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AbstractAbstract
[en] A new method is described for localizing failures on the nuclear fuel elements during reactor operation. The fuel rods contain a mixture of ''N'' different pairs of rare gas isotopes. The mixture is composed in a way that it is possible to localize ''I'' failures which occur simultaneously. This is achieved if the points which signify each single fuel element within the N-dimensional isotope-room are chosen in a way that with each point newly to be chosen in a way that with each point newly to be chosen all linear combinations of ''I'' points of the multitude of points now existing coincide with a minimum of linear combinations of ''I'' other points of the same multitude of points. The cover gas is continuously analysed with regard to the appearance of such rare gase isotopes. (P.K.)
Original Title
Verfahren zur Lokalisierung von Defekten an Brennstaeben von Reaktorbrennelementen
Primary Subject
Secondary Subject
Source
15 Mar 1977; 6 p; AT PATENT DOCUMENT 340013/B/; available from Oesterreichisches Patentamt, Kohlmarkt 8-10, A-1010 Vienna, Austria
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Benuzzi, A.; Delaval, M.; Yerkees, A.
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. E1983
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. E1983
AbstractAbstract
[en] The COVA (COde VAlidation) programme undertaken by UKAEA and JRC-Ispra consists of a series of scale model explosive experiments performed to provide data for the validation of dynamic fluid/structure codes to be used eventually for fast reactor containment studies. In the test series loop and pool type reactor designs are simulated by two length-to-diameter ratios represented by long and short tanks, respectively. The programme has been completed and the analysis of the results reveals that containment codes generally give sufficiently accurate predictions of the main phenomena involved such as pressure wave propagation and fluid motion. Nevertheless, there are two areas, namely roof loadings and structural deformations, where all the codes used consistently give not negligible discrepancies with the experimental results. In particular the trend observed is a general underprediction of hoop strains and an overprediction of roof impulses for tests using long tanks. This paper deals with the roof loading overpredictions, the problem of the strain underpredictions being treated in a complementary paper. It has to be noted that the measured pressure records on the roof for long and short tanks are generally quite different in character. Long tank records tend to be smooth and it is thought that, due to the cover gas, little or no contact of the fluid with the roof occurs, this observation is confirmed by the computed results. In contrast, the short tank records change rapidly and the fluid contact with the roof takes place except for the extreme outer region of the roof. In order to reduce the complexity of the reasons for the overpredicted roof loadings, results from calculations of simple COVA tests such as IT6, a thick overstrong bare cylindrical vessel, are mainly considered in this paper. (orig.)
Primary Subject
Source
Commission of the European Communities, Luxembourg; Argonne National Lab., IL (USA); 751 p; ISBN 0444 86694 9;
; 1983; p. 35-42; North-Holland; Amsterdam (Netherlands); 7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7); Chicago, IL (USA); 22-26 Aug 1983

Record Type
Book
Literature Type
Conference
Country of publication
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Furkert, W.; Schulze, G.; Schmidt, R.
Zentralinstitut fuer Kernforschung, Rossendorf bei Dresden (German Democratic Republic)1979
Zentralinstitut fuer Kernforschung, Rossendorf bei Dresden (German Democratic Republic)1979
AbstractAbstract
[en] A system of standard components is shown which can used to produce protective gas chambers in module principle of construction. (author)
Original Title
Handschuhboxen
Primary Subject
Source
Jul 1979; 20 p
Record Type
Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Sato, Masuo; Makishima, Kenji; Ito, Takero.
Toshiba Corp., Kawasaki, Kanagawa (Japan)1978
Toshiba Corp., Kawasaki, Kanagawa (Japan)1978
AbstractAbstract
[en] Purpose: To provide the subject device wherein a follow-up control rendering the difference between the pressure of freeze seal backup gas and that of reactor vessel cover gas into a predetermined value is preformed, thereby to lower the height of the gutter of a rotary plug freeze seal, to improve the real function and to facilitate the manufacture of the seal gutter. Constitution: A signal generated from a pressure converter for detecting the pressure of reactor cover gas is supplied as input to an adjustment station for reading a signal generated from a volumeric tank gas pressure converter, where a control command is issued on the basis of the constant of PID most adapted for the response of the control system so that the differential pressure becomes constant. This output signal is converted into a signal for actuating a pressure control valve by V/I converter and I/P converter, and actuates an argon inlet valve and the like. (Yoshino, Y.)
Primary Subject
Source
20 Oct 1978; 5 p; JP PATENT DOCUMENT 53-120087/A/; Available from JAPATIC. Also available from INPADOC
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This patent describes a solid tag material for identifying a nuclear reactor component when placed within the component comprising: solid materials which contain at least one non-gaseous element that undergoes nuclear transmutation into one or more detectable, identifiable, and measurable tag gases on irradiation in a nuclear reactor. The tag gases generated are stable, are not fission products, and are generated in predetermined proportions different from their natural occurrence. Upon the failure of a component the tag gases can be detected in the reactor cover gas and the failed component identified according to the tag gas composition
Primary Subject
Source
14 Apr 1987; vp; US PATENT DOCUMENT 4,657,729/A/; U.S. Commissioner of Patents, Washington, D.C. 20231, USA, $.50
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
McCormick, N.J.
Department of Energy, Washington, DC (USA)1978
Department of Energy, Washington, DC (USA)1978
AbstractAbstract
[en] This invention provides a method for the identification of failed fuel assemblies in a nuclear reactor having a cover gas therein wherein multiple assembly failures can be distinguished from single assembly failures comprising the steps of incorporating a blended mixture of inert, non-radioactive gas tags in each fuel pin of each of the fuel assemblies, the blended mixture of inert, non-radioactive gas tags having gas tag ratios that are located, when plotted in a three dimensional rectilinear coordinate system, on a curved surface, and thereafter monitoring the cover gas for the presence of the blended mixture of the inert, non-radioactive gas tags. (author)
Primary Subject
Source
25 Apr 1978; 21 p; CA PATENT DOCUMENT 1030278/A/; Available from Commissioner of Patents, Ottawa-Hull, Canada K1A 0E1
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Buescher, E.; Eils, F.; Jansing, W.; Kirchner, G.
Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1979
Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1979
AbstractAbstract
[en] Several plate filters are piled on top of one another on a pipe where plate rim and base support each other and thus form collecting spaces. Each collecting space is connected to the pipe. The entire arrangement is in a container into which the Na-containing protective gas is introduced. The sintered metal plate filters retain the Na, and the gas disperses via the pipe which serves as a hanging device for the plate filters. (DG)
[de]
Mehrere Tellerfilter sind an einem Rohr uebereinandergestapelt angeordnet, wobei sich abwechselnd Tellerrand und Tellerboden gegeneinander abstuetzen und somit Sammelraeume gebildet werden. Jeder Sammelraum steht mit dem Rohr in Verbindung. Die gesamte Anordnung befindet sich in einem Gefaess, in das das Na-haltige Schutzgas eingebracht wird. Die Tellerfilter aus Sintermetall halten das Na zurueck und das Gas entweicht ueber das Rohr, welches als Aufhaengevorrichtung fuer die Tellerfilter dient. (DG)Original Title
Vorrichtung zur kontinuierlichen Abscheidung von Fluessigmetallen aus Gasen
Primary Subject
Source
20 Sep 1979; 3 p; DE PATENT DOCUMENT 2112891/B/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Poirier, J.C.; Mulcey, P.; Morel, P.; Vavasseur, C.
CEA, 75 - Paris (France)1989
CEA, 75 - Paris (France)1989
AbstractAbstract
[en] The system for dismantling an installation under a controlled atmosphere is made by a tool polluting the atmosphere, a gas blanket creating a continement zone around the tool, an extractor removing polluted gas from the zone, a purifier for the extracted gas and a controller regulating the flow of gas in the blanket and keeping the installation at constant pressure
[fr]
La presente invention a pour objet un systeme de demantelement d'installations presentes dans un local maintenu en depression grace a un systeme de ventilation. Apres avoir bouche l'entree d'air du local on amene une hotte au-dessus des installations a demanteler. Un ventilateur permet d'extraire en partie centrale de la hotte l'air charge des aerosols dus aux operations de demantelement. Apres epuration, une partie des gaz est renvoyee sur la hotte et s'ecoule a la peripherie de celle-ci, creant ainsi une zone de confinement dynamique autour desdites installations. Une autre partie des gaz est envoyee dans la canalisation d'extraction afin de maintenir la depression voulue a l'interieur du local. Application au demantelement d'installations nucleairesOriginal Title
Systeme de demantelement d'installations presentes dans un local, son procede de mise en oeuvre et hotte utilisable dans ce systeme
Primary Subject
Source
3 Mar 1989; 1 Sep 1987; 24 p; FR PATENT DOCUMENT 2619953/A/; FR PATENT APPLICATION 8712136; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 1 Sep 1987
Record Type
Patent
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INIS VolumeINIS Volume
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McKinnon, M.A.; Stewart, L.
International symposium on storage of spent fuel from power reactors. Book of extended synopses1998
International symposium on storage of spent fuel from power reactors. Book of extended synopses1998
AbstractAbstract
No abstract available
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 131 p; Nov 1998; p. 75-76; International symposium on storage of spent fuel from power reactors; Vienna (Austria); 9-13 Nov 1998; IAEA-SM--352/37; 2 refs
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Miscellaneous
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AbstractAbstract
[en] This document details the Software Acceptance Testing of gas characterization systems. The gas characterization systems will be used to monitor the vapor spaces of waste tanks known to contain measurable concentrations of flammable gases
Primary Subject
Source
27 Feb 1996; 69 p; CONTRACT AC06-96RL13200; Also available from OSTI as DE97052632; NTIS; US Govt. Printing Office Dep
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