Abstract
The experience gained in several years of operating the G2 and G3 reactors confirms that natural uranium-graphite-gas reactors are extremely safe. The built-in shut-down and safety mechanisms which minimize operational incidents such as lack of power from the mains, blower failure, lack of water etc., together with accidents such as cladding bursts, local overheating, loss of coolant etc. are described and their operation explained by means of diagrams. The main points examined are as follows: (a) power distribution and controlability during accident conditions; (b) distribution of emergency water; and (c) the safety chain. The performance of the installations and the successive improvements incorporated in them are mentioned. The built-in safety characteristics of the reactors are shown by means of an experimental study of their behaviour in transient operation. These studies make it possible to check the validity of the calculation model. The machine calculation programmes can subsequently be used to study the consequences of possible accidents. Special attention is given to the depressurization accident, taking into account the performance of the safety device installed. (author) [French] L'experience acquise'au cours de plusieurs annees d'exploitation des piles G2 et G3 permet de confirmer le haut degre de securite du fonctionnement des piles
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Citation Formats
Henri, C., Plisson, J., and Teste duBailler, A.
Efficiency of the Shut-Down and Safety Equipment and the Kinetic Characteristics of the G2 and G3 Reactors; Efficacite des dispositifs de secours et de securite et caracteristiques cinetiques des piles G2 et G3; Ehffektivnost' sistem avarijnoj zashchity reaktorov G.2 i G.3 i kineticheskie kharakteristiki ehtikh sistem; Caracteristicas cineticas y eficacia de los dispositivos de auxilio y de seguridad de los reactores G2 y G3.
IAEA: N. p.,
1963.
Web.
Henri, C., Plisson, J., & Teste duBailler, A.
Efficiency of the Shut-Down and Safety Equipment and the Kinetic Characteristics of the G2 and G3 Reactors; Efficacite des dispositifs de secours et de securite et caracteristiques cinetiques des piles G2 et G3; Ehffektivnost' sistem avarijnoj zashchity reaktorov G.2 i G.3 i kineticheskie kharakteristiki ehtikh sistem; Caracteristicas cineticas y eficacia de los dispositivos de auxilio y de seguridad de los reactores G2 y G3.
IAEA.
Henri, C., Plisson, J., and Teste duBailler, A.
1963.
"Efficiency of the Shut-Down and Safety Equipment and the Kinetic Characteristics of the G2 and G3 Reactors; Efficacite des dispositifs de secours et de securite et caracteristiques cinetiques des piles G2 et G3; Ehffektivnost' sistem avarijnoj zashchity reaktorov G.2 i G.3 i kineticheskie kharakteristiki ehtikh sistem; Caracteristicas cineticas y eficacia de los dispositivos de auxilio y de seguridad de los reactores G2 y G3."
IAEA.
@misc{etde_22108190,
title = {Efficiency of the Shut-Down and Safety Equipment and the Kinetic Characteristics of the G2 and G3 Reactors; Efficacite des dispositifs de secours et de securite et caracteristiques cinetiques des piles G2 et G3; Ehffektivnost' sistem avarijnoj zashchity reaktorov G.2 i G.3 i kineticheskie kharakteristiki ehtikh sistem; Caracteristicas cineticas y eficacia de los dispositivos de auxilio y de seguridad de los reactores G2 y G3}
author = {Henri, C., Plisson, J., and Teste duBailler, A.}
abstractNote = {The experience gained in several years of operating the G2 and G3 reactors confirms that natural uranium-graphite-gas reactors are extremely safe. The built-in shut-down and safety mechanisms which minimize operational incidents such as lack of power from the mains, blower failure, lack of water etc., together with accidents such as cladding bursts, local overheating, loss of coolant etc. are described and their operation explained by means of diagrams. The main points examined are as follows: (a) power distribution and controlability during accident conditions; (b) distribution of emergency water; and (c) the safety chain. The performance of the installations and the successive improvements incorporated in them are mentioned. The built-in safety characteristics of the reactors are shown by means of an experimental study of their behaviour in transient operation. These studies make it possible to check the validity of the calculation model. The machine calculation programmes can subsequently be used to study the consequences of possible accidents. Special attention is given to the depressurization accident, taking into account the performance of the safety device installed. (author) [French] L'experience acquise'au cours de plusieurs annees d'exploitation des piles G2 et G3 permet de confirmer le haut degre de securite du fonctionnement des piles de la filiere uranium naturel-graphitegaz. Les installations fixes de secours et de securite permettant de pallier, d'une part aux incidents d'exploitation tels que manque d'alimentation du reseau de distribution, arret de soufflage, manque d'alimentation en eau, etc., d'autre part, a des accidents tels que rupture de gaine, echauffements locaux, perte de fluide caloporteur, etc., sont decrites et leur fonctionnement explicite au moyen de schemas de principe. On examine principalement (a) la distribution ''puissance'' et ''controle'' des installations secourues, (b) la distribution d'eau secourue, et (c) la chaine de securite. Les performances et les ameliorations successives apportees a ces installations sont mentionnees. Les caracteristiques intrinseques de securite de ces piles sont mises en evidence par l'etude experimentale de leur comportement en regime transitoire. Ces etudes permettent de s'assurer de la validite de modeles de calcul. Ces programmes de calcul machine peuvent ensuite etre utilises pour l'etude des consequences des accidents possibles. L'accident de depressurisation est particulierement etudie en tenant compte des performances des dispositifs de surete installes. (author) [Spanish] La experiencia adquirida durante varios afios de explotacion de los reactores G2 y G3 permite confirmar el alto grado de seguridad de funcionamiento de los reactores del tipo uranio natural-grafito-anhidrido carbonico. La memoria describe por una parte, las instalaciones fijas de auxilio y de seguridad que permiten superar incidentes tales como falta de alimentacion de la red de distribucion, paro de los sopladores, interrupcion del suministro de agua, etc., y por otra, accidentes com o la ruptura de una vaina, sobrecalentamientos locales, escape del fluido intercambiador de calor, etc.; asimismo, explica su functionamiento por medio de esquemas, examinando principalmente: a) la distribucion ''potencia'' y ''control'' de las instalaciones con sistemas de auxilio, b) la distribucion de agua por sistemas de auxilio; c) la cadena de seguridad. La memoria menciona los rendimientos y las mejoras introducidas sucesivamente en estas instalaciones. El estudio experimental de su comportamiento en regimen transitorio pone en evidencia las caracteristicas de seguridad intrinseca de estos reactores. Estos estudios permiten comprobar la validez del modelo utilizado para el calculo. Los programas para las calculadores pueden servir despues para el estudio de las consecuencias de los posibles accidentes. Estudia en particular la caida de presion accidental, teniendo en cuenta la eficacia de los dispositivos de seguridad instalados. (author) [Russian] Opyt, priobretennyj v techenie neskol'kikh let ehkspluatatsii reaktorov G.2 i G.3, daet vozmozhnost' podtverdit' vysokuyu stepen' bezopasnosti raboty semejstva reaktorov na prirodnom urane, grafite i gaze. Opisyvayutsya ustanovki avarijnoj zashity, kotorye pozvolyaet predotvrashchat', s odnoj storony, takie avarii kak prekrashchenie postupleniya ehlektroehnergii v raspredelitel'nuyu set', ostanovka tsirkulyatsii gaza, prekrashchenie podachi vody i t.d., i, s drugoj storony, takie avarii, kak razrushenie obolochki, mestnye peregrevy, poterya zhidkogo teplonositelya i t.d. Printsipial'nye skhemy dayut ob{sup y}asnenie rabote ehtikh ustanovok. Izuchaetsya, glavnym obrazom, ehlektrosnabzhenie i ''kontrol''' pri avarijnykh situatsiyakh, avarijnoe snabzhenie vodoj i tsepochka avarijnoj zashchity. Ukazyvayutsya posledovatel'nye izmeneniya i uluchsheniya ehtikh ustanovok S pomoshch'yu ehksperimental'nogo issledovaniya povedeniya reaktorov na nestatsionarnom rezhime vyyavlyayutsya vnutrenne prisushchie ehtim reaktoram kharakteristiki zashchity. Issledovaniya pozvolyayut podttverdit' prigodnost' raschetnogo metoda. (author)}
place = {IAEA}
year = {1963}
month = {Oct}
}
title = {Efficiency of the Shut-Down and Safety Equipment and the Kinetic Characteristics of the G2 and G3 Reactors; Efficacite des dispositifs de secours et de securite et caracteristiques cinetiques des piles G2 et G3; Ehffektivnost' sistem avarijnoj zashchity reaktorov G.2 i G.3 i kineticheskie kharakteristiki ehtikh sistem; Caracteristicas cineticas y eficacia de los dispositivos de auxilio y de seguridad de los reactores G2 y G3}
author = {Henri, C., Plisson, J., and Teste duBailler, A.}
abstractNote = {The experience gained in several years of operating the G2 and G3 reactors confirms that natural uranium-graphite-gas reactors are extremely safe. The built-in shut-down and safety mechanisms which minimize operational incidents such as lack of power from the mains, blower failure, lack of water etc., together with accidents such as cladding bursts, local overheating, loss of coolant etc. are described and their operation explained by means of diagrams. The main points examined are as follows: (a) power distribution and controlability during accident conditions; (b) distribution of emergency water; and (c) the safety chain. The performance of the installations and the successive improvements incorporated in them are mentioned. The built-in safety characteristics of the reactors are shown by means of an experimental study of their behaviour in transient operation. These studies make it possible to check the validity of the calculation model. The machine calculation programmes can subsequently be used to study the consequences of possible accidents. Special attention is given to the depressurization accident, taking into account the performance of the safety device installed. (author) [French] L'experience acquise'au cours de plusieurs annees d'exploitation des piles G2 et G3 permet de confirmer le haut degre de securite du fonctionnement des piles de la filiere uranium naturel-graphitegaz. Les installations fixes de secours et de securite permettant de pallier, d'une part aux incidents d'exploitation tels que manque d'alimentation du reseau de distribution, arret de soufflage, manque d'alimentation en eau, etc., d'autre part, a des accidents tels que rupture de gaine, echauffements locaux, perte de fluide caloporteur, etc., sont decrites et leur fonctionnement explicite au moyen de schemas de principe. On examine principalement (a) la distribution ''puissance'' et ''controle'' des installations secourues, (b) la distribution d'eau secourue, et (c) la chaine de securite. Les performances et les ameliorations successives apportees a ces installations sont mentionnees. Les caracteristiques intrinseques de securite de ces piles sont mises en evidence par l'etude experimentale de leur comportement en regime transitoire. Ces etudes permettent de s'assurer de la validite de modeles de calcul. Ces programmes de calcul machine peuvent ensuite etre utilises pour l'etude des consequences des accidents possibles. L'accident de depressurisation est particulierement etudie en tenant compte des performances des dispositifs de surete installes. (author) [Spanish] La experiencia adquirida durante varios afios de explotacion de los reactores G2 y G3 permite confirmar el alto grado de seguridad de funcionamiento de los reactores del tipo uranio natural-grafito-anhidrido carbonico. La memoria describe por una parte, las instalaciones fijas de auxilio y de seguridad que permiten superar incidentes tales como falta de alimentacion de la red de distribucion, paro de los sopladores, interrupcion del suministro de agua, etc., y por otra, accidentes com o la ruptura de una vaina, sobrecalentamientos locales, escape del fluido intercambiador de calor, etc.; asimismo, explica su functionamiento por medio de esquemas, examinando principalmente: a) la distribucion ''potencia'' y ''control'' de las instalaciones con sistemas de auxilio, b) la distribucion de agua por sistemas de auxilio; c) la cadena de seguridad. La memoria menciona los rendimientos y las mejoras introducidas sucesivamente en estas instalaciones. El estudio experimental de su comportamiento en regimen transitorio pone en evidencia las caracteristicas de seguridad intrinseca de estos reactores. Estos estudios permiten comprobar la validez del modelo utilizado para el calculo. Los programas para las calculadores pueden servir despues para el estudio de las consecuencias de los posibles accidentes. Estudia en particular la caida de presion accidental, teniendo en cuenta la eficacia de los dispositivos de seguridad instalados. (author) [Russian] Opyt, priobretennyj v techenie neskol'kikh let ehkspluatatsii reaktorov G.2 i G.3, daet vozmozhnost' podtverdit' vysokuyu stepen' bezopasnosti raboty semejstva reaktorov na prirodnom urane, grafite i gaze. Opisyvayutsya ustanovki avarijnoj zashity, kotorye pozvolyaet predotvrashchat', s odnoj storony, takie avarii kak prekrashchenie postupleniya ehlektroehnergii v raspredelitel'nuyu set', ostanovka tsirkulyatsii gaza, prekrashchenie podachi vody i t.d., i, s drugoj storony, takie avarii, kak razrushenie obolochki, mestnye peregrevy, poterya zhidkogo teplonositelya i t.d. Printsipial'nye skhemy dayut ob{sup y}asnenie rabote ehtikh ustanovok. Izuchaetsya, glavnym obrazom, ehlektrosnabzhenie i ''kontrol''' pri avarijnykh situatsiyakh, avarijnoe snabzhenie vodoj i tsepochka avarijnoj zashchity. Ukazyvayutsya posledovatel'nye izmeneniya i uluchsheniya ehtikh ustanovok S pomoshch'yu ehksperimental'nogo issledovaniya povedeniya reaktorov na nestatsionarnom rezhime vyyavlyayutsya vnutrenne prisushchie ehtim reaktoram kharakteristiki zashchity. Issledovaniya pozvolyayut podttverdit' prigodnost' raschetnogo metoda. (author)}
place = {IAEA}
year = {1963}
month = {Oct}
}