Pruchon, P.
Compagnie Generale des Matieres Nucleaires (COGEMA), 78 - Velizy Villacoublay (France)1986
Compagnie Generale des Matieres Nucleaires (COGEMA), 78 - Velizy Villacoublay (France)1986
AbstractAbstract
[en] A safety device is claimed for a correct air flow in an enclosure in case of low pressure variations. This device is incorporated: to the air inlet adjusting the flow rate, increasing available room inside the glovebox
[fr]
On decrit un dispositif de securite permettant d'etablir un debit d'air convenable dans une enceinte en cas de variation accidentelle de la depression; selon l'invention, le dispositif de securite est incorpore au dispositif d'entree d'air et assure lui-meme la regulation du debit d'air dans l'enceinte, ce qui augmente l'espace disponible a l'interieur. Application au controle de la depression a l'interieur d'une boite a gantsOriginal Title
Dispositif de ventilation d'une enceinte confinee
Primary Subject
Source
13 Jun 1986; 11 Dec 1984; 20 p; FR PATENT DOCUMENT 2574520/A/; FR PATENT APPLICATION 8418901; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 11 Dec 1984
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Barrocas, M.; Pruchon, P.; Robin, J.P.; Rouyer, J.L.; Salmon, P.
16th DOE nuclear air cleaning conference: proceedings1981
16th DOE nuclear air cleaning conference: proceedings1981
AbstractAbstract
[en] For large ventilation networks, it is necessary to make a safety evaluation of their responses to perturbations such as blower failure, unexpected transfers, local pressurization. This evaluation is not easy to perform because of the many interrelationships between the different parts of the networks, interrelationships coming from the circulations of workers and matetials between cells and rooms and from the usefulness of air transfers through zones of different classifications. This evaluation is all the more necessary since new imperatives in energy savings push for minimizing the air flows, which tends to render the network more sensitive to perturbations. A program to evaluate safety has been developed by the Service de Protection Technique in cooperation with operators and designers of big nuclear facilities and the first applications presented here show the weak points of the installation studied from the safety view point
Primary Subject
Source
First, M.W. (ed.); Harvard Univ., Boston, MA (USA). Harvard Air Cleaning Lab; p. 216-224; Feb 1981; p. 216-224; 16. DOE nuclear air cleaning conference; San Diego, CA, USA; 20 - 23 Oct 1980
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The parameters of the ventilation flow rate, depression, arrangement of the premises, dimensioning of the equipment, energy sources are determined in order to reach the target fixed in the best technical and economic conditions throughout the whole life of the system
[fr]
On determine les parametres de la ventilation: debit, depression, disposition des locaux, dimensionnement des equipements, sources d'energie pour atteindre le but fixe dans les meilleures conditions technico-economiques pendant toute la duree de vie du systemeOriginal Title
Optimisation des systemes de ventilation, choix et evolution des equipements
Primary Subject
Source
Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 322 p; 1982; 23 p; Societe Francaise de Radioprotection; Fontenay-aux-Roses (France); Meeting on the ventilation of nuclear facilities; Pierrelatte (France); 22 - 26 Mar 1982
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Perdriau, P.; Raboin, S.; Mulcey, P.; Martin, G.; Pruchon, P.
Proceedings of the 19th DOE/NRC nuclear air cleaning conference1987
Proceedings of the 19th DOE/NRC nuclear air cleaning conference1987
AbstractAbstract
[en] The response of a ventilation network to disturbances either mechanical or thermal is difficult to evaluate when the network becomes complex as is the case in nuclear power plants and other nuclear facilities. Several teams from the CEA GROUP have joined together to elaborate a computation code able to simulate the behavior of any classical ventilation network. Such a code allows the study of a ventilation system in its design stage, pointing out safety problems and helping to solve them; the basis model generated in the design stage may be used to follow the operating life of the system, up to dismantling. The code, called PIAF, solves the set of equations which simulate a ventilation network in steady state: the numerical network is composed of nodes connected with various components. The unknowns of such a problem are pressure and temperature at the nodes and flow rates in the links. The problem induces a weakly nonlinear system, that PIAF solves by an iterative matricial newtonian method. PIAF has been validated in several facilities in France for various mechanical disturbances: some of those validation cases are considered
Primary Subject
Secondary Subject
Source
First, M.W. (ed.); USDOE Assistant Secretary for Environment, Safety, and Health, Washington, DC; Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation; Harvard Univ., Boston, MA (USA). Harvard Air Cleaning Lab; p. 674-684; May 1987; p. 674-684; 19. DOE/NRC nuclear air cleaning conference; Seattle, WA (USA); 18-21 Aug 1986; NTIS, PC A99/MF A01 - US Govt. Printing Office. as TI88015222
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue