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Hoffman, Patrick; Salmon, Jean; Vuillemin, Michel.
CEA Centre d'Etudes de Limeil, 94 - Villeneuve-Saint-Georges (France)1978
CEA Centre d'Etudes de Limeil, 94 - Villeneuve-Saint-Georges (France)1978
AbstractAbstract
[en] Inside a reactor, when the drift velocity of the neutron gas is small with respect to its velocity of thermal agitation, it is possible to introduce an approximation in the usual Grad expansion and to obtain a simple form of the neutron distribution as a function of the components of their individual velocities and of the usual moments. Carrying that distribution into Boltzmann's equation, and integrating conveniently, one obtains equations of the hydrodynamic type. The terms which express the influence of collisions contain noticeable functions which are characteristic of the nature of the nuclei and of the neutron temperature. In the case of a spherical fast-neutron reactor, the determination of the multiplication coefficient boils down to the integration of four differential equations. The results thus obtained for a certain number of configurations are compared with those obtained with the D.S.N. method
[fr]
Au sein d'un reacteur, lorsque la vitesse d'ensemble du gaz de neutrons est faible vis-a-vis de sa vitesse d'agitation thermique, il est possible d'introduire une approximation dans le developpement usuel de Grad et d'obtenir une forme simple de distribution des neutrons en fonction des composantes de leurs vitesses individuelles et des moments usuels. En reportant celle-ci dans l'equation de Boltzmann, et en integrant de maniere convenable, des equations du type hydrodynamique sont obtenues. Les termes exprimant l'influence des collisions contiennent des fonctions remarquables caracteristiques de la nature des noyaux et de la temperature des neutrons. Dans le cas d'un reacteur spherique a neutrons rapides, la determination du coefficient de multiplication se ramene a l'integration de quatre equations differentielles. Les resultats relatifs a un certain nombre de configurations sont compares a ceux obtenus avec la methode D.S.NOriginal Title
Application d'un developpement de Grad au transport des neutrons
Primary Subject
Source
Dec 1978; 39 p
Record Type
Report
Report Number
Country of publication
BOLTZMANN EQUATION, BOUNDARY CONDITIONS, CRITICALITY, DISTRIBUTION FUNCTIONS, ENRICHED URANIUM REACTORS, FAST REACTORS, HERMITE POLYNOMIALS, MOMENTS METHOD, NATURAL URANIUM, NEUTRON DENSITY, NEUTRON REFLECTORS, NEUTRON TEMPERATURE, NEUTRON TRANSPORT THEORY, REACTOR KINETICS EQUATIONS, SPHERICAL CONFIGURATION, TEMPERATURE DEPENDENCE, TIME DEPENDENCE
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