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AbstractAbstract
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Ceskoslovenska Akademie Ved, Rez. Ustav Jaderneho Vyzkumu; p. 12; Oct 1971; Colloquium on reactor physics; Marianske Lazne, Czechoslovakia; 30 Aug 1971; Available in abstract form only.
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AbstractAbstract
[en] The fuel element assembly (FA) of fast reactor comprising fuel elements with enriched fuel and fuel elements with fossil material is described. With the purpose of increasing the power rating without deterioration of coolant temperature parameters at the core outlet in each FA elementary cell there are fuel elements of both types
Original Title
Toplivnaya sborka bystrogo reaktora
Primary Subject
Source
16 Feb 1981; 2 p; SU PATENT DOCUMENT 1003676/A/; 1 ref.
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Patent
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Bartosek, V.
Colloquium on reactor physics, held in Marianske Lazne, Czechoslovakia, from August 30 to September 4, 19711971
Colloquium on reactor physics, held in Marianske Lazne, Czechoslovakia, from August 30 to September 4, 19711971
AbstractAbstract
No abstract available
Primary Subject
Source
Ceskoslovenska Akademie Ved, Rez. Ustav Jaderneho Vyzkumu; p. 8; Oct 1971; Colloquium on reactor physics; Marianske Lazne, Czechoslovakia; 30 Aug 1971; Available in abstract form only.
Record Type
Report
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Reference NumberReference Number
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AbstractAbstract
No abstract available
Primary Subject
Source
21 Nov 1973; 3 p; GB PATENT DOCUMENT 1338462/B/
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Patent
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Raven, L.F.; Naylor, J.E.; Crossley, B.
Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] The construction of the cell grid provides a large number of tubular clamps or twin clamps, which are suitable for accommodating fuel rods or sprinkler pipes. They consist of a closed metal strip, which is divided into two similar openings by a bridge piece. Bowspring or leaf springs (Nimonic from RTH) are used to fix the rods and pipes, the former are supported on bridge supports. There is always a pair of coplanar hollows or bumps in the surface of the metal strip or the clamp opposite the springs. (RW)
[de]
Der Zellengitteraufbau sieht eine Vielzahl roehrenfoermiger Zwingen bzw. Zwillingszwingen auf die fuer die Aufnahme von Brennstaeben und Sprinklerrohren geeignet sind. Sie bestehen aus einem geschlossenen Metallstreifen, der von einem Brueckenstueck in zwei aehnliche Oeffnungen geteilt wird. Zur Fixierung der Staebe und Rohre dienen Bogen- oder Blattfedern (Nimonic von RTM), die auf den Brueckenstuetzen aufgesteckt sind, und jeweils ein Paar koplanarer Vertiefungen oder Erhoehungen in der den Federn gegenueberliegenden Flaeche des Metallstreifens bzw. der Zwinge. (RW)Original Title
Zellengitter
Primary Subject
Source
13 Jul 1978; 13 p; DE PATENT DOCUMENT 2801100/A/
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Patent
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AbstractAbstract
No abstract available
Original Title
Lokal'nyj geterogennyj raschet reaktora
Primary Subject
Secondary Subject
Source
Aug 1972; 8 p
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Davis, R.S.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1977
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1977
AbstractAbstract
[en] CONIFERS is a neutronics code for nuclear reactors whose fuel is in channels that are separated from each other by several neutron mean-free-path lengths of moderator. It can treat accurately situations in which the usual homogenized-cell diffusion equation becomes inaccurate, but is more economical than other advanced methods such as response-matrix and source-sink formalisms. CONIFERS uses exact solutions of the neutron diffusion equation within each cell. It allows for the breakdown of this equation near a channel by means of data that almost any cell code can supply. It uses the results of these cell analyses in a reactor equations set that is as readily solvable as the familiar finite-difference equations set. CONIFERS can model almost any configuration of channels and other structures in two or three dimensions. It can use any number of energy groups and any reactivity scales, including scales based on control operations. It is also flexible from a programming point of view, and has convenient input and output provisions. (author)
Primary Subject
Source
Apr 1977; 116 p
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Chomat, Laure; Bouyer, Frédéric; Gin, Stéphane; Roux, Stéphane, E-mail: frederic.bouyer@cea.fr2012
AbstractAbstract
[en] The kinetics of glass alteration is studied in a reactor cell containing parallel glass plates with a small gap, representing an ideal crack geometry. The calibrated aperture of the crack is varied from a few tens to a few hundred micrometers. The glass coupons are immersed in a highly alkaline solution to obtain fast alteration. Although the cell is closed and isothermal, it is observed that vertical or horizontal configurations lead to very different alteration gel thickness profiles. This effect results from gravity-driven flow taking place in the vertical geometry due to glass leaching as opposed to essentially diffusive transport in the horizontal case. The advection velocity is estimated from a one-dimensional model of the coupled reaction/transport mechanism, based on a zero or first order reaction. The coupling between reaction and transport has a clear influence on the apparent alteration kinetics, a phenomenon generally ignored.
Primary Subject
Source
S0022-3115(12)00090-6; Available from http://dx.doi.org/10.1016/j.jnucmat.2012.02.021; Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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AbstractAbstract
[en] Some imprecisions are pointed out in the derivation by a previous author of a correction for the neutron flux in a heterogeneous lattice cell. In particular, the equation which is basic to the mathematical formulation does not properly take into account the lethargy and energy variables. It is shown that this and other errors in the derivation lead to an overestimation of the proposed correction. (UK)
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AbstractAbstract
[en] The diffusion equation for the fluidized bed nuclear reactor concept (FBNR) is derived. It is shown that existing neutronic codes can be applied for the cell calculation. (orig.)
[de]
Die Diffusionsgleichung fuer das Konzept FBNR eines Wirbelschichtreaktors wird hergeleitet. Es wird gezeigt, dass die neutronenphysikalischen Berechnungen fuer dieses Konzept mit bereits vorhandenen Rechencodes durchfuehrbar sind. (orig.)Primary Subject
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