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Riou, J.C.; Spinelli, J.C.
Commissariat a l'Energie Atomique - CEA, Service des Experiences Critiques (France)1960
Commissariat a l'Energie Atomique - CEA, Service des Experiences Critiques (France)1960
AbstractAbstract
[en] This report presents the algebraic equation written in spherical geometry with an infinite reflector for the calculation and comparison of critical masses of a pile as a function of the vessel nature and thickness, and of radius values. It presents the iterative process adopted for the calculation, and discusses some peculiarities of this calculation. It reports matrix critical calculations, and calculations performed by using the Hassit method
Original Title
Methodes de calcul pour les conditions critiques d'une pile homogene (Proserpine)
Primary Subject
Secondary Subject
Source
10 Jun 1960; 19 p; 4 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/
Record Type
Miscellaneous
Report Number
Country of publication
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AbstractAbstract
[en] 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
[sr]
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 fluksaOriginal Title
Program kriticnih eksperimenata i merenja na reaktoru RA
Primary Subject
Source
14 Apr 1960; 8 p; RA-B-R--6-P1-59; Also available from the Institute of nuclear sciences Vinca; This record replaces 37050233
Record Type
Miscellaneous
Report Number
Country of publication
CONTROL ELEMENTS, DEUTERIUM COMPOUNDS, ENRICHED URANIUM REACTORS, FUEL ELEMENTS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HYDROGEN COMPOUNDS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, OXYGEN COMPOUNDS, PLANNING, RADIATION FLUX, REACTIVITY COEFFICIENTS, REACTOR CHANNELS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SIZE, TANK TYPE REACTORS, THERMAL REACTORS, WATER
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The buckling in the bare heavy water natural uranium critical assembly was determined by measuring the thermal neutron flux distribution. The obtained value for the critical buckling at the temperature of 20 deg C is: B2 = (8.516 ± 0.02) m-2. The above error is a statistical one, obtained from several series of measurements. The possible systematic error was estimated as 0.1 m-2. (author)
Primary Subject
Source
Bulletin of the Institute of Nuclear Sciences 'Boris Kidric'; v. 10(195); Mar 1960; 6 p; Institute of Nuclear Sciences 'Boris Kidric'; Beograd-Vinca (Yugoslavia); Also available from the Institute of Nuclear Sciences Vinca; 7 refs., 3 figs.
Record Type
Miscellaneous
Literature Type
Numerical Data
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Country of publication
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INIS IssueINIS Issue
Banchereau, A.; Berthier, P.; Genthon, J.P.; Gourdon, C.; Lattes, R.; Martelly, J.; Mazancourt, R. de; Portes, L.; Sagot, M.; Schmitt, A.P.; Tanguy, P.; Teste du Bailler, A.; Veyssiere, A.
CEA Saclay, 91 - Gif-sur-Yvette (France)1957
CEA Saclay, 91 - Gif-sur-Yvette (France)1957
AbstractAbstract
[en] An important part of the experiments carried out on the reactor G1 during a period of shut-down has consisted in determinations of critical sizes, and measurements of flux distribution by irradiations of detectors. This report deals with the following points: 1- Critical sizes of the flat pile, the long pile and the uranium-thorium pile. 2- Flux charts of the same piles, and study of an exponential experiment. 3- Determination of the slit effect. 4- Calculation of the anisotropy of the lattice. 5- Description of the experimental apparatus of the irradiation measurements. (author)
[fr]
Une part importante des experiences a froid effectuees sur le reacteur G1 a consiste en des determinations de tailles critiques et des mesures de distributions de flux par irradiations de detecteurs. Le present rapport traite les points suivants: 1- Tailles critiques de la pile plate, de la pile longue, de la pile a uranium-thorium. 2 - Cartes de flux des memes piles et etude d'une experience exponentielle. 3 - Determination de l'effet de fente. 4 - Calcul de l'anisotropie du reseau. 5 - Description de l'appareillage experimental des mesures d'irradiations. (auteur)Original Title
Tailles critiques et cartes de flux a froid
Primary Subject
Source
1957; 28 p; 7 refs.
Record Type
Report
Report Number
Country of publication
ACTINIDE ALLOYS, AIR COOLED REACTORS, ALLOYS, DIMENSIONS, DISTRIBUTION, GAS COOLED REACTORS, GCR TYPE REACTORS, GRAPHITE MODERATED REACTORS, KINETICS, LENGTH, MATHEMATICAL OPERATORS, MEASURING INSTRUMENTS, NEUTRON DETECTORS, PHOTOTUBES, PLUTONIUM PRODUCTION REACTORS, PRODUCTION REACTORS, RADIATION DETECTORS, RADIATION FLUX, REACTOR COMPONENTS, REACTORS, SHUTDOWN, SIZE, THERMAL REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Absalom, R.M.; Barclay, F.R.; Cameron, I.R.; Della Loggia, V.E.; Hage, W.; Kinchin, G.H.; Sanders, J.E.; Tiren, L.I.; Wilson, D.J.
United Kingdom Atomic Energy Authority, Reactor Group, Winfrith (United Kingdom)1960
United Kingdom Atomic Energy Authority, Reactor Group, Winfrith (United Kingdom)1960
AbstractAbstract
[en] The loading to criticality of the first core of the zero energy reactor ZENITH, and the results of the subsequent experimental programme are described. The composition of the reactor core corresponds to graphite: U235 and Th232: U235 atomic ratios of 3843 and 9.51 respectively. (author)
Primary Subject
Source
Dec 1960; 90 p; Also available from H.M. Stationery Office; Country of input: International Atomic Energy Agency (IAEA); 16 refs, 28 figs, 16 tabs
Record Type
Report
Literature Type
Software
Report Number
Country of publication
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, CARBON, ELEMENTS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, HEAVY NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MINERALS, MINUTES LIVING RADIOISOTOPES, NONMETALS, NUCLEI, RADIOISOTOPES, REACTOR COMPONENTS, SPONTANEOUS FISSION RADIOISOTOPES, THORIUM ISOTOPES, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Tanguy, P.
CEA Saclay, 91 - Gif-sur-Yvette (France)1957
CEA Saclay, 91 - Gif-sur-Yvette (France)1957
AbstractAbstract
[en] In this report are described and interpreted some experiments, carried out in the pile G1 during a period of shut-down, which have made it possible to measure the variation of the material Laplacian of the lattice with the radius of the uranium bar. The variation of the reactivity of the pile is measured when an increasing number of fuel elements are progressively replaced in the central region by fuel elements of greater diameter; it is shown that, starting from measurements based on less than ten per cent of the total number of elements, the variation of reactivity corresponding to the replacement of all the elements can be determined; it is then easy to deduce the variations of the Laplacian. Results: the variations of the Laplacian with the uranium rod diameter are 0 (d. 26 mm), +0.065 ± 0.004 m-2 (d. 28 mm) and +0.080 ± 0.008 m-2 (d. 32 mm). (author)
[fr]
Dans ce rapport sont decrites et interpretees des experiences realisees sur la pile G1 'froide', experiences qui ont permis de mesurer la variation du Laplacien matiere du reseau avec le rayon du barreau d'uranium. On mesure la variation de reactivite de la pile lorsqu'on remplace progressivement dans la region centrale un nombre croissant de cartouches par des cartouches de plus gros diametre; on montre qu'a partir de mesures portant sur moins de dix pour cent du nombre total de cartouches, on peut determiner la variation de reactivite qui correspondrait au remplacement de toutes les cartouches; il est facile d'en deduire les variations du Laplacien. Resultats: les variations du Laplacien en fonction du diametre du barreau d'uranium sont: 0 (d. 26 mm), +0.065 ± 0.004 m-2 (d. 28 mm) and +0.080 ± 0.008 m-2 (d. 32 mm). (auteur)Original Title
Variation du laplacien matiere de G1 avec le rayon du barreau d'uranium
Primary Subject
Secondary Subject
Source
1957; 20 p
Record Type
Report
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Country of publication
ACTINIDES, AIR COOLED REACTORS, BARYONS, CONFIGURATION, ELEMENTARY PARTICLES, ELEMENTS, EQUATIONS, FERMIONS, FUEL ELEMENTS, GAS COOLED REACTORS, GCR TYPE REACTORS, GRAPHITE MODERATED REACTORS, HADRONS, MATHEMATICAL OPERATORS, MATHEMATICS, METALS, NEUTRONS, NUCLEONS, PLUTONIUM PRODUCTION REACTORS, PRODUCTION REACTORS, RADIATION FLUX, REACTOR CHANNELS, REACTOR COMPONENTS, REACTORS, SHUTDOWN, SIZE, THERMAL REACTORS, TRANSPORT THEORY
Reference NumberReference Number
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Sanchez del Rio, C.; Santiago, S.; Verdaguer, F.
Junta de Energia Nuclear (JEN), Madrid (Spain)1960
Junta de Energia Nuclear (JEN), Madrid (Spain)1960
AbstractAbstract
[en] A resistor network is described which can be used to solve the partial differential equations for the scalar potential and for the only component of the vector potential in problems with cylindrical symmetry. To calculate the values of the resistors a general method is presented valid for any equation which can be solved by the resistor network analogy. (Author) 2 refs
Primary Subject
Source
1960; 34 p
Record Type
Report
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Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
Bernot, J.; Koechlin, J.C.; Portes, L.; Teste du Bailler, A.
CEA Saclay, 91 - Gif-sur-Yvette (France)1957
CEA Saclay, 91 - Gif-sur-Yvette (France)1957
AbstractAbstract
[en] The various methods used during the physical study of the reactor G1 to determine the variations of the effective multiplication factor consecutive to a given change in the geometry of the multiplying medium, are presented and discussed. The comparison of the results obtained by these various methods has allowed their validity to be tested and precise conditions of use to be given. In the first part are presented the principles used and their ranges of validity. In the second part the experimental results are given, together with some indications on their comparison with theoretical estimations. (author)
[fr]
Nous exposons et discutons diverses methodes utilisees, lors de l'etude physique du reacteur G1, pour determiner les variations du facteur de multiplication effectif consecutives a un changement donne dans la geometrie du milieu multiplicateur. La comparaison des resultats obtenus par diverses methodes nous a permis de tester leur validite et d'en preciser les conditions d'emploi. Dans une premiere partie, nous exposons les principes utilises et leurs domaines de validite. Dans une seconde partie nous donnons les resultats experimentaux obtenus avec quelques indications sur leur comparaison avec les estimations theoriques. (auteur)Original Title
Mesures de reactivite sur reacteur G1
Primary Subject
Secondary Subject
Source
1957; 18 p; 20 refs.
Record Type
Report
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Country of publication
ABSOLUTE COUNTING, CONFIGURATION CONTROL, CONTROL ELEMENTS, CRITICAL SIZE, CRITICALITY, DELAYED NEUTRON FRACTION, EXTRAPOLATION LENGTH, FERMI AGE THEORY, FUEL PLATES, FUEL RODS, INHOUR EQUATION, MULTIPLICATION FACTORS, NEUTRON ABSORBERS, NEUTRON FLUX, PERTURBATION THEORY, REACTIVITY, REACTOR KINETICS, REACTOR LATTICE PARAMETERS
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INIS IssueINIS Issue
AbstractAbstract
[en] The results of two months' experiments, carried out at low power following the first divergence (4. July 1957) are presented. These experiments dealt with the following points: comparison of experimental and calculated values of the critical size; effects due to the introduction of absorbing materials into the principal experimental facilities, flux distribution measurements especially in these facilities, calibration of safety, control and compensating rods, determination of the average life of the neutrons. (author)
[fr]
On expose les resultats relatifs a deux mois d'experiences effectuees a basse puissance a la suite de la premiere divergence (4 juillet 1957). Ces experiences ont porte sur les points suivants: comparaison des tailles critiques experimentales et calculees, effets dus a l'introduction de corps absorbants dans les principaux dispositifs experimentaux, mesures des distributions de flux particulierement dans ces dispositifs, etalonnage des barres de securite, de reglage et de compensation, determination de la vie moyenne des neutrons. (auteur)Original Title
Etude experimentale de la pile EL3
Primary Subject
Source
1958; 67 p; 5 refs.
Record Type
Report
Report Number
Country of publication
ACTIVATION DETECTORS, BF3 COUNTERS, COINCIDENCE METHODS, CONFIGURATION CONTROL, CONTROL ROD WORTHS, CRITICAL SIZE, CRITICALITY, EL-3 REACTOR, FISSION FOIL DETECTORS, LIFETIME, MULTIPLICATION FACTORS, NEUTRON FLUX, PRESSURE DROP, REACTIVITY INSERTIONS, REACTOR KINETICS, REACTOR LATTICES, REACTOR SAFETY, SLIGHTLY ENRICHED URANIUM, SPATIAL DISTRIBUTION
ACTINIDES, CONTROL, COUNTING TECHNIQUES, DIMENSIONLESS NUMBERS, DISTRIBUTION, ELEMENTS, ENRICHED URANIUM, ENRICHED URANIUM REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, KINETICS, MATERIALS, MATERIALS TESTING REACTORS, MEASURING INSTRUMENTS, METALS, NEUTRON DETECTORS, PROPORTIONAL COUNTERS, RADIATION DETECTORS, RADIATION FLUX, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, SIZE, TANK TYPE REACTORS, URANIUM
Reference NumberReference Number
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INIS IssueINIS Issue
Jarvis, R.G.
Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)1960
Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)1960
AbstractAbstract
[en] This report contains calculations on the criticality of assemblies of NRX fuel elements in light water. The elements are dealt with in three sections, 'X rods' of natural uranium, enriched elements of U235/A1 alloy and enriched elements of Pu/Al alloy. Values of k∞ and B2 are provided for two fuel concentrations for each of the two enriched types and for a range of irradiations of the X rods. The calculations for the X rods provide maximum and minimum values of k∞. The maximum values for some lattices are a few per cent above unity. Unfortunately, the present experimental evidence does not prove that it is impossible to achieve values of k∞ greater than unity in lattices of natural uranium in light water. Hence for safety predictions maximum values have been used. The resulting restrictions are not very severe. It is possible to make critical assemblies of the enriched elements, Part (5) contains a set of recommended minimum spacings such that elements of all kinds may safely be mixed in a stack together. There are also predictions of the minimum critical numbers of complete elements or elements cut into slugs. (author)
Primary Subject
Source
Mar 1960; 64 p; CRRP--914; 5 refs., 6 figs.
Record Type
Report
Report Number
Country of publication
ACTINIDE NUCLEI, ACTINIDES, ALPHA DECAY RADIOISOTOPES, ELEMENTS, EVEN-ODD NUCLEI, HEAVY NUCLEI, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, INTERNAL CONVERSION RADIOISOTOPES, IRRADIATION REACTORS, ISOMERIC TRANSITION ISOTOPES, ISOTOPE ENRICHED MATERIALS, ISOTOPE PRODUCTION REACTORS, ISOTOPES, MATERIALS, MATERIALS TESTING REACTORS, METALS, MINUTES LIVING RADIOISOTOPES, NATURAL URANIUM REACTORS, NUCLEI, POWER REACTORS, PRESSURE TUBE REACTORS, RADIOISOTOPES, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, TANK TYPE REACTORS, THERMAL REACTORS, URANIUM, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
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INIS IssueINIS Issue
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