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Results 1 - 10 of 1970.
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Schmidtke, B.
Zentralinstitut fuer Kernforschung, Rossendorf bei Dresden (German Democratic Republic)1983
Zentralinstitut fuer Kernforschung, Rossendorf bei Dresden (German Democratic Republic)1983
AbstractAbstract
[en] The described irradiation assembly has been designed so that a) it can be adjusted to the dimensions of the material to be irradiated, b) individual parts can be reused, and c) it can be cooled effectively
Original Title
Mehrteilige Bestrahlungskassette
Primary Subject
Source
9 Feb 1983; vp; DD PATENT DOCUMENT 158971/A/; Available from BUCHEXPORT, DDR-7010 Leipzig
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Anon; p. 86-87; 1974; Univ. of Virginia; Charlottesville, VA; Conference on research, test and training reactors; Charlottesville, Virginia, USA; 12 Aug 1974
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A continuous-flow/helium cryostat for the irradiation of materials with high energy electrons up to 50 μA/cm2 beam density and subsequent annealing in the range 4.2- 500 K is described. During operation liquid helium is fed from a large storage vessel through a flexible vacuum-insulated transfer line. The cryostat design allows the storage vessel to be replaced without warming the samples. This eliminates any limitation on the length of continuous operation. In the range 150-500 K it is possible to use helium gas with either external cooling or internal heating. Helium consumption is up to 5 1/h (liquid) or 10 m3/h (gas) depending on the irradiation temperature and heat evolved in the irradiation zone. (Author)
Primary Subject
Source
14. international cryogenic engineering conference and international cryogenic materials conference: cryogenic engineering and superconductor technology; Kiev (Ukraine); 8-12 Jun 1992
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Cartier, Louis; Dupouy, J.-M.
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. des Reacteurs a Neutrons Rapides; CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1974
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. des Reacteurs a Neutrons Rapides; CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1974
AbstractAbstract
No abstract available
Original Title
Fluage d'irradiation: dispositif et premiers resultats
Primary Subject
Source
1974; 4 p; European conference on irradiation behaviour of fuel cladding and core component materials; Karlsruhe, F.R. Germany; 03 Dec 1974
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Corrigan, D.C.; Julyk, L.J.; Hoth, C.W.; McGuire, J.C.; Sloan, W.R.
Hanford Engineering Development Lab., Richland, WA (USA)1980
Hanford Engineering Development Lab., Richland, WA (USA)1980
AbstractAbstract
[en] FFTF utilization for irradiation testing is beginning. Two Fuels Open Test Assemblies and one Vibration Open Test Assembly, both containing in-core contact instrumentation, are installed in the reactor. These assemblies will be used to confirm plant design performance predictions. Some 100 additional experiments are currently planned to follow these three. This will result in an average core loading of about 50 test assemblies throughout the early FFTF operating cycles
Primary Subject
Source
1980; 7 p; 2. international conference of liquid metal technology for energy systems; Richland, WA, USA; 20 - 24 Apr 1980; CONF-800401--25; Available from NTIS., PC A02/MF A01
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
23 Oct 1973; 4 p; US PATENT DOCUMENT 3,767,525
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Butzek, D.A.; Stelzer, F.
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany). Zentralinstitut fuer Reaktorexperimente1973
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany). Zentralinstitut fuer Reaktorexperimente1973
AbstractAbstract
No abstract available
Original Title
Die programmierte thermische Auslegung von Material- und Brennstoffrigs
Primary Subject
Secondary Subject
Source
Nov 1973; 39 p; 9 figs.; 5 tabs.; 24 refs. With abstract.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Loevenich, J.; Broun, E.
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)1987
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)1987
AbstractAbstract
[en] The turning and positioning device is suitable for use in a swimming pool reactor. The upward and downward movement of the test capsule is done by a rope winch with a crank, where the channel consisting of several tubular pieces pushes outside or inside one another. In the lower end position, the rotation of the test capsule can be done by rotary movement of the tubular pieces. (DG)
[de]
Die Dreh- und Positioniervorrichtung eignet sich fuer den Einsatz in einem Schwimmbadreaktor. Die Auf- und Abwaertsbewegung der Probenkapsel erfolgt mittels einer Seilwinde mit Kurbel, wobei sich der aus mehreren Rohrstuecken bestehende Kanal formschluessig auseinander- bzw. ineinanderschiebt. In der unteren Endstellung kann die Drehung der Probenkapsel ueber eine Drehbewegung der Rohstuecke vorgenommen werden. (DG)Original Title
Vorrichtung zum Positionieren und Drehen einer Probenkapsel in einem senkrechten Bestrahlungskanal eines Kernreaktors
Primary Subject
Secondary Subject
Source
25 Jun 1987; 10 May 1985; 4 p; DE PATENT DOCUMENT 3516856/C2/; ?: 10 May 1985
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Danko, A.D.
Hanford Engineering Development Lab., Richland, WA (USA)1984
Hanford Engineering Development Lab., Richland, WA (USA)1984
AbstractAbstract
[en] The Interim Examination and Maintenance (IEM) Cell is a vertical hot cell located within the containment dome of the Fast Flux Test Facility (FFTF). The cell has two basic functions: (1) to perform disassembly/reassembly and nondestructive testing on radioactive, sodium-wetted reactor components, and (2) to provide a shielded work volume where radioactive, sodium-wetted reactor and refueling equipment can be repaired and maintained. One of the recent FFTF experiments processed through the IEM Cell was the Material Open Test Assembly (MOTA). This paper describes the disassembly and reassembly of the MOTA test assembly
Original Title
Interim examination and maintenance
Primary Subject
Source
Jan 1984; 5 p; Annual meeting of the American Nuclear Society; New Orleans, LA (USA); 3-8 Jun 1984; CONF-840614--46; Available from NTIS, PC A02/MF A01; 1 as DE84010317
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Cho, M. S.; Choi, M. H.; Choo, K. N.; Sohn, J. M.; Kang, Y. H.; Kim, B. G.
Proceedings of the KNS spring meeting2006
Proceedings of the KNS spring meeting2006
AbstractAbstract
[en] A creep capsule with two specimens was designed, fabricated and irradiated during the period from Feb, 2004 to May, 2005. In the design stage, the reactivity effect was reviewed and an analysis for the structural and thermal integrity was performed to review the safety of the creep capsule. During the irradiation test, the temperature of the components and the displacement of the specimen were measured and analyzed. The temperature of the specimen during the test was 550±5 .deg. C over the whole irradiation period. The measured temperature of the components showed differences of not more than 90 .deg. C. when compared with the design values and this indicates the error range to be 18% or so when compared with the design values
Primary Subject
Source
Korean Nuclear Society, Taejon (Korea, Republic of); [1 CD-ROM]; 2006; [2 p.]; 2006 spring meeting of the KNS; Gapyoung (Korea, Republic of); 25-26 May 2006; Available from KNS, Taejon (KR); 3 refs, 3 figs, 3 tabs
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
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