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Study of the dynamic behaviour of the reactor Rapsodie; Etude du comportement dynamique de la pile rapsodie

Abstract

It is known that fast neutron breeder reactors pose new problems in the fields of mechanics and heat technology, as well as in respect to their dynamic behaviour and safety. The reactor RAPSODIE has been the object of numerous dynamic studies on analogue and digital computers for two types of fuel (metal and oxide). After elaborating the mathematical models representing the whole of the installation (reactor block and cooling circuit) from the point of view of neutrons as well as thermodynamics, the analogue diagrams and digital codes required for simulating incidents, control and stability of the reactor were established. Considerable effort was made to obtain a greater precision than in the usual methods, either by using smaller intervals, or by the use of formulations closer to the real system, or even analytically soluble. The study of incidents was carried out on analog computer for the whole system, and digital computer for the reactor block alone or the installation functioning with a single thermal circuit. A special complementary programme - which so far as we know, was used for the first time here for sodium reactors - which takes into account the behaviour of the reactor beyond the boiling point of  More>>
Authors:
Abdon, R; Chaigne, M [1] 
  1. Commissariat a l'Energie Atomique, Cadarache (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1964
Product Type:
Technical Report
Report Number:
CEA-R-2657
Resource Relation:
Other Information: 14 refs
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COMPUTER-AIDED INSTRUCTION; COMPUTERIZED SIMULATION; RAPSODIE REACTOR; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR STABILITY; SYSTEMS ANALYSIS
OSTI ID:
20668351
Research Organizations:
CEA Cadarache, 13 - Saint-Paul-lez-Durance (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR05R2657107052
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
25 pages
Announcement Date:
Dec 14, 2005

Citation Formats

Abdon, R, and Chaigne, M. Study of the dynamic behaviour of the reactor Rapsodie; Etude du comportement dynamique de la pile rapsodie. France: N. p., 1964. Web.
Abdon, R, & Chaigne, M. Study of the dynamic behaviour of the reactor Rapsodie; Etude du comportement dynamique de la pile rapsodie. France.
Abdon, R, and Chaigne, M. 1964. "Study of the dynamic behaviour of the reactor Rapsodie; Etude du comportement dynamique de la pile rapsodie." France.
@misc{etde_20668351,
title = {Study of the dynamic behaviour of the reactor Rapsodie; Etude du comportement dynamique de la pile rapsodie}
author = {Abdon, R, and Chaigne, M}
abstractNote = {It is known that fast neutron breeder reactors pose new problems in the fields of mechanics and heat technology, as well as in respect to their dynamic behaviour and safety. The reactor RAPSODIE has been the object of numerous dynamic studies on analogue and digital computers for two types of fuel (metal and oxide). After elaborating the mathematical models representing the whole of the installation (reactor block and cooling circuit) from the point of view of neutrons as well as thermodynamics, the analogue diagrams and digital codes required for simulating incidents, control and stability of the reactor were established. Considerable effort was made to obtain a greater precision than in the usual methods, either by using smaller intervals, or by the use of formulations closer to the real system, or even analytically soluble. The study of incidents was carried out on analog computer for the whole system, and digital computer for the reactor block alone or the installation functioning with a single thermal circuit. A special complementary programme - which so far as we know, was used for the first time here for sodium reactors - which takes into account the behaviour of the reactor beyond the boiling point of sodium was refined on the basis of some simplifying assumptions. The investigation of incidents has served to determine: - The intrinsic safety of the reactor, i.e. its behaviour-under accident conditions without the intervention of the safety systems; - The behaviour of the installation under normal accident conditions, i.e. with the safety systems functioning, and the definition and organisation of the latter ; - the comparison of the two versions investigated (metal or oxide fuel) for the choice of the first loading of the reactor; - the determination of thermal shocks (amplitudes and gradients suffered by the structures during probable incidents) to be used in the test on the full-scale model of the reactor. The stability tests were carried out digitally. The investigation of the control, carried out on analog computer, served to determine the different possible means of starting and changing the conditions of the reactor as well as its automatic control. The calculations were examined in the totality by the construction of a training simulator composed of a board similar to the control board of the reactor, all of whose commands (reactivity and flows) work on an analogue computer which resolves in the real time the dynamic equations of the reactor and which reproduces simultaneously all the parameters representing the state of the installation (power, period, temperatures, etc. ) in the case of various incidents as well as under normal conditions of functioning. (authors) [French] On sait que le developpement des reacteurs surgenerateurs a neutrons rapides pose des problemes nouveaux d'une part dans les domaines mecanique et thermique et d'autre part en ce qui concerne leur comportement dynamique et leur surete. La pile RAPSODIE a ete l'objet de tres nombreuses etudes dynamiques effectuees sur machines analogiques et digitales, pour deux versions du combustible (metal et oxyde). Apres elaboration des modeles mathematiques representatifs de l'ensemble de l'installation (bloc pile et circuit de refroidissement) tant du point de vue neutronique que du point de vue thermodynamique, on a mis au point les schemas analogiques et les codes digitaux utilisables pour mener a bien les simulations d'incidents, de conduite et de stabilite du reacteur. On s'est attache, par rapport aux methodes habituelles a obtenir une precision plus grande, par un decoupage en zones plus fines, par l'emploi de formulations plus representatives du systeme reel, voire solubles analytiquement. Les etudes d'incidents ont ete effectuees par voie analogique pour l'ensemble de l'installation et par voie digitale pour l'etude du bloc pile seul ou de l'installation fonctionnant avec un seul circuit thermique. Un programme complementaire special - qui, a notre connaissance, a ete employe pour la premiere fois ici pour les piles a sodium - rendant compte du comportement du reacteur au-dela de l'ebullition du sodium a ete mis au point moyennant certaines hypotheses simplificatrices. Les etudes d'incidents ont permis de preciser: - La securite intrinseque du reacteur, c'est-a-dire son comportement en regime accidentel sans intervention du systeme de securite; - Le comportement de l'installation en regime accidentel normal, c'est-a-dire avec fonctionnement du systeme de securite et la definition et l'organisation de celui-ci; - La comparaison entre les deux versions etudiees (combustible metal et combustible oxyde) en vue du choix de la premiere charge de la pile; - La determination des chocs thermiques (amplitude et gradients subis par les structures lors des incidents probables en vue des essais sur la maquette a l'echelle 1 de la pile. Les etudes de stabilite ont ete effectuees par voie digitale. Les etudes de conduite, menees sur machines analogiques, ont permis de preciser les differentes procedures envisageables pour le demarrage et les changements de regime de la pile, ainsi que son pilotage automatique. L'ensemble de toutes ces etudes a ete concretise par la mise au point d'un simulateur d'entrainement compose d'un pupitre similaire au pupitre de controle de la pile mais dont toutes les commandes (reactivite et debits) actionnent une calculatrice analogique resolvant en temps reel les equations dynamiques de la pile, laquelle restitue simultanement tous les parametres representatifs de l'etat de l'installation (puissance, periode, temperatures, etc) aussi bien en fonctionnement normal que dans le cas des divers incidents possibles. (auteurs)}
place = {France}
year = {1964}
month = {Jul}
}