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AbstractAbstract
[en] The APACHE code (Automatic Analysis of Failures of Hydraulic and Thermohydraulic Circuits more particularly of Water) situates in an important program of computer codes development in the field of studies on reliability and safety of systems in nuclear power plants. APACHE is an automatic generation code of failure pattern and of their effects. After a presentation of the theoretical basis, the methodological principles of the theory of networks are developed. Then, the model of the code is developed: model of individual behavior of each classical model component of normal behavior and model of failure pattern with specifications. The global model of hydraulic systems and the resolution systems are then developed. More particularly, some aspects of the theory of graphs, and the algorithms developed for the automatic construction of the equation systems and especially the algorithm of the research of meshes are presented. The computer aspect of the code and the programming of the code with its limits and some specifications are described. The practical aspect of utilization is finally presented
[fr]
Le code APACHE (Analyse des Pannes Automatique des Circuits Hydrauliques et thermohydrauliques et notamment d'Eau) fait partie d'un vaste programme de developpement des codes informatiques lors des etudes de fiabilite et de securite des systemes dans les centrales nucleaires. APACHE est un code de generation automatique de modes de defaillances et de leurs effets. Apres avoir presente les bases theoriques, on developpe les principes methodologiques de la theorie des reseaux. On developpe ensuite le modele du code: modeles de comportement individuel de chaque composant, modele classique de comportement normal et modele de mode de defaillance avec l'ensemble des specifications. On developpe ensuite le modele global des systemes thermohydrauliques et les methodes de resolution. On developpe en particulier quelques aspects de la theorie des graphes, et les algorithmes developpes pour la construction automatique des systemes d'equations et notamment l'algorithme de la recherche des mailles. On decrit l'aspect informatique du code et la mise en informatique avec l'ensemble des limites et des specifications. On presente l'aspect d'utilisation pratique du codeOriginal Title
Analyse inductive des modes de defaillances et de leurs effets des circuits thermohydrauliques dans les centrales nucleaires; APACHE
Primary Subject
Secondary Subject
Source
1983; 336 p; 3 refs.; FORTRAN, IBM.; These (D. Ing.).
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation; Software
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue