno proizojti polnoe smeshivanie. V to zhe vremya ehto rasstoyanie ne dolzhno byt' slishkom bol'shim, chtoby izbezhat' znachitel'noj prodol'noj dispersii ili poteri indikatora v rezul'tate pogloshcheniya ego dnom reki. Dispersiya zavisit ot gidravlicheskikh kharakteristik stoka, i ona kharakterna dlya ehtogo metoda. Pogloshchenie zavisit ot vybora indikatora i ot geologicheskoj prirody dna reki. Imenno s ehtoj tochki zreniya N{sup 3} yavlyaetsya ideal'nym indikatorom, poskol'ku on ne pogloshchaetsya. Odnako ego trudno izmeryat', i ego prokhozhdenie v reke ne mozhet byt' proslezheno neposredstvenno. Drugie indikatory bolee udobny, no oni mogut pogloshchat'sya. Stepen' pogloshcheniya Na{sup 24},Br{sup 82} i R{sup 32} v vide NaHC0{sub 3}, NH{sub 4}Br i NaN{sub 2}R0{sub 4} izuchalas' putem sravneniya dannykh izmerenij v neskol'kikh tochkakh vniz po techeniyu o obshchej tochki vvedeniya i putem vvedeniya mechennoj tritiem vody (NTO) odnovremenno s vvedeniem kazhdogo iz trekh indikatorov. Ustanovleno, chto R{sup 32}, kotoryj, kak ozhidalos', budet sil'no pogloshchat'sya khimicheski, yavlyaetsya na samom dele neprigodnym v kachestve indikatora bez nositelya dlya izmereniya rechnykh stokov, khotya s nositelem oshibka izmerenij znachitel'no men'she. Na{sup 24} i Br{sup 82} ne proyavlyayut priznakov pogloshcheniya ikh na znachitel'nykh rasstoyaniyakh, bol'she chem neobkhodimo dlya gorizontal'nogo smeshivaniya; na rasstoyanii svyshe 660 m v reke s samym medlennym techeniem obnaruzhivayutsya priznaki ischeznoveniya Na{sup 24}. Predstavleny nekotorye nablyudeniya otnositel'no stepeni gorizontal'noj i prodol'noj dispersii, kotoraya otrazhaetsya na obshchem primenenii indikatornykh metodov dlya izmerenij rechnykh stokov. Delaetsya vyvod, chto vse tri metoda mogut uspeshno primenyat'sya. Odnako metod nepreryvnogo otbora prob v konechnom

  1. Carbon-14 and Hydrogen-3 Measurement by Means of a Liquid Scintillation Spectrometer: Colour Quenching; Mesure du Carbone-14 et du Tritium a l'Aide d'un Spectrometre a Scintillateurliquide: Extinction Chromatique; Izmerenie soderzhaniya Ugleroda-14 i Vodoroda-3 s pomoshch'yu zhidkostnogo stsintillyatsionnogo spektrometra. oslablenie tsveta; Influencia de la Extincion Cromatica en la Medicion del Carbono-14 y del Hidrogeno-3 por Espectrometria del Centelleo Liquido

    Energy Technology Data Exchange (ETDEWEB)

    Iwakura, T.; Kasida, Y. [National Institute of Radiological Sciences, Chiba (Japan)

    1965-10-15

    TRI-CARB, model' 314 EH2. Nastrojka diskriminatora sostavljala 100-1000 delenij dlja krasnogo kanala i 186-1000 delenij dlja zelenogo. Vysokoe naprjazhenie, primenjaemoe dlja fotoumnozhitelja, vybrali dlja togo, chtoby obespechit' uravnoveshennuju tochechnuju rabotu v krasnom kanale pri neoslablennom obrazce. Koncentracija krasok byla izuchena po stepeni oslablenija. Vsledstvie harakternosti dliny voln sveta, ishodjashhego iz scintilljatornyh sistem i reakcii fotoumnozhitelej (reakcija S-I), predpolagalos', chto krasno-zheltyj rastvor, kotoryj imeet maksimum pogloshhenija pri 400 - 500 mmk budet imet' samyj bol'shoj jeffekt oslablenija. Chtoby ocenit' obshhee oslablenie cveta dlja opredelenija kojefficienta obshhego pogloshhenija ispol'zovalos' sledujushhee otnoshenie: A = ({Sigma}A{sub i}W{sub i})/({Sigma}W{sub i}), gde W{sub i} - otnositel'naja chuvstvitel'nost' fotoumnozhitelja k svetu s dlinoj volny i mmk; a A{sub i} - pogloshhenie sveta s dlinoj volny i mmk v predelah ispol'zuemogo spektra. Obshhee pogloshhenie bylo rasschitano dlja kazhdogo intervala v 40 mmk, naprimer dlja 360 - 400, 400 - 440 i t.d. do 520 - 560 mmk. Jekvivalentnoe pogloshhenie 1/A v zavisimosti ot jeffektivnosti scheta pokazyvaet linejnuju zavisimost' v shirokom diapazone jeffektivnosti scheta. Krivye zavisimosti kojefficienta diskriminatora ot jeffektivnosti scheta pokazyvajut, chto, kogda oslablenie cveta stanovitsja sil'nym, krivaja oslablenija cveta otdeljaetsja ot krivoj himicheskogo oslablenija pri schete ugleroda-14. S drugoj storony, proizvedennye pri schete vodoroda-3 analogichnye izmerenija ne pokazyvajut razdelenija dvuh krivyh oslablenija. (author)

  2. Studies on the Relationship of Organ Size and Scanning Picture; Etudes sur la Relation entre les Dimensions de l'Organe et le Scintigramme; Izuchenie sootvetstviya razmera organa i izobrazheniya ego na skennogramme; Estudios sobre la Relacion entre las Dimensiones de un Organo y el Centelleograma

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, R.; Fischer, J. [Institute for Clinical Radiology and I. Medical Clinic and Policlinic, University of Mainz, Federal Republic of Germany (Germany)

    1964-10-15

    metod opredelenija razmera pecheni s ispol'zovaniem razlichnyh porogov propuskanija. Dlja takih organov, kak shhitovidnaja zh eleza i pochki, predstavljaet interes ustanovit' chetkoe sootvetstvie s rentgenov skim snimkom ili rezul'tatami pal'pacii i akkumulirujushhej i neakkumulirujushhej tkan'ju. Vazhno tochno ustanovit' razmer jet o g o sootnoshenija, naprimer, pri scintigrafii krovjanyh depo s erdechnososudistoj sistemy. Chto k asaet sja takogo organa, kak s elezenka, razmery kotoroj mogut bystro menjat'sja pri razlichnyh zabolevanijah, to tochnost' scintigraficheskogo izobrazhenija imeet reshajushhee znachenie. S jetoj cel'ju byla provedena celaja serija issledovanij na fantome dlja opredelenija tochnosti scintigraficheskogo izobrazhenija pri razlichnyh uslovijah. Ispol'zovavshiesja modeli byli izgotovleny iz plastika i mogli zapolnjat'sja radioaktivnymi rastvorami. Issledovanija provodilis' na otkrytom vozduheipod vodoj; izuchalis' rezul' taty izmerenija u koncentracii radioizotopov, a takzhe takie parametry, kak rasstojanie ot ob{sup e}kta do kollimatora, granica propuskanija, kontrastnoe uvelichenie, skorost' razvertki, prolet kanalov spektrometra i glubina vodnoj absorbirujushhej massy vokrug organa. Ispol'zovalsja ''Magnaskenner'' firmy Pikker s dvumja razlichnymi kollimatorami, kollimator s 19 jachejkami i kollimator s tonkoj fokusirovkoj, imejushhej 31 jachejku. Poslednij ispol'zovalsja tol'ko dlja shhitovidnoj zhelezy. Rezul'taty pokazali, chto tochnost' izobrazhenija pri ispol'zovanii kollimatora s tochnoj fokusirovkoj zavisit ot izmenenij rasstojanija ot kollimatorad o ob{sup e}kta. S drugoj storony, pri ispol'zovanii kollimatora s 19 jachejkami rasstojanie ne imeet bol'shogo zn a chenija. Kogda sverjajutsja razmery, luchshe v sego rabotat' pri odnoj i toj zhe maksimal'noj cha st o tepovtorenija impul'sov, naskol'ko jeto vo zm ozhno. Pri sobljudenii fiksirovannogo sootnoshenija mezhdu shirinoj kanala spektrometra, porogom propuskanija, chastotoj impul

  3. Data Evaluation Problems in the Pulsed Neutron Source Method; Problemes d'Evaluation des Donnees dans les Applications de la Methode de la Source Pulsee; Problemy otsenki dannykh pri primenenii metoda istochnika impul'snykh nejtronov; Problemas de Evaluacion de Datos en el Metodo de la Fuente de Neutrones Pulsados

    Energy Technology Data Exchange (ETDEWEB)

    Pal, L.; Bod, L.; Szatmary, Z. [Central Research Institute for Physics, Hungarian Academy of Sciences, Budapest (Hungary)

    1965-08-15

    ' nadlezhashhuju tochnost'. Opredeljaetsja takzhe vlijanie vremeni otstava- nija detektora nejtronov i usilitel'noj shemy na velichinu konstanty raspada i dokazyvaetsja, chto vremenem otstavanija mozhno prenebrech', es [i(t) {tau}]{sup 2} << 1, gde i/t/d t vyrazhaet chislo nejtronov, obnaruzhennyh za promezhutok vremeni (t, t + dt) , a {tau} oboznachaet vremja otstavanija. Dlja ocenki konstanty raspada primenjaetsja metod maksimal'noj verojatnosti. Dlja odno- znachnogo opredelenija funkcii verojatnosti byl vybran mnogokanal'nyj analizator, kotoryj rabotal takim obrazom, chto dlja kazhdogo cikla analiza i dlja kazhdogo kanala zanosilos' v pamjat' tol'ko odno zaregistrirovannoe sobytie.' Obnaruzheno, chto vvedenie v funkciju ve- rojatnosti parametra, harakterizujushhego fon, imeet pervostepennoe znachenie. Parametry funkcii maksimal'noj verojatnosti byli opredeleny na schetno-reshajushhem ustrojstve po N'jutonovskomu metodu povtorenij. Esli ne prinimat' v raschet fonovye shumy, to jeto mozhet vyzvat' javnoe, bolee sil'noe garmonicheskoe zagrjaznenie, a ono v svoju ochered', mozhet byt' prinjato za javnyj fon. Po- jetomu predstavljaetsja osobenno vazhnym opredelit' harakterizujushhij fon parametr nepo- sredstvenno iz dannyh raspada, poluchennyh dlja raznyh vremen zamedlenija. Diffuzionnye parametry podschityvali po metodu vzveshennyh naimen'shih kvadratov s ispol'zovaniem konstant raspada naimen'shego standartnogo otklonenija, opredelennyh po funkcii maksimal'noj verojatnosti. Tak kak dlja issleduemyh materialov ne byli iz- vestny velichiny srednego svobodnogo puti perenosa, to dlja opredelenija srednego svobod- nogo puti perenosa byla vyrabotana bystro konvergirujushhaja povtornaja formula. Ispol'- zovanie schetno-reshajushhego ustrojstva dalo vozmozhnost' opredelit' kojefficienty konstanty raspada porjadka V' i dazhe bolee vysokih porjadkov. Diffuzionnye parametry issleduemyh gidrogennyh materialov byli podschitany s pomoshh'ju osazhdenija po metodu Radkovskogo na osnovanii