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Peyton, A.T. Jr.
Conference on transportation of radioactive material held in Charlottesville, Virginia on 26--27 October 1970
Conference on transportation of radioactive material held in Charlottesville, Virginia on 26--27 October 1970
AbstractAbstract
No abstract available
Original Title
Problems of highway transport
Primary Subject
Source
Virginia Univ., Charlottesville (USA); p. 119-128; 16 Nov 1970
Record Type
Report
Literature Type
Conference
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Griveau, R.; Kerlau, D.; Tucoulat, D.; Colas, J.; Pellier, R.
Societe Generale pour les Techniques Nouvelles (SGN), 78 - Saint-Quentin-en-Yvelines (France)
Societe Generale pour les Techniques Nouvelles (SGN), 78 - Saint-Quentin-en-Yvelines (France)
AbstractAbstract
[en] The push piece permits the displacement of little section elements in a magazine of high section. At the end of cut, the push piece leans its flank against an auxiliary blank holder and the element is pushed by a paddle, the push piece being immobilized
[fr]
L'invention concerne un poussoir place dans un magasin pour elements combustibles irradies qui permet leur deplacement pour les operations de coupe. Le poussoir selon l'invention permet le deplacement d'elements de petite section dans un magasin de grande section. En bout de coupe, le poussoir appuie son flanc contre le serre-flanc auxiliaire formant une surface continue et l'element est pousse par une palette, le corps du poussoir etant immobiliseOriginal Title
Poussoir pour magasin d'elements combustibles irradies
Primary Subject
Source
1 Sep 1989; 29 Feb 1988; 11 p; FR PATENT DOCUMENT 2627891/A/; FR PATENT APPLICATION 8802498; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 29 Feb 1988
Record Type
Patent
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AbstractAbstract
No abstract available
Original Title
Recipient de transport d'elements combustibles de reacteurs nucleaires
Primary Subject
Source
06 Feb 1973; 7 p; FR PATENT DOCUMENT 2171163/A/; Available from INPI, Paris; Available from Institut National de la Propriete Industrielle, Paris (France); priority claim: 11 Feb 1972.
Record Type
Patent
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AbstractAbstract
[en] The programme to develop a new generation of casks to ship spent fuel from reactors in the United States has come up with some innovative approaches to optimize cask design. Capacity increases of up to four and a half times that of casks now in use are projected. (author)
Primary Subject
Record Type
Journal Article
Journal
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AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
19 Mar 1974; 6 p; US PATENT DOCUMENT 3,797,860
Record Type
Patent
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Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
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Smith, A.J.
British Nuclear Fuels Ltd., Risley; Deutsches Patentamt, Muenchen (Germany, F.R.)
British Nuclear Fuels Ltd., Risley; Deutsches Patentamt, Muenchen (Germany, F.R.)
AbstractAbstract
[en] The inner container of a transport flask is used for the transport of irradiated fuel elements to an irradiation plant. The cylindrical inner container has a removable lid, a saucer-shaped floor and a cellular subdivision for accommodating fuel elements. Pipes pass through the lid and floor, by which the fuel elements can be sprayed with a liquid. The pipes led through the floor are bent through an angle so that the spraying liquid is given a helical motion. A sump arranged at the floor and having discharbe pipes can be used to remove solids from the inner container. (DG) 891 HP/DG 892 MKO
[de]
Der Innenbehaelter eines Transportkessels dient dem Transport von bestrahlten BE zu einer Aufarbeitungsanlage. Der zylinderfoermige Innenbehaelter weist einen abnehmbaren Deckel, einen tellerfoermig ausgebildeten Boden und eine zellenartige Unterteilung zur Aufnahme der BE auf. Durch den Deckel und den Boden sind Rohre gefuehrt, ueber die die BE mit Spuelfluessigkeit besprueht werden koennen. Die durch den Boden gefuehrten Rohre sind winklig abgebogen, so dass die Spruehfluessigkeit in eine Spiralbewegung versetzt wird. Ueber einen am Boden angeordneten Abzugssumpf mit Abfuehrleitungen koennen Feststoffe aus dem Innenbehaelter entfernt werden. (DG)Original Title
Transportbehaelter fuer Kernbrennstoffe
Primary Subject
Source
3 May 1979; 18 p; DE PATENT DOCUMENT 2748019/A/
Record Type
Patent
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Reference NumberReference Number
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INIS IssueINIS Issue
Stamm, W.J.; Kleij, N. van der.
Non-destructive testing for reactor core components and pressure vessels
Non-destructive testing for reactor core components and pressure vessels
AbstractAbstract
No abstract available
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); p. 87-92; 1972; Panel on non-destructive testing for reactor core components and pressure vessels; Vienna, Austria; 29 Nov 1971
Record Type
Report
Literature Type
Conference
Report Number
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AbstractAbstract
[en] The described device for testing the tightness of fuel elements has been developed for determining defect, in particular spent fuel elements after medium-term storage before removal from the plant and interim storage, resp
Original Title
Vorrichtung zur Dichtheitspruefung von Kernbrennstoffelementen
Primary Subject
Source
16 Nov 1983; vp; DD PATENT DOCUMENT 204173/A/; Available from BUCHEXPORT, DDR-7010 Leipzig
Record Type
Patent
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Publication YearPublication Year
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INIS VolumeINIS Volume
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AbstractAbstract
No abstract available
Primary Subject
Source
8 May 1973; 14 p; US PATENT DOCUMENT 3,732,427
Record Type
Patent
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INIS VolumeINIS Volume
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AbstractAbstract
[en] Dissolution process of matter in a cavity, and more particularly, nuclear fuel reprocessing for example by acid attack of nuclear fuels and fission products in cutted fuel pins where the fuel is inside the cladding for example in stainless steel. In this process the material is put in the liquid submitted to pressure cycles comprising pressure decrease to lead to liquid boiling and pressure increase to stop liquid boiling
[fr]
Procede de dissolution d'une matiere dans une cavite, et plus particulierement, un procede de retraitement d'un combustible nucleaire, par exemple dans un dissolvant acide dans lequel des matieres combustibles nucleaires et des produits de fission sont dissous a partir de morceaux d'aiguilles de combustible nucleaire tronconnees, c'est-a-dire un combustible nucleaire enferme dans une matiere telle qu'une gaine d'acier inoxydable. Ce procede consiste a mettre la matiere en contact avec le liquide et a soumettre ce dernier a plusieurs cycles de pression, chacun d'eux comprenant une baisse de pression pour provoquer l'ebullition du liquide et une augmentation de pression par rapport a la pression reduite pour inhiber l'ebullition dudit liquideOriginal Title
Procede de dissolution d'une matiere, telle que des troncons d'aiguilles de combustible nucleaire, dans une cavite partiellement fermee
Primary Subject
Source
7 Mar 1980; 12 p; FR PATENT DOCUMENT 2432888/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 9 Aug 1978, UK.
Record Type
Patent
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