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Nagasaka, Hideo.
Tokyo Shibaura Electric Co. Ltd., Kawasaki, Kanagawa (Japan)
Tokyo Shibaura Electric Co. Ltd., Kawasaki, Kanagawa (Japan)
AbstractAbstract
[en] Purpose: To provide a reactor container system for preventing the leakage of radioactivity at the time of a reactor accident, wherein spraying water is sprayed without mutual interference thereby to carry out the heat removal and the removal of radioactive gas within the reactor container spray system. Constitution: On the circumference of a reactor container there are provided a group of upward spray nozzles at its upper stage and a group of transverse spray nozzles at the lower stage. Each of nozzle groups at both stages is provided with a feedwater system consisting of a pump for exclusive use thereof, a heat exchanger, and a pipe. Furthermore, one of these feedwater systems is connected through a valve to another nozzle group. When the valve is opened, spraying water from a suppression chamber is sprayed without interference on the periphery of the pressure vessels from the above described spray nozzle groups, and the heat removal and the removal of radioactive gas within the reactor container are carried out efficiently. (Horiuchi, T.)
Primary Subject
Source
26 Nov 1976; 2 p; JP PATENT DOCUMENT 1978-67091/A/; Available from JAPATIC. Also available from INPADOC
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Patent
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AbstractAbstract
No abstract available
Primary Subject
Record Type
Journal Article
Journal
Hitachi Hyoron; v. 56(8); p. 713-718
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AbstractAbstract
[en] This invention concerns the transfer of toxic or radioactive substances between a containment and a flask in which such substances are transported. When toxic or radioactive substances are being transferred, it is important to ensure that such substances cannot excape into the surrounding atmosphere and, preferably, the appliance utilized has to be capable of making a misuse impossible, whether accidental or calculated. The flask to which this invention applies is of the type comprising lugs, near its open ends, which act in combination with a groove made around an access opening to hold and maintain the flask in position against the wall of the containment, so that its open end is aligned with an access opening provided in the containment wall
[fr]
La presente invention concerne le transfert de matieres toxiques ou radioactives entre une enceinte et un recipient dans lequel de telles matieres sont transportees. Lors du transfert de matieres toxiques ou radioactives, il importe que ces matieres ne puissent pas s'echapper dans l'atmosphere environnante et, de preference, l'appareil utilise doit etre capable de rendre impossible un mesusage, soit accidentel, soit volontaire. Le recipient auquel la presente invention s'applique est du type comportant des pattes, a proximite de ses extremites ouvertes, qui cooperent avec une gorge menagee autour d'une ouverture d'acces pour retenir le recipient en position sur la paroi de l'enceinte, de facon que son extremite ouverte soit alignee avec l'ouverture d'acces menagee dans ladite paroi de l'enceinteOriginal Title
Dispositif d'acces pour le transfert de matieres toxiques ou radioactives entre un recipient et une enceinte
Primary Subject
Source
6 Jun 1980; 17 p; FR PATENT DOCUMENT 2441244/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 6 Nov 1978, GB.
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This invention concerns the transfer of toxic or radioactive substances between a containment and a flask in which such substances are transported. When toxic or radioactive substances are being transferred, it is important to ensure that such substances cannot escape into the surrounding atmosphere and, preferably, the appliance utilized has to be capable of making a misuse impossible, whether accidental or calculated. The flask to which this invention applies is of the type comprising a flange near an open end which can marry with a sliding blocking component inside the containment to hold and maintain the flask against the wall of the latter. Its open end is aligned with an access opening in the wall of the containment
[fr]
La presente invention concerne le transfert de matieres toxiques ou radioactives entre une enceinte et un recipient dans lequel de telles matieres sont transportees. Lors du transfert de matieres toxiques ou radioactives, il importe que ces matieres ne puissent pas s'echapper dans l'atmosphere environnante et, de preference, l'appareil utilise doit etre capable de rendre impossible un mesusage, soit accidentel, soit volontaire. Le recipient auquel la presente invention s'applique est du type comportant une bride a proximite d'une extremite ouverte qui peut cooperer avec un element coulissant de blocage a l'exterieur de l'enceinte pour maintenir le recipient en position sur la paroi de cette derniere Son extremite ouverte est alignee avec une ouverture d'acces de la paroi de l'enceinteOriginal Title
Dispositif d'acces permettant le transfert de matieres toxiques entre un recipient bride et une enceinte
Primary Subject
Source
6 Jun 1980; 14 p; FR PATENT DOCUMENT 2441243/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 6 Nov 1978, GB.
Record Type
Patent
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Publication YearPublication Year
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Daublebsky, P.
Kraftwerk Union A.G., Muelheim an der Ruhr (F.R. Germany)
Kraftwerk Union A.G., Muelheim an der Ruhr (F.R. Germany)
AbstractAbstract
[en] A bursting safeguard for reactor pressure vessels is described which provides favourable transport possibilities and allows easy assembly. (TK/LH)
[de]
Es wird eine Berstsicherung fuer Reaktordruckbehaelter beschrieben, die guenstige Transportmoeglichkeiten und leichte Montage gestattet. (TK)Original Title
Berstsicherung fuer zylindrische Grossbehaelter
Primary Subject
Secondary Subject
Source
24 Apr 1975; 9 p; DE PATENT DOCUMENT 2349518/A/; 2 figs.
Record Type
Patent
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Baum, M.R.
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs
AbstractAbstract
[en] Generally there is a large number of pressure vessels containing high pressure gas on power stations and chemical plant. In many instances, particularly on power plant, these vessels are within the main building. If a pressure vessel were to fail, the surrounding structures would be exposed to blast loads and the forces resulting from jets of fluid issuing from the breached vessel. In the case where the vessel is in a relatively closed chamber there would also be a general overpressurisation of the chamber. At the design stage it is therefore essential to demonstrate that the plant could be safely shut down in the event of a pressure vessel failure, that is, it must be shown that the chamber will not collapse thus putting the building at risk or hazarding equipment essential for a safe shut down. Such an assessment requires the loads applied to the chamber walls, roof, etc. to be known. (author)
Primary Subject
Source
Apr 1989; 21 p
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Report
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AbstractAbstract
No abstract available
Primary Subject
Source
22 Aug 1972; 8 p; CA PATENT DOCUMENT 908320; Available from Commissioner of Patents, Ottawa; Filed 11 Feb 1970. Priority UK 19 Feb 1969 (9,095/69). 8 claims, 1 drawing. Available from Commissioner of Patents, Ottawa.
Record Type
Patent
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Lee, Y.S.; Sohn, Y.S.
Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 2
Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 2
AbstractAbstract
[en] When nozzles in the spherical vessel head are designed by area replacement method defined in the majority of pressure vessel code, the thickness of the reinforcements is so thick that the application of the thin shell theory may not be appropriate in the shell intersection problems. To obtain the solution of the thick reinforcement in the radial nozzle of the spherical vessel head subjected to radial load, the nature of thick shell is introduced to the solution of thin shell: modified meridional moment at the junction should be used in moment equilibrium equation instead of meridional moment equilibrium equation instead of meridional moment at mid-plane of reinforcement; angular rotation derivation may be neglected in the meridional moment equation; or double derivative of radial displacement may be neglected in meridional moment equation. These modified solutions are found to be reasonable and be able to use for the design of nozzle with the thick reinforcement in the initial design stage. (author). 6 refs., 9 figs
Primary Subject
Secondary Subject
Source
Riera, J.D.; Rocha, M.M. (Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Escola de Engenharia) (eds.); 897 p; ISBN 85-7025-350-8;
; 1995; p. 39-47; Editora de Universidade Federal do Rio Grande do Sul; Porto Alegre, RS (Brazil); 13. International Conference on Structural Mechanics in Reactor Technology; Porto Alegre, RS (Brazil); 13-18 Aug 1995

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Book
Literature Type
Conference
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AbstractAbstract
[en] For reactor containment vessels, one of the most important installations for the safety of nuclear power stations, the works of improving the conventional design and standardization have been forwarded, based on the experiences of construction, operation and maintenance. No. 2 plant of the Fukushima No. 2 Nuclear Power Station, Tokyo Electric Power Co., Inc., designed, manufactured and being constructed on the basis of these results is the first plant adopting this improved standard containment vessel, and the pressure endurance test and leaking rate test of the containment vessel were able to be completed without any trouble on August 30, 1980. The features of this containment vessel were to give some margin to the internal space by enlarging the diameter of the containment vessel in order to make the works of maintenance and inspection easy and to reduce the radiation exposure of workers, to provide the exclucive opening for taking out a relief safety valve and control rod-driving mechanism, to adopt high strength steel stronger than the conventional material, to improve the construction of the welded parts in bottom linear plates, and to adopt diaphragm floor seal bellows made of stainless steel. The basic structure and features of the improved standard Mark-2 containment vessels, the basic specifications for the design, and the stress calculation for the important parts are explained. (Kako, I.)
Primary Subject
Record Type
Journal Article
Journal
Hitachi Hyoron; ISSN 0367-5874;
; v. 62(9); p. 675-678

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Okajima, Masanao; Nojima, Hiroshi.
Fujita Corp., Tokyo (Japan)
Fujita Corp., Tokyo (Japan)
AbstractAbstract
[en] Purpose: To minimize the activation of shielding materials and effectively confine tritiums in the buildings for thermonuclear experiment facilities. Constitution: Water vessels made of less activatable aluminum alloys are disposed to the outside of pillars and beams and the floor made of less activatable aluminum alloys disposed to the outer circumference of experiment facilities, so as to entirely surround the facilities with no gaps. The water vessels are filled with shielding purified water, and connected with a cleanup and cooling device for purified water for nuclear facility disposed outside the buildings, a recycling device for shielding purified water and feeding and returning pipeways therefor. Purified water in the water vessels are circulated to eliminate activated impurities in the purified water, and radiolysed gases are processed. As the result, activated materials can be processed at a predetermined position of the buildings, operator's access after the end of the experiment is facilitated, and the amount of activated materials to be handled upon dismantling of the buildings can significantly be reduced. (Moriyama, K.)
Primary Subject
Source
16 Jan 1985; 27 Jun 1983; 4 p; JP PATENT DOCUMENT 60-7385/A/; JP PATENT APPLICATION 58-114351; Available from JAPIO. Also available from INPADOC; Application date: 27 Jun 1983
Record Type
Patent
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