Study of neutron migration ion a multiplying medium according to the intensity and distribution of absorptions
- 1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires
Description
The calculation of the neutron migration area assumes a simple form in two limiting cases: the case of pure slowing down and the case of purely thermal diffusion. In a thermal reactor, through these two schemes can be more or less applied at the start and finish of the life of the neutron, we must also consider a transition zone, in which the phenomena are obviously far more complex. How is the link to be made, and in what way does it depend on the distribution law of the captures? Two different methods have been developed to solve this problem. In the first one, the neutron is tracked through successive collisions, and attention is particularly concentrated on the variation of the absorption probability; in the second one, the spectrum is considered as a whole, the balance of neutrons arriving and disappearing at each velocity being written down. It is proved, moreover, that the two methods are based on the same formulation. The first one gives rise to interesting interpretations which permit a deep understanding of the physical phenomena; the second produces easier calculation, through the new thermalization operators developed at Saclay, The parameters of the problem are being studied successively (thermalization model, absorption law, variation law of the diffusion coefficient, geometrical parameters of the cell, relative importance of the leakages) For each of then, numerical applications are presented. (author)
Availability note (English)
Available from INIS in electronic formAbstract (French)
Le calcul de l'aire de migration des neutrons se formule simplement dans deux cas limites: celui du ralentissement pur, et celui de la diffusion purement thermique. Dans un reacteur thermique, si on peut a la rigueur utiliser ces deux schemas au debut et a la fin de la vie des neutrons, il faut bien aussi considerer une zone de transition ou les phenomenes sont visiblement plus complexes. Comment effectuer le raccordement, et comment depend-il de la loi de repartition des captures? Deux methodes differentes ont ete etudiees pour resoudre ce probleme. Dans la premiere on suit le neutron au cours de ses chocs successifs, et on s'interesse en particulier a la maniere dont varie sa probabilite de capture; dans la seconde on considere globalement ce spectre, en ecrivant a chaque vitesse le bilan des neutrons qui arrivent et disparaissent. On montre d'ailleurs que ces deux methodes reposent en definitive sur le meme formalisme. La premiere donne lieu a des interpretations interessantes qui permettent une tres bonne comprehension des phenomenes physiques, la seconde conduit a des calculs particulierement commodes, grace aux operateurs de thermalisation mis au point a Saclay. Les differents parametres qui regissent ce probleme sont etudies successivement (modele de thermalisation - loi de capture - loi de variation du coefficient de diffusion - parametres geometriques de la cellule - importance relative des fuites), pour chacun d'eux, on donne des applications numeriques. (auteur)Files
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Additional details
Additional titles
- Original title (French)
- Etude de la migration des neutrons dans un milieu multiplicateur en fonction de l'intensite et de la distribution des captures
Publishing Information
- Imprint Pagination
- 56 p.
- Report number
- CEA-R--2476
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 37077154
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- ABSORPTION; CAPTURE; DIFFUSION; DISTRIBUTION FUNCTIONS; MIGRATION LENGTH; NEUTRON AGE; NEUTRON LEAKAGE; NEUTRON SPECTRA; PROBABILITY; SLOWING-DOWN LENGTH; THERMAL REACTORS; THERMALIZATION
- Descriptors DEC
- DIMENSIONS; FUNCTIONS; LENGTH; REACTORS; SLOWING-DOWN; SORPTION; SPECTRA
Optional Information
- Notes
- 5 refs.