Filters
Results 1 - 10 of 2738
Results 1 - 10 of 2738.
Search took: 0.041 seconds
Sort by: date | relevance |
AbstractAbstract
No abstract available
Original Title
Experimentelle Ergebnisse der nicht nuklearen LOFT-Versuche
Primary Subject
Source
Kerntechnische Gesellschaft im Deutschen Atomforum e.V., Bonn (Germany, F.R.); p. 269-273; 1977; ZAED; Eggenstein-Leopoldshafen, Germany, F.R; Reactor congress 1977; Mannheim, Germany, F.R; 29 Mar 1977; AED-CONF--77-013-067; 1 fig.; 1 tab. Short communication only.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Perrin, J.; Dupont, G.
CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France). Service des Piles1974
CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France). Service des Piles1974
AbstractAbstract
[en] The loop installed in the Siloe reactor is described. It is intended for giving data on the phenomena involved in HTR reactors: fission product migration, deposit, and corrosion; and reactor safety (blowdown and water flooding)
[fr]
On decrit la boucle installee dans le reacteur Siloe qui doit fournir les donnees permettant la comprehension des phenomenes de la filiere RHT: migration des produits de fission, leur depot et la corrosion, la securite avec la depressurisation et l'entree d'eauOriginal Title
Boucle d'irradiation liee a la filiere R.H.T
Primary Subject
Source
7 Nov 1974; 4 p; Reactor congress; Nuremberg, Germany, F.R; 8 Apr 1975
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Howard, G.E.
Anco Engineers, Inc., Culver City, CA (USA)1984
Anco Engineers, Inc., Culver City, CA (USA)1984
AbstractAbstract
[en] This report consists of comparisons of prediction and experiment for German Standard Problem 4a, a blowdown experiment involving structural dynamic response. The comparisons presented herein are of the time histories of displacement, bending stress, and bending axis angle. The reasons for error in the predictions are discussed. The structural model is improved to obtain a better match with the experimental natural frequencies
Primary Subject
Source
Mar 1984; 43 p; Available from NTIS, PC A03; 3 - GPO* $4.00 as DE84901071
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Ehksperimental'noe issledovanie statsionarnogo raskhoda i reaktivnogo usiliya pri adiabatnom istechenii vskipayushchej vody cherez ogranichiteli techi
Primary Subject
Source
Short note. For English translation see the journal High Temperature (USA).
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The efflux of underheated to saturation boiling-up water, containing particles of foamy polystyrene with the density dose to water density and 0.2-0.6 mm in diameter, is studied experimentally. The channel is horizontal, of rectangular cross section 8x10x110 mm3 with transparent walls. Parameters in the experiments varied in the following ranges: pressure at the input to the channel p0=0.1-0.4 MPa; pressure at the output from the channel p1=0.1-0.25 MPa; water temperature at the input T=283-353 K; mass part of the particles x=0-10sup(-3). The flow structure was photographed. It is shown that the addition of solid particles to liquid flow intensifies the boiling-up process, increases the dimensions of bubble structure zone, which results in the attaining of efflux crisis at lower flow rate values
Original Title
Ehksperimental'noe issledovanie istecheniya vskipayushchej zhidkosti, soderzhashchej tverdye chastitsy
Primary Subject
Source
For English translation see the journal High Temperature (USA).
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This report deals with the structural behaviour of piping systems under earthquake and blowdown conditions. The tests were conducted within the scope of the HDR-safety programme of the BMFT. The applied measuring technique and the evaluation of strains enables a good experimental stress analysis by determining the pressure, axial, bending and torsion loads. Inspite of the extremely low loading which only reached five percent of the material yield point, it was possible to conduct a clear experimental analysis of the structural dynamic response during the earthquake tests under snapback, shaker and explosive excitement. As opposed to this there occurred high pressure and bending peaks exceeding the yield load in steam insulation valve as well as feedwater check valve blowdown tests. The stresses are strongly influenced by the closing characteristic of the valves. (orig.)
Primary Subject
Secondary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. F4/1 (1-8); ISBN 0444 85362 6; ; 1979; p. F4/1 (1-8); North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-199; With figs.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The HDR plant has been out of service for several years and is now a test facility for full scale blowdown experiments. The first experimental program was concerned with valves and their dynamic behaviour under blowdown conditions. The pressure waves and the loading of the discharge pipe influenced by the blowdown and the quick closing valves were also observed. A steam isolation valve and a feed water check valve have been tested in this program. The correct operation of these valves is essential in blowdown. For the first tests an original isolation valve which is installed in the steam line of PWR's or BWR's was used. The HDR pressure vessel has a volume of about 66 m3. On the top of this vessel a test blowdown tube with a length of 20 m and an I.D. of 450 mm was constructed. With this facility several tests were conducted with various discharge rates (from nominal rate up to strong blowdown conditions) in the blowdown tube and with a delayed closure so that closing behaviour during two phase flow could also be investigated. In the second part of the valve experiments a quick closing feed water check valve (I.D. 200 mm) was tested with a variation of the damping in order to study the influence on the closing time and on the pressure waves. The pressure amplitudes observed after the valve was closed reached 300 bars in some tests which indicates that it is necessary to consider these severe problems very carefully. (orig.)
Primary Subject
Secondary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. F8/2 (1-7); ISBN 0444 85362 6; ; 1979; p. F8/2 (1-7); North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-227; With figs.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The blowdown of a safety valve is defined as the difference between the pressure at which the valve opens and the pressure at which the valve fully closes under certain fluid flow conditions. An extensive series of tests carried out in the EPRI/PWR Utilities Valve Test Program have shown that the blowdown of safety valves can in general be strongly dependent upon the valve geometry and other parameters such as ring adjustments, spring stiffness, back pressure etc. On this study, fluid velocity within safety valve in accordance with ring setting has been investigated
Primary Subject
Source
Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2003; [7 p.]; 2003 autumn meeting of the KNS; Yongpyong (Korea, Republic of); 30-31 Oct 2003; Available from KNS, Taejon (KR); 4 refs, 9 figs, 1 tab
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Reactor depressurization system
Primary Subject
Secondary Subject
Source
24 Jul 1973; 38 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] As a part of the HDR program, methods for coupled fluid-structural dynamics are being developed. On the fluid side the 2D finite difference code YAQUI has been modified (it became YAQUIR) and adapted to describe the fluid dynamics in the downcomer of PWR's. On the structural side for determination of the dynamic core barrel response the code CYLDY2 has been developed. In this code the core barrel is treated as a thin cylindrical shell fixed at the upper end and ring stiffened at the lower end. The mass of the lower end ring also simulated a part of the core mass. Both models have been successfully tested. Coupling has been achieved for a simplified structural model proving the correctness of the coupling procedure. The structural model CYLDY2 is based on Fluegge's shell equations and uses variational principles. The solution is a superposition of steady-state and transient eigenfunctions. Results indicate that for the relatively thin-walled core barrel of the HDR-experiments in most cases the local deformations are somewhat higher than the global deformation (beam model). The coupling of YAQUIR and CYLDY2 is performed by imbedding the structural model in the fluid model. Fluid velocities are parallel to the fluid/structure interface. The structure desplacements define the time and space dependent thickness of the two-dimensional fluid layer (2 1/2-dimensional model)
Primary Subject
Source
v. B; 1977; B 5/2, 10 p; 4. International conference on structural mechanics in reactor technology; San Francisco, Calif., USA; 15 - 19 Aug 1977
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |