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Ascherl, R.J.
Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. I1963
Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. I1963
AbstractAbstract
[en] Asignificant amount of operating experience has now been accumulated by boiling-water-reactor power plants. By the end of 1962, over 2200 million kWh of electricity have been generated by three plants operating on utility.system - Dresden Nuclear Power Station, Commonwealth Edison Company, Morris, Illinois; Vallecitos Atomic Power Plant, Pacific Gas and Electric Company and General Electric Company, Pleasanton, California; and Kahl Nuclear Power Station, Rheinisch Westfaelisches Elektrizitaetswerk and Bayernwerk, Kahl-am-Main, West Germany. Boiling-water-reactor power-plant performance, under routine electric-utility operating conditions, has been excellent. Reactor and plant availability and capacity factor provide a sound basis for anticipation of continuing reliable performance from boiling-water-reactor power stations. During 1963, four additional boiling-water-reactor plants will begin power operation: Big Rock Point Nuclear Plant, Consumers Power Company, Charlevoix, Michigan; Humboldt Bay Plant Nuclear Unit, Pacific Gas and Electric Company, Eureka, California; Garigliano Nuclear Power Station, Societa Elettronucleare Nazionale, Scauri, Italy; and Japan Power Demonstration Reactor, Japan Atomic Energy Research Institute, Tokai Mura, Japan. The start-up and initial operation of these plants confirms the expectation of reliable performance established by Dresden, Kahl, and Vallecitos. Performance records of Dresden, Kahl and Vallecitos have clearly proved the stability and safety of boiling-water reactors. Additionally, radiation levels within the plant and in the environs have been significantly below limits established by operating licences. Simplicity and ease of operation of boiling-water reactors has been confirmed. Load following characteristics of the Dresden dual-cycle boiling-water reactor have been excellent. Major and minor maintenance and repair work can be accomplished by ordinary craft unions, and without undue hardship or time limits caused by radioactivity exposure considerations. Recent full-scale inspection and overhaul of the Dresden turbine provided no maintenance problems, after over 12 000 h of operation on direct-cycle steam and after operation with known failed fuel elements in the reactor. (author)
[fr]
On a maintenant acquis une experience appreciable dans l'exploitation des centrales equipees de reacteurs a eau bouillante. Vers la fin de 1962, on avait produit plus de 2,2.109 kWh dans trois centrales nucleaires rattachees a des reseaux de distribution: la centrale de Dresden (Commonwealth Edison Company, Morris, Illinois), la centrale de Vallecitos (Pacific Gas and Electric Company and General Electric Company, Pleasanton, Californie) et la centrale de Kahl (Rheinish-Westfaiisches Elektrizitatswerk et Bayemwerk, a Kahl-sur-le-Main, Republique federale d'Allemagne). Le rendement de ces reacteurs a eau bouillante, exploites dans les conditions normales de production d'electricite, est excellent. On peut donc s'attendre que les centrales a eau bouillante continueront d'etre sures, etant donne le facteur de disponibilite et le facteur de puissance des reacteurs et des installations de ce type. Au cours de 1963, quatre nouvelles centrales equipees de reacteurs a eau bouillante entreront en service: la centrale de Big Rock Point (Consumers Power Company, Charlevoix, Michigan), la centrale de Humboldt Bay (Pacific Gas and Electric Company, Eureka, Californie), la centrale de Garigliano (Societa Elettronucleare Nazionale, Scauri, Italie) et la centrale de demonstration japonaise (Institut de recherches nucleaires du Japon, Tokai Mura, Japon). Les resultats obtenus lors du demarrage et pendant le fonctionnement initial de ces installations confirment les espoirs suscites par les centrales de Dresden, Kahl et Vallecitos. Les journaux de marche des centrales de Dresden, Kahl et Vallecitos mettent en evidence la stabilite et la securite des reacteurs a eau bouillante. De plus, les niveaux de rayonnements dans la centrale et aux alentours restent nettement au-dessous des limites fixees par les permis d'exploitation. La simplicite et la facilite d'exploitation des reacteurs a eau bouillante se sont confirmees. La rapidite de reponse du reacteur de Dresden aux variations de la demande est excellente. Aucun des travaux d'entretien et de reparation, quelle que soit leur importance, n'exige de qualification speciale ni ne comporte de risques de radioexposition excessifs. L'inspection generale et la revision de la turbine de la centrale de Dresden n'ont revele aucun probleme d'entretien apres 12 000 h de fonctionnement avec la vapeur en cycle direct. Or, on avait continue l'exploitation apres avoir constate que des cartouches de combustible etaient deteriorees. (author)[es]
El autor sefiala que la experiencia adquirida con la explotacion de centrales nucleoeleonicas que utilizan reactores de agua hirviente es ya bastante considerable. En efecto, al finalizar el aflo 1962 se habian generado mas de 2,2.109 kWh en tres centrales nucleoelectricas integradas en redes de distribucion: la central nucleoelectrica de Dresden (Commonwealth Edison Company, Moriis, Illinois), la central nucleoelectrica de Vallecitos (Pacific Gas and Electric Company, Pleasanton, California) y la central nucleoelectrica de Kahl (Reinisch-Westfalisches Elektrizitatswerk y Bayernwerk A.G., Kahl-am-Main, Republica Federal de Alemania). El rendimiento de estas centrales explotadas en condiciones normales de produccion de electricidad es excelente. Los factores de disponibilidad y de capacidad de los reactores y de las plantas constituyen una base firme para prever que las centrales nucleoelectricas dotadas de reactores de agua hirviente funcionaran a regimen continuo en condiciones de seguridad. En 1963 entraran en servicio cuatro nuevas centrales equipadas con reactores de agua hirviente: la central nucleoelectrica de Big Rock Point (Consumere Power Company, Charlevoix, Michigan), la central nucleoelectrica de Humboldt Bay (Pacific Gas and Electric Company, Eureka, California), la central nucleoelectrica de Garigliano (Societa Elettronucleare Nazionale, Scauri, Italia), y el reactor de potencia japones para fines de demostracion (Instituto de Investigaciones Nucleares, Tokai Mura, Japon). La puesta en marcha y el funcionamiento inicial de estas centrales confirma las esperanzas despertadas por las centrales de Dresden, Kahl y Vallecitos. Los registros de rendimiento de las centrales de Dresden, Kahl y Vallecitos han puesto claramente de manifiesto la estabilidad y seguridad de los reactores de agua hirviente. Ademas, los niveles de radiacion dentro de la central y en sus alrededores se han mantenido muy por debajo de los limites fijados en los permisos de explotacion. Ha quedado confirmada la sencillez y facilidad de explotacion de los reactores de agua hirviente. La rapidez de la respuesta del reactor con doble ciclo de Dresden a las fluctuaciones de la demanda es excelente. Ninguno de los trabajos de conservacion y reparacion, sea cual fuere su importancia, exige calificaciones especiales ni entrana riesgos de irradiacion excesivos. La inspeccion general y la revision de la turbina de la central de Dresden puso de manifiesto la inexistencia de problemas de conservacion despues de mas de 12 000 h de funcionamiento con el vapor en ciclo directo, a pesar de que la explotacion prosiguio despues de haberse comDtobado algunas fallas en los elementos combustibles. (author)[ru]
K nastoyashchemu vremeni priobreten znachitel'nyj opyt v ehkspluatatsii ehlektrostantsij s kipyashchim reaktorom. K kontsu 1962 goda proizvedeno svyshe 2200 mln.kvt.ch ehlektroehnergii na trekh ehlektrostantsiyakh ehnergosistemy kommunal'nogo obsluzhivaniyagna Drezdenskoj atomnoj ehlektrostantsii, ''Kommonvels Ehdison kompani'', Morris, Illinojs, na atomnoj ehlektrostantsii Valleeitos,''Pasifik gaz ehnd ehlektrik kompani'', Plezanton, Kaliforniya, i na Kal'skoj atomnoj ehlektrostantsii, ''Rejnish vestfalishes ehlektritsitetsverk und bajernverk'', Kal'-na-Majne, Zapadnaya Germaniya. Rabochaya kharakteristika kipyashchego reaktora atomnoj ehlektrostantsii pri obychnom rezhime raboty v kommunal'noj ehnergosisteme ochen' khoroshaya. Koehffitsient ispol'zovaniya i moshchnosti reaktora i ehlektrostantsii daet tverdoe osnovanie polagat', chto ehlektrostantsii s kipyashchimi reaktorami yavlyayutsya nadezhnymi s tochki zreniya ikh rabochej kharakteristiki. V techenie 1963 goda budut vvedeny v stroj chetyre dopolnitel'nye ehlektrostantsii s kipyashchimi reaktorami: atomnaya ehlektrostantsiya v Big Rok Pojnt, ''Kons'yumers pauehr kompani'', Sharl'vua, Michigan, atomnaya ehnergeticheskaya ustanovka v KHamboldt Bej, ''Pasifik gaz ehnd ehlektrik kompani'', Yurika, Kaliforniya, atomnaya ehlektrostantsiya v Garig'yano, Natsional'noe obshchestvo po atomnoj ehnergii, Skauri, Italiya,i Yaponskij demonstratsionnyj ehnergeticheskij reaktor. Yaponskij nauchno-issledovatel'skij institut po atomnoj ehnergii, Tokai-Mura, Yaponiya. Pusk i pervonachal'naya ehkspluatatsiya ehtikh ehlektrostantsij podtverzhdayut predpolozhenie o nadezhnosti ikh raboty, chto uzhe prodemonstrirovano atomnymi ehlektrostantsiyami v Drezdene, Kale i Vallesitose. Rabochaya kharakteristika atomnykh ehlektrostantsij v Drezdene, Kale i Vallesitose yavlyaetsya naglyadnym dokazatel'stvom stabil'nosti i bezopasnosti kipyashikh reaktorov. Krome togo, urovni radiatsii na samoj ehlektrostantsii i v okruzhayushchej srede znachitel'no nizhe predelov, ustanovlennykh litsenziyami na ehkspluatatsiyu. Podtverdilis' prostota i legkost' ehkspluatatsii kipyashchikh reaktorov. Kharakteristika kontrolya za nagruzkoj u kipyashchego reaktora s dvojnym tsiklom Drezdenskoj ehlektrostantsii okazalas' ochen' khoroshej. Krupnye i nebol'shie raboty po ukhodu i remontu mogut osushchestvlyat'sya obychnymi remontnymi gruppami bez vrednykh posledstvij ili bez limita vremeni, svyazannymi s soobrazheniyami radioaktivnogo oblucheniya. V rezul'tate provedennykh nedavno polnoj inspektsii i kapital'nogo remonta turbiny Drezdenskoj ehlektrostantsii ne obnaruzheno nikakikh remontnykh problem kak posle bolee 12 000-chasovoj ehkspluatatsii s pryamym parovym tsiklom, tak i posle ehkspluatatsii s zavedomo neispravnymi toplivnymi ehlementami v reaktore. (author)Original Title
Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 540 p; Oct 1963; p. 27-33; Conference on Operating Experience with Power Reactors; Vienna (Austria); 4-8 Jun 1963; ISSN 0074-1884; 

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BWR TYPE REACTORS, ENRICHED URANIUM REACTORS, EQUIPMENT, EXPERIMENTAL REACTORS, LICENSES, MACHINERY, MAINTENANCE, NUCLEAR FACILITIES, OPERATION, POWER PLANTS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SAFETY, STABILITY, START-UP, THERMAL POWER PLANTS, THERMAL REACTORS, TURBOMACHINERY, WATER COOLED REACTORS, WATER MODERATED REACTORS
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Kelly, F.L.; Skovholt, D.J.
Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. II1963
Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. II1963
AbstractAbstract
[en] The current USAEC licensing regulations and procedures for reactor operators at licensed facilities are presented and supplemented by a discussion of the historical development of these practices, particularly as influenced by the advent of nuclear-power generating stations. In addition, a statistical resume and discussion of the operator's backgrounds and qualifications and training programmes used at existing facilities to qualify reactor operators is presented. This data is derived from records of over 200 applicants for operator licences at ten existing nuclearpower stations. (author)
[fr]
Les auteurs exposent les reglements et procedures actuellement appliques par le Commission de l'energie atomique des Etats-Unis a la formation des operateurs de reacteurs dans les centrales autorisees, et ils examinent ensuite l'evolution progressive de ces pratiques, notamment depuis l'entree en service des premieres centrales nucleaires. En outre, ils donnent un apercu statistique, suivi d'une evaluation critique, des connaissances et titres exiges des operateurs ainsi que des programmes de formation appliques dans les installations existantes. Ces renseignements proviennent des dossiers de plus de 200 candidats au permis d'exploiter, constitues dans dix centrales nucleaires en fonctionnement. (author)[es]
En la memoria se exponen las normas y procedimientos seguidos por la Comision de Energia Atomica de los Estados Unidos en la concesion de licencias para operadores de reactor de instalaciones autorizadas, exposicion que se completa con un examen de la evolucion de las practicas seguidas en este terreno, particularmente despues de la entrada en funcionamiento de las primeras centrales nucleoelectricas. Ademas, se presenta un resumen estadistico, seguido por una evaluacion critica, de las aptitudes y los conocimientos exigidos a los operadores, asi como de los programas de formacion aplicados en las instalaciones en funcionamiento para capacitar a los mismos. Estos datos se han extraido de los expedientes de mas de 200 candidatos a la licencia de operador en nueve centrales nucleoelectricas en funcionamiento. (author)[ru]
Predstavleny dejstvuyushchie pravila i protsedura KAEH SSHA po vydache litsenzij dlya operatorov reaktora na litsenzirovannykh ustanovkakh. Obsuzhdaetsya istoricheskoe razvitie ehtikh prakticheskikh pravil, osobenno v svyazi s vliyaniem, okazannym na nikh poyavleniem atomnykh ehlektrostantsij. Krome togo, predstavleny statistichiskie obobshcheniya i materialy obsuzhdeniya voprosov podgotovki operatorov i ikh kvalifikatsii, a takzhe uchebnykh programm, ispol'zuemykh na sushchestvuyushchikh ustanovkakh dlya podgotovki operatorov reaktora. Ispol'zovany svedeniya, poluchennye ot dvukh sot s lishnim kandidatov na poluchenie litsenzij operatora na devyati dejstvuyushchikh yadernykh ehlektrostantsiyakh. (author)Original Title
Formation des operateurs de reacteurs dans les centrales nucleaires et regime des permis d'exploiter; Obuchenie operatorov i vydacha im litsenzij na litsenzirovannykh reaktorakh; Formacion de operadores de reactores de potencia y regimen de las licencias de explotacion
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 428 p; Oct 1963; p. 197-214; Conference on Operating Experience with Power Reactors; Vienna (Austria); 4-8 Jun 1963; ISSN 0074-1884;
; 7 figs., 6 tabs.

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Beattie, W.C.; Freyberg, R.H.
Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. I1963
Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. I1963
AbstractAbstract
[en] Indian Point Station Unit No. 1 consists of a 585 MW(t) pressurized-water reactor, four primary coolant loops with horizontal heat exchanger boilers, two 1.1 million lb/h oil-fired superheaters and a 275 000 kW turbine generator. The reactor fuel is a mixture of fully enriched U235 oxide and Th232 oxide. The station is located on the Hudson River about 24 miles north of New York City. Because of this proximity to New York, exceptional safeguards against the occurrence of a reactivity excursion as well as against the radiation effects of such an excursion were incorporated into the station design. Construction was completed in May 1962. Fuel loading was accomplished in June and the reactor was taken critical for the first time on 2 August 1962. Low power testing up to 5 MW(t) at ambient and at elevated temperatures was done during August, and the turbine generator was first phased into the Consolidated Edison system on 16 September 1962. Testing at reactor power levels up to 50% extended into November and was marked by frequent automatic shut-downs, alarge number of which were initiated inthe conventional plant. Control-rod-drive control system difficulties were the heaviest contributor from the nuclear plant to automatic rod insertion operations and to delays in recovery from automatic trips. On 14 November 1962 the station was shut down for scheduled piping changes in the conventional plant and for modifications and additions to the control-rod-drive system. The latter included the installation of a dry nitrogen purging system for the control-rod-drive housings designed to minimize the effects of seal water leakage into the rod-drive housings. This appears to have been the major cause of the false indications encountered with the reactor control system. The unit was returned to service on 1 January 1963. Testing at reactor power levels up to 100% under steady load conditions was completed on 27 January 1963. Test results have followed closely the predicted performance for the reactor. Further testing of response to load transients is to continue into the Spring of 1963. The Indian Point Station has proved to the satisfaction of our Company the feasibility of a combination nuclear and oil-fired plant to produce competitive power. The United States Atomic Energy Commission has been requested to issue a construction permit for the Company to build another nuclear plant, similar in design, but of 1000 MW capacity, to be located at Ravenswood which is within the corporate limits of the City of New York. Our Company is prepared to finance the venture with its own funds without subsidy of any kind as was the case with our Indian Point Station. (author)
[fr]
La centrale No. 1 d'Indian Point se compose d'un reacteur a eau sous pression de 585 MWt, quatre circuits de refroidissement primaires avec des echangeurs de chaleur horizontaux, deux surchauffeurs au mazout de 500 000 kg/h et un turbogenerateur de 275 000 kW. Le combustible du reacteur est un melange d'oxyde d'uranium completement enrichi en 235U et d'oxyde de 232Th. L'installation se trouve au bord de l'Hudson a une quarantaine de kilometres au nord de New York. En raison de la proximite de cette ville, on a prevu des dispositifs de securite intrinseques exceptionnels contre le risque d'un emballement du reacteur et contre les rayonnements qui pourraient en resulter. La construction a ete terminee en mai 1962. Le combustible a ete charge en juin et le reacteur est entre en divergence pour la premiere fois le 2 aout 1962. On a ensuite procede, dans le courant du mois d'aout, a des essais a faible puissance (jusqu'a 5 MWt), a la temperature ambiante et a .des temperatures elevees. Le turbogenerateur aeteintegre pour la premiere fois au reseau de la ''Consolidated Edison'', le 16 septembre 1962. Les essais aux puissances allant jusqu'a 50% de la puissance theorique se sont prolonges jusqu'en novembre et ont ete marques par de frequents arrets automatiques dont un grand nombre avaient leur origine dans le secteur ''classique'' de la centrale. Ce sont surtout des defectuosites du systeme de commande des barres de controle qui, dans le secteur nucleaire, ont contribue a la chute automatique des barres et aux retards dans la remise en marche apres arret. Le 14 novembre 1962, on a arrete la centrale pour proceder aux changements prevus dans les tuyauteries de la partie classique et pour apporter des modifications ou additions aux organes de commande des barres de reglage (installation d'un purgeur a azote sec pour les logements des organes de commande, afin de reduire les effets des fuites d'eau a travers les joints), n semble que c'etait la la cause principale du mauvais fonctionnement du systeme. La centrale a ete remise en service le 1er janvier 1963. Les essais, jusqu'a 100% de la puissance theorique a charge constante, etaient termines le 27 janvier 1963. Les resultats concordent parfaitement avec les previsions. De nouveaux essais pour etudier la maniere dont le reacteur repond a des variations subites de la demande se poursuivront au printemps 1963. (author)[es]
El grupo No. 1 de la central de Indian Point consta de un reactor de 585 MW(t), de agua a presion cuatro circuitos refrigerantes primarios con intercambiadores de calor horizontales, dos sobrecalentadores a petroleo de 500 000 kg/h y un turbogenerador de 275 000 kW. El combustible del reactor consiste en una mezcla de oxido de 235U totalmente enriquecido y de oxido de 232T. La central se encuentra a orillas del rio Hudson, a uno 40 km al norte de Nueva York. Debido a la proximidad de esa ciudad se adoptaron dispositivos especiales de seguridad intrinseca para evitar saltos bruscos de reactividad y- prevenir sus efectos radiologicos. La construccion quedo terminada en mayo de 1962. Se cargo el combustible en junio y el reactor alcanzo la criticidad inicial el 2 de agosto de 1962. En el curso del mismo mes, se efectuaron los ensayos de baja potencia, hasta 5 MW(t), a la temperatura ambiente y a temperaturas elevadas, y el 16 de septiembre de ese ano el turbogenerador se conecto por primera vez a la red de la Consolidated Edison. Hasta entrado el mes de noviembre, prosiguieron los ensayos a potencias de hasta 50% del valor teorico, con frecuentes detenciones automaticas, originadas en gran parte por perturbaciones en la seccion ''clasica'' de la central. En cuanto a la seccion nuclear, fueron sobre todo las fallas del mecanismo de mando de las barras de control que contribuyeron a la caida automatica de las barras y a las demoras en la reiniciacion de la marcha despues del paro. El 14 de noviembre de 1962 se detuvo la marcha de la central para proceder a los cambios previstos en las tuberias de la seccion ''clasica'' y para modificar y perfeccionar el mecanismo de mando de las barras de control. Esta ultima operacion comprendia la instalacion de un dispositivo de purga a base de nitrogeno seco para las cajas de los mecanismos de las barras de control, a fin de reducir al minimo los efectos de los escapes de agua, a traves de las juntas. Al parecer, dichas perdidas eran la causa principal de las indicaciones erroneas registradas en el sistema de control del reactor. La central se volvio a poner en servicio el lc de enero de 1963. El 27 de enero de 1963, se dio fin a los ensayos del reactor, con potencias hasta el 100%, en condiciones de carga constante. Los resultados de los ensayos concordaron satisfactoriamente con las previsiones. En la primavera de 1963 se continuaran las pruebas, para estudiar la manera en que el reactor responde a fluctuaciones rapidas de la demanda. (author)[ru]
Blok No. 1 Indian-pojntskoj yadernoj ehlektrostantsii sostoit iz reaktora s vodoj pod davleniem moshchnost'yu 585 mgvt, chetyrekh pervichnykh konturov okhlazhdeniya s gorizontal'nymi teploobmennikami, dvukh rabotayushchikh ka nefti paroperegrevatelej proizvoditel'nost'yu 1 100 tys. funtov/chas i turbogeneratora moshchnost'yu 275 tys. kvt. Toplivom v reaktore sluzhit smes' polnost'yu obogashchennoj okisi U235 i okisi Th232. Stantsiya raspolozhena na reke Gudzon, primerno v 24 milyakh severnee N'yu-Jorka. V svyazi s takoj blizost'yu ot N'yu-Jorka v proekte stantsii byli predusmotreny dopolnitel'nye predokhranitel'nye ustrojstva dlya predotvrashcheniya otkloneniya reaktivnosti i radiatsionnykh ehffektov takogo otkloneniya. Stroitel'stvo zakoncheno v mae 1962 goda. Zagruzka topliva osushchestvlena v iyune, a 2 avgusta 1962 goda reaktor vpervye dostig kritichnosti. V techenie avgusta privodilis' ispytaniya ka maloj moshchnosti do 5 mgvt pri temperature okrukhaitsej sredy i povyshennoj temperature. 16 sentyabrya 1962 goda turbogenerator byl vpervye fazirovan s sistemoj Konsolidejtid Ehdison. Ispytanie reaktora na moshchnostyakh do 50% provodilos' do noyabrya i preryvalos' chastymi avtomaticheskimiostanovkami, bol'shaya chast' kotorykh byla vyzvana nepoladkami v neyadernoj chasti stantsii. Nepoladki v sisteme upravleniya privodov reguliruyushchikh sterzhnej byli samymi ser'eznymi pomekhami so storony yadernoj chasti stantsii dlya raboty s avtomaticheskim vvedeniem reguliruyushchikh sterzhnej i prichinoj zaderzhek s puskom reaktora posle avtomaticheskikh ostanovok. 14 noyabrya 1962 goda stantsiya byla ostanovlena dlya planovoj zameny truboprovodov v neyadernoj chasti stantsii i modifikatsij i dopolneniya sistemy provodov reguliruyushchikh sterzhnej. Poslednee vklyuchalo ustanovku sistemy ochistki sukhogo azota dlya kozhukhov privodov reguliruyushchikh sterzhnej, prednaznachennykh dlya svedeniya k minimumu ehffektov vody, prosachivayushchejsya cherez uplotneniya v kozhukhi reguliruyushchikh sterzhnej. Okazalos', chto ehto yavlyaetsya osnovnoj prichinoj nepravil'nykh pokazanij sistemy upravleniya reaktorom. Blok byl vnov' pushchen 1 yanvarya 1963 goda. Ispytanie reaktora na moshchnostyakh do 100% v usloviyakh stabil'noj nagruzki bylo zakoncheno 27 yanvarya 1963 goda. Rezul'taty ispytanij ochen' khorosho soglasuyutsya s raschetnymi kharakteristikami raboty reaktora. Sleduyushchie ispytaniya chuvstvitel'nosti reaktora k perekhodnym kolebaniyam nagruzki dolzhny byt' prodolzheny vesnoj 1963 goda. (author)Original Title
Experience d'exploitation de la centrale nucleaire d'Indian point; Opyt ehkspluatatsii Indian-pojntskoj yadernoj ehlektrostantsii; Experiencia adquirida con la explotacion de la central nucleoelectrica de Indian point
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 540 p; Oct 1963; p. 307-323; Conference on Operating Experience with Power Reactors; Vienna (Austria); 4-8 Jun 1963; ISSN 0074-1884;
; 5 figs.

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ACCIDENTS, ACTINIDE COMPOUNDS, ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, CHALCOGENIDES, CONTROL SYSTEMS, COOLING SYSTEMS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, EQUIPMENT, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, HEAVY NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, KINETICS, LICENSES, MACHINERY, MINUTES LIVING RADIOISOTOPES, NUCLEI, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, PWR TYPE REACTORS, RADIOISOTOPES, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, THERMAL REACTORS, THORIUM COMPOUNDS, THORIUM ISOTOPES, TURBOMACHINERY, URANIUM COMPOUNDS, URANIUM ISOTOPES, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
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Cantel, J.; Fruchard, Y.; Lavie, J.-M.; Leclerc, J.; Michel, P.; Nollet, P.G.
Criticality Control Fissile of Materials. Proceedings of the Symposium on Criticality Control of Fissile Materials1966
Criticality Control Fissile of Materials. Proceedings of the Symposium on Criticality Control of Fissile Materials1966
AbstractAbstract
[en] The operation of various French installations using fissile materials has enabled us to work out a number of rules for dealing with criticality hazards. In this connection it is useful to distinguish two stages in the study of the nuclear safety of an installation, viz. the design stage and the operational stage. In the design stage it is emphasized that the safety studies should be carried out in conjunction with the design work on the installation from the very outset ; project directors should therefore always be kept informed of the latest available data on criticality problems. It is also important to decide as soon as possible what type of control system (concentration, mass, geometry) to use in particular sections of the installation. The various sections of an installation being interdependent, one can in this way devise an over-all solution to the safety problem by locating the controls at the most suitable points. When deciding what type of control system to use, it is essential to aim at the highest possible degree of inherent safety and, particularly where solutions are involved, to make the maximum use of favourable geometries, to the extent that economic considerations permit. In the operational stage, the important thing is to work out and distribute instructions for dealing with the problem of criticality. These instructions should provide clear information on the method of control adopted, the limitations imposed and the procedures to be used for ensuring the latter. To make sure that the instructions are properly understood and applied, operating staff should be briefed on the implications of the criticality hazard and the methods to be used for averting the dangers involved. (author)
[fr]
L'exploitation de quelques installations françaises mettant en oeuvre des matières fissiles nous a permis de dégager certaines règles concernant la sûreté en matière de criticité. Il est utile, pour présenter ces règles, de distinguer deux phases dans l'évolution de l'étude de la sûreté nucléaire: la phase de conception et la phase d'exploitation d'une installation. Au stade de la conception, il faut d'abord souligner l'intérêt qu'il y a à mener de front, et dès le départ, les études de sûreté et le projet de l'installation: c'est pourquoi l e responsable d'un projet devra être tenu au courant des derniers résultats connus en matière de criticité. Il est important également de définir dès que possible le mode de contrôle (concentration, masse, géométrie) qui sera adopté dans telle ou telle partie de l'usine: les différentes parties de l'usine étant dépendantes, cela permet, en prévoyant les moyens de contrôle aux emplacements les plus adaptés, de résoudre le problème de sûreté dans son ensemble. Lors de cette définition du mode de contrôle, il est essentiel de rechercher la sûreté intrinsèque la plus grande possible, et, en particulier lorsque l'on a affaire à des solutions, d'employer au maximum la géométrie favorable, compte tenu des impératifs économiques. Au stade de l'exploitation, le travail essentiel est la définition et la diffusion des consignes de criticité. Ces consignes doivent faire ressortir clairement le mode de contrôle adopté, la limitation imposée et les moyens mis en oeuvre pour garantir cette limitation. Afin d'assurer une bonne compréhension et une bonne application des consignes par le personnel d'exploitation, il est utile d'informer celui-ci des dangers présentés par le risque de criticité et des moyens de prévenir ce risque. (author)Original Title
Conception et Exploitation d'Ensembles Industriels Presentant des Risques de Criticite: Experience Tiree de Realisations Françaises
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Source
International Atomic Energy Agency, Vienna (Austria); 772 p; May 1966; p. 411-417; Symposium on Criticality Control of Fissile Materials; Stockholm (Sweden); 1-5 Nov 1965; IAEA-SM--70/20; ISSN 0074-1884;
; 6 refs.

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[en] The Japan Atomic Energy Commission (JAEC) has issued ''A Guide to Reactor Site Evaluation'' to provide a provisional criterion for site selection. The basic idea of the guide is that even if a certain postulated accident occurred which released fission products, the public in the surrounding area should not suffer from radiation hazards. ''Major accident'' and ''hypothetical accident'' are defined as postulated accidents; the former is connected with a non-residential area and the latter with a low-population area and population centre distance. In a safety analysis such as this, the method of evaluation of meteorological conditions is as important as the assumption of an accident. Therefore the JAEC has issued ''Meteorological Guidance for Reactor Safety Analysis'', This document states that the meteorological conditions should be selected by the statistical processing of observed data, so that if other conditions are selected the results may not become more severe. Construction permits for three commercial power reactors have recently been granted after JAEC examined the safety of the reactors according to the two JAEC documents mentioned above. The data, derived from many conservative premises, seem to show that site selection for a light-water reactor is not a problematic matter in Japan as long as it concerns the safety estimated by accident analysis. On the other hand, however, waste disposal and its treatment may be a problem affecting the site selection of a reactor. The proximity of reactors to population centres seems to present a problem, owing to the fear of the Japanese of radiation hazards. (author)
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International Atomic Energy Agency, Vienna (Austria); 836 p; Sep 1967; p. 19-33; Symposium on the Containment and Siting of Nuclear Power Plants; Vienna (Austria); 3-7 Apr 1967; IAEA-SM--89/25; ISSN 0074-1884;
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Technical specifications
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3 Apr 1967; 127 p
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CONNECTICUT YANKEE REACTOR, CONTAINMENT, DOCUMENTATION, ECCS, EQUIPMENT PROTECTION DEVICES, GASEOUS WASTES, HEAT TRANSFER, INSPECTION, LEAKS, LIQUID WASTES, MANAGEMENT, PRESSURE VESSELS, PRESSURIZERS, PUMPS, RADIOACTIVE WASTES, REACTIVITY, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTOR CORES, REACTOR FUELING, REACTOR INSTRUMENTATION, REACTOR LICENSING, REACTOR OPERATION, REACTOR SAFETY, REACTOR SITES, SPECIFICATIONS, STEAM GENERATORS, TESTING, TURBINES, VALVES
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20 Jun 1967; 24 p; DOCKET-50270--59; DOCKET-50287--51
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Ringhals kraftstation. Koncessionsansoekan med beskrivning
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Mar 1967; 101 p
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24 Jun 1968; 12 p; DOCKET-50306--59
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26 Nov 1968; 621 p
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