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AbstractAbstract
[en] Full text: The first electricity from nuclear power was produced by a fast reactor - EBR-1 - in the United States in 1951, 28 years ago. Since that time extensive development work has been done in many countries in the field of fast breeder reactor physics. Large scale development programmes on liquid metal fast breeder reactors (LMFBR) are being carried out in Belgium, Federal Republic of Germany, France, India, Italy, Japan, the Netherlands, UK, USA and USSR, resulting in a number of important experimental sodium-cooled fast reactors, e.g. Rapsodie in France, KNK-2 in the Federal Republic of Germany, JOYO in Japan, EBR-2 in the USA, BOR-60 in the USSR. Operating experience with the first fast breeder demonstration power stations is being accumulated with the BN-350 in the USSR, Phenix in France and PFR in the United Kingdom. A number of experiments are being carried out at zero power fast test facilities such as BFS (USSR), FCA (Japan), MASURCA (France), ZEBRA (UK), ZPPR (USA), SNEAK (FRG) and others. The 400 MW(th) fast breeder FFTF in the USA, designed for irradiation testing of fast breeder reactor fuels and materials is expected to operate at full power in March 1980 and the commissioning of the USSR fast breeder reactor BN-600 (600 MWe) will be started this year. Therefore, the purpose of the symposium was to review the experience gained in the field of fast reactor physics since the last International Symposium on 'Physics of Fast Reactors' which was held in Tokyo in 1973, in order that this experience may be fully utilized in the design, construction and operation of new power stations incorporating such reactors. The papers presented at the symposium covered 5 main topics: physics of conventional cores of large fast power reactors, physics of operating fast reactors, physics of burn-up in fast reactors, experimental studies on heterogeneous fast reactor cores and improvements and optimization of large fast power reactors. They reviewed the extensive experience gained in the field of fast reactor physics since the last international symposium on the subject. It was shown that conceptual design of large power reactor cores is under development in many countries. The design work is being supported by experiments carried out at zero power fast test facilities and at operating experimental and prototype or demonstration reactors. The increasing tendency is to use prototype reactors. Though the adjustment of neutron capture cross-section is progressing, the uncertainties of actinides and structural materials cross-sections could lead to errors in the design of large power reactor cores and influence the breeding ratio prediction. There are difficulties in extrapolating from experiments on small critical facilities to the larger volumes of power reactors; this applies especially to control rods, and their interactions. The sodium void coefficient increases with increasing core size and therefore fast power reactors with large conventional cores require more rigid safety and reliability requirements. Assessments of accuracy calculations for reactivity parameters, Doppler effect and sodium void coefficient (the main safety related characteristics) are being made in different countries. A number of countries are also conducting experiments on critical facilities to model the possible consequences of hypothetical accidents. The breeding characteristics of the first mixed-oxide fuelled LMFBRs are expected to be moderate. But it was clearly shown at the meeting that Phenix already has a breeding ratio of 113 based on chemical analysis of reprocessed fuel elements. This is positive experimental confirmation of a better breeding ratio than was predicted a few years ago. It was also shown that there is considerable scope for further improvement of safety-related and breeding performance characteristics of fast reactors by using advanced oxide fuels, by improved core design, such as heterogeneous cores and by application of an improved external fuel cycle. The mam effort is expected to continue to concentrate on homogeneous, mixed oxide-fuelled cores. However, considerable effort is being made to determine the extent to which heterogeneous cores can improve breeding ratio and safety-related characteristics for a somewhat larger core size At this stage of development it is premature to judge the advantages or disadvantages of different conventional and heterogeneous cores. There are different approaches in a number of countries to designing large power reactor cores: the USA considers safety-related aspects more thoroughly, the USSR considers the problem from the standpoint of breeding and France prefers to tackle economic aspects. Heterogeneous cores could improve safety related characteristics of fast reactors, fluence, doubling time depending on the initial preconditions. For example, the central fertile zone has considerable effect on the leakage term and consequently on the sodium void reactivity effect. Of course in order to implement promising new concepts it will be necessary to solve a number of additional engineering problems, thermohydraulics problems, economic problems and so on. It is a difficult task but by the turn of the century it could be possible to demonstrate the real potential of fast breeder reactors. (author)
Primary Subject
Source
IAEA/NEA international symposium on fast reactor physics; Aix-en-provence (France); 24-28 Sep 1979; Available on-line: http://www.iaea.org/Publications/Magazines/Bulletin/Bull216/21604787677.pdf
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
AIR COOLED REACTORS, BREEDER REACTORS, COMMISSIONING, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, GAS COOLED REACTORS, KINETICS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, NAK COOLED REACTORS, PHYSICS, PLUTONIUM REACTORS, POTASSIUM COOLED REACTORS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, SODIUM COOLED REACTORS, TEST FACILITIES, TEST REACTORS, ZERO POWER REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Furet, J.; Landauer, C.
CEA Saclay, 91 - Gif-sur-Yvette (France)
CEA Saclay, 91 - Gif-sur-Yvette (France)
AbstractAbstract
[en] This catalogue consists of tables (one per reactor) giving the following information: number and type of detectors, range of the shutdown channels, nature of the associated electronics, thresholds setting off the alarms, fitted interlocks. These cards have been drawn up with a view to an examination of the reactors safety by the 'Reactor Safety Sub-Commission', they take into account the latest decisions. The reactors involved in this review are: Azur, Cabri, Castor-Pollux, Cesar-Marius-2, Edf-2, EL3, EL4, Eole, G1, G2-G3, Harmonie, Isis, Masurca, Melusine, Minerve, Osiris, Pegase, Peggy, PAT, Rapsodie, SENA, Siloe, Siloette, Triton-Nereide, and Ulysse. (authors)
[fr]
Ce catalogue est compose d'un ensemble de tableaux (a raison de un tableau par pile) donnant les renseignements suivants: nombre et nature des detecteurs, dynamique des chaines, nature de l'electronique associee, seuils provoquant des actions de securite, verrouillages installes. Ces fiches ont ete etablies en vue de l'examen de la securite des piles par la 'Sous-Commission de Surete des Piles', et tiennent compte des decisions de celle-ci. Les reacteurs concernes sont: Azur, Cabri, Cator-Pollux, Cesar-Marius-2, Edf-2, EL3, EL4, Eole, G1, G2-G3, Harmonie, Isis, Masurca, Melusine, Minerve, Osiris, Pegase, Peggy, PAT, Rapsodie, SENA, Siloe, Siloette, Triton-Nereide, et Ulysse. (auteurs)Original Title
Chaines de securite et verrouillages installes sur les piles atomiques
Primary Subject
Source
1968; [28 p.]
Record Type
Report
Report Number
Country of publication
ALARM SYSTEMS, ARDENNES REACTOR, CABRI REACTOR, CESAR REACTOR, CHINON-2 REACTOR, EMERGENCY PLANS, EOLE REACTOR, HARMONIE REACTOR, HISTORICAL ASPECTS, ISIS REACTOR, MASURCA REACTOR, MELUSINE-1 REACTOR, MINERVE REACTOR, OSIRIS REACTOR, PEGASE REACTOR, PEGGY REACTOR, RAPSODIE REACTOR, REACTOR CONTROL SYSTEMS, REACTOR MONITORING SYSTEMS, REACTOR SAFETY, REACTOR SHUTDOWN, SILOE REACTOR, SILOETTE REACTOR, TRITON REACTOR, ULYSSE REACTOR
AIR COOLED REACTORS, ARGONAUT TYPE REACTORS, BREEDER REACTORS, CARBON DIOXIDE COOLED REACTORS, CONTROL SYSTEMS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, GAS COOLED REACTORS, GCR TYPE REACTORS, GRAPHITE MODERATED REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS TESTING REACTORS, NATURAL URANIUM REACTORS, PLUTONIUM REACTORS, POOL TYPE REACTORS, POWER REACTORS, PWR TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SAFETY, SHUTDOWN, SODIUM COOLED REACTORS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, TRAINING REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZERO POWER REACTORS
Publication YearPublication Year
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INIS IssueINIS Issue
AbstractAbstract
[en] Regular inspections were carried out in 17 reactor facilities for test and research. As for the experimental FBR 'Joyo' and the ATR 'Fugen', the report was made separately. Besides, JRR-3 reactor facility is under reconstruction at present. On respective reactor facilities, the appearance inspection of reactor vessels, the inspection of the functioning of reactor stop, interlocking system and alarm, the inspection of confirming the effect of reactivity control, excessive reactivity and the storage capacity of fuel storage facilities, the inspection of the treatment capacity of radioactive waste facilities, the inspection of confirming the negative pressure in reactor buildings, the inspection of the functioning of emergency power sources, the inspection of measuring radiation dose rate and the concentration of radioactive substances and so on were carried out, and all the facilities passed the inspections. The main repair works were the addition of pulse operation and the repair of a transient rod in NSRR reactor facilities, and the repair of heavy water pipe leak and the renewal of heat exchangers in KUR. The exposure dose accompanying the regular inspections was sufficiently low within the limit of the relevant laws in all the facilities. (K.I.)
Primary Subject
Record Type
Journal Article
Journal
Country of publication
ARGONAUT TYPE REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HELIUM COOLED REACTORS, HOMOGENEOUS REACTORS, HTGR TYPE REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MAINTENANCE, MATERIALS TESTING REACTORS, MIXED SPECTRUM REACTORS, POOL TYPE REACTORS, POWER REACTORS, PULSED REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, TRAINING REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZERO POWER REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The report presents the 1986 operating results of the nuclear power reactors in the Federal Republic of Germany. The material is arranged by the names of power stations. The survey also includes reports about two nuclear power stations in Finland, three in Sweden, and three in Switzerland. (UA)
[de]
Es wird abschnittsweise ueber die 1986 in der Bundesrepublik Deutschland in Betrieb befindlichen Leistungsreaktoren berichtet. Angeschlossen sind die Berichte ueber 2 finnische Reaktoren, 3 schwedische Reaktoren und 3 schweizerische Reaktoren. (UA)Original Title
Betriebserfahrungen mit Kernkraftwerken 1986
Primary Subject
Record Type
Journal Article
Journal
Country of publication
AVR REACTOR, BEZNAU-1 REACTOR, BEZNAU-2 REACTOR, BIBLIS REACTOR, BIBLIS-B REACTOR, BROKDORF REACTOR, BRUNSBUETTEL REACTOR, FEDERAL REPUBLIC OF GERMANY, GOESGEN REACTOR, GRAFENRHEINFELD REACTOR, GROHNDE REACTOR, GUNDREMMINGEN-2 REACTOR, GUNDREMMINGEN-3 REACTOR, ISAR REACTOR, KNK-2 REACTOR, KRUEMMEL REACTOR, NECKAR REACTOR, NECKAR-2 REACTOR, OBRIGHEIM REACTOR, OKG-1 REACTOR, OKG-2 REACTOR, OKG-3 REACTOR, PHILIPPSBURG-1 REACTOR, PHILIPPSBURG-2 REACTOR, POWER REACTORS, REACTOR OPERATION, STADE REACTOR, THTR-300 REACTOR, TVO-1 REACTOR, TVO-2 REACTOR, UNTERWESER REACTOR, WUERGASSEN REACTOR
BWR TYPE REACTORS, DEVELOPED COUNTRIES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EUROPE, EXPERIMENTAL REACTORS, FAST REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HOMOGENEOUS REACTORS, HTGR TYPE REACTORS, HYDRIDE MODERATED REACTORS, LIQUID METAL COOLED REACTORS, OPERATION, PEBBLE BED REACTORS, PWR TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, SOLID HOMOGENEOUS REACTORS, SZR TYPE REACTORS, THERMAL REACTORS, THORIUM REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Pong, E.L.
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Plant
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Plant
AbstractAbstract
[en] Reactor Incident followup action is summarized through periodic status reports. This annual report summarizes action taken or anticipated for Reactor Incidents through December, 1985 for Reactors C, K, L, and P
Primary Subject
Source
31 Mar 1986; 256 p; Available from NTIS, PC A12/MF A01; 1 as DE87006290; Portions of this document are illegible in microfiche products.
Record Type
Report
Literature Type
Progress Report
Report Number
Country of publication
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In this second section of reports from the world's nuclear power station sites, a very brief summary is given of experience gained from stations which have been in commercial operation and those recently commissioned. The reactors, which are listed under country, included: Pickering NGS-A, Phenix, Rapsodie, Obrigheim, Brunsbuettel, Biblis B, Wuergassen, Gundremmingen, Stade, Rajasthan, Takahama 1 and 2, Mihama 1, Mihama 2, Tokai 2, Tsuruga, Borssele, Muehleberg, Prototype Fast Reactor, Hinkley Point B, Hunterston A, Hunterston B, Port St. Vrain, Pilgrim, San Onofre-1. (U.K.)
Primary Subject
Record Type
Journal Article
Journal
Nuclear Engineering International; v. 22(256); p. 64-67
Country of publication
BIBLIS-B REACTOR, BORSSELE REACTOR, BRUNSBUETTEL REACTOR, HINKLEY POINT-B REACTOR, HUNTERSTON-A REACTOR, HUNTERSTON-B REACTOR, MIHAMA-1 REACTOR, MIHAMA-2 REACTOR, MUEHLEBERG REACTOR, NUCLEAR POWER PLANTS, OBRIGHEIM REACTOR, PFR REACTOR, PHENIX REACTOR, PICKERING-4 REACTOR, PILGRIM REACTOR, RAJASTHAN-1 REACTOR, RAPSODIE REACTOR, REACTOR OPERATION, RWE-BAYERNWERK REACTOR, SAN ONOFRE-1 REACTOR, STADE REACTOR, TAKAHAMA-1 REACTOR, TAKAHAMA-2 REACTOR, TOKAI-MURA REACTOR, TSURUGA REACTOR, VRAIN REACTOR, WUERGASSEN REACTOR
AGR TYPE REACTORS, BREEDER REACTORS, BWR TYPE REACTORS, CANDU TYPE REACTORS, CARBON DIOXIDE COOLED REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, GAS COOLED REACTORS, GCR TYPE REACTORS, GRAPHITE MODERATED REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HTGR TYPE REACTORS, LIQUID METAL COOLED REACTORS, MAGNOX TYPE REACTORS, NATURAL URANIUM REACTORS, NUCLEAR FACILITIES, OPERATION, PHWR TYPE REACTORS, PLUTONIUM REACTORS, POWER PLANTS, POWER REACTORS, PRESSURE TUBE REACTORS, PWR TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, TEST REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Within the VGB Technical Committee 'Exchange of Operating Experience' (ABE), a regular exchange of experience has been cultivated for more than 25 years. It involves 28 nuclear power plants in Germany, Finland, France, The Netherlands, Sweden, Switzerland and Spain. This paper reports operating results obtained in 1996 and safety-related incidents, important retrofit measures and annual discharge rates of radioactivity. (orig.)
[de]
Innerhalb des VGB-Fachausschusses 'Austausch von Betriebserfahrungen' - ABE - (Kerntechnik) wird seit mehr als 25 Jahren ein reger Erfahrungsaustausch gepflegt. Er schliesst 36 Kernkraftwerke in Deutschland, Finnland, Frankreich, den Niederlanden, Schweden, der Schweiz und Spanien ein. Ueber die im Jahre 1996 erzielten Betriebsergebnisse sowie ueber sicherheitsrelevante Ereignisse, wichtige Umruestmassnahmen und Jahresabgaberaten an Radioaktivitaet wird berichtet. (orig.)Original Title
Betriebserfahrungen mit Kernkraftwerken 1996
Primary Subject
Record Type
Journal Article
Journal
Country of publication
BARSEBAECK-1 REACTOR, BARSEBAECK-2 REACTOR, BEZNAU-1 REACTOR, BEZNAU-2 REACTOR, BIBLIS-1 REACTOR, BORSSELE REACTOR, BROKDORF REACTOR, BRUNSBUETTEL REACTOR, EMSLAND REACTOR, FEDERAL REPUBLIC OF GERMANY, FINLAND, GOESGEN REACTOR, GRAFENRHEINFELD REACTOR, GROHNDE REACTOR, GUNDREMMINGEN-2 REACTOR, GUNDREMMINGEN-3 REACTOR, ISAR REACTOR, ISAR-2 REACTOR, KRUEMMEL REACTOR, LEIBSTADT REACTOR, MUELHEIM-KAERLICH REACTOR, NECKAR-1 REACTOR, NECKAR-2 REACTOR, NETHERLANDS, NUCLEAR POWER PLANTS, OBRIGHEIM REACTOR, OKG-1 REACTOR, OKG-2 REACTOR, OKG-3 REACTOR, PHILIPPSBURG-1 REACTOR, PHILIPPSBURG-2 REACTOR, POWER REACTORS, REACTOR OPERATION, RINGHALS-1 REACTOR, RINGHALS-2 REACTOR, RINGHALS-3 REACTOR, RINGHALS-4 REACTOR, SPAIN, STADE REACTOR, SWEDEN, SWITZERLAND, TRILLO-1 REACTOR, TVO-1 REACTOR, TVO-2 REACTOR, UNTERWESER REACTOR, WUERGASSEN REACTOR
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The survey presents the operating results and experience of the year 1989, of nuclear power plants in West Germany, Finland, the Netherlands, Sweden, Switzerland, and Spain. A summarizing brief account and aggregated operating data set out in tables are given, followed by individual reports on the power stations under review, each including the 1989 annual operating log. (UA)
[de]
Im vorliegenden Bericht werden die Betriebsergebnisse des Jahres 1989 der in der Bundesrepublik Deutschland, in Finnland, den Niederlanden, in Schweden, der Schweiz und in Spanien betriebenen Kernkraftwerke zusammenfassend dargestellt. Nach einem einleitenden Ueberblick werden abschnittsweise die einzelnen Kernkraftwerke behandelt, wobei neben anderen Abbildungen jeweils die Betriebsdiagramme 1989 wiedergegeben werden. (UA)Original Title
Betriebserfahrungen mit Kernkraftwerken 1989
Primary Subject
Record Type
Journal Article
Journal
Country of publication
AVR REACTOR, BEZNAU-1 REACTOR, BEZNAU-2 REACTOR, BIBLIS REACTOR, BIBLIS-B REACTOR, BORSSELE REACTOR, BROKDORF REACTOR, BRUNSBUETTEL REACTOR, DIAGRAMS, EMSLAND REACTOR, FEDERAL REPUBLIC OF GERMANY, FINLAND, GOESGEN REACTOR, GRAFENRHEINFELD REACTOR, GROHNDE REACTOR, GUNDREMMINGEN-2 REACTOR, GUNDREMMINGEN-3 REACTOR, ISAR REACTOR, ISAR-2 REACTOR, KNK-2 REACTOR, KRUEMMEL REACTOR, LEIBSTADT REACTOR, MUELHEIM-KAERLICH REACTOR, NECKAR REACTOR, NECKAR-2 REACTOR, NETHERLANDS, NUCLEAR POWER PLANTS, OBRIGHEIM REACTOR, OKG-1 REACTOR, OKG-2 REACTOR, OKG-3 REACTOR, PHILIPPSBURG-1 REACTOR, PHILIPPSBURG-2 REACTOR, POWER REACTORS, REACTOR OPERATION, RINGHALS-1 REACTOR, RINGHALS-2 REACTOR, RINGHALS-3 REACTOR, RINGHALS-4 REACTOR, SPAIN, STADE REACTOR, SWEDEN, SWITZERLAND, THTR-300 REACTOR, TRILLO-1 REACTOR, TVO-1 REACTOR, TVO-2 REACTOR, UNTERWESER REACTOR, WUERGASSEN REACTOR
BWR TYPE REACTORS, DEVELOPED COUNTRIES, DEVELOPING COUNTRIES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EUROPE, EXPERIMENTAL REACTORS, FAST REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HOMOGENEOUS REACTORS, HTGR TYPE REACTORS, HYDRIDE MODERATED REACTORS, INFORMATION, LIQUID METAL COOLED REACTORS, NUCLEAR FACILITIES, OPERATION, PEBBLE BED REACTORS, POWER PLANTS, PWR TYPE REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SCANDINAVIA, SODIUM COOLED REACTORS, SOLID HOMOGENEOUS REACTORS, SZR TYPE REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, THORIUM REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Full text: In 1997 RA reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor
[sr]
kompletan tekst: U 1997 godini reaktor Ra nije bio u pogonu. Nova instrumentacija nije kompletna, a bez nje se ne moze ni pomisljati o pustanju reaktora u pogon. Od 1985, kada je reaktoru RA zabranjem rad u jezgru reaktora ostalo je 480 gorivnih elemenata u 48 tehnoloskih kanala. Zbog remonta teskovodnih pumpi 1986. godine, ispustena je sva teska voda iz jezgra reaktora. Stara instrumentacija je uklonjena. Nakon jedanaest godina prepustanja reaktora sudbini tesko da bi se iko usudio da pusti reaktor ponovo u pogon bez detaljnog istitivanja stanja suda reaktora i ostalih vitalnih delova reaktorskog sistema. Zadrzavanje reaktora u ovakvom stanju, bez donosenja konacne odluke o njegovom pustanju u rad ili konacnom zaustavljanju, pogubno je za ovu nuklearnu masinu. Stanje koje se odrzava vise od deset godina izvesno je da ce rezultirati samo u jednom: unistenju reaktora RAOriginal Title
Prilog A - Eksploatacija reaktora RA
Primary Subject
Source
Sotic, O. (Vinca Institute of Nuclear Sciences, Beograd (Serbia)); Vinca Institute of Nuclear Sciences, Beograd (Serbia); 203 p; Dec 1997; 3 p; RA--103/R1/P2/21/02; Also available from the Institute of nuclear sciences Vinca; This record replaces 37021917
Record Type
Miscellaneous
Report Number
Country of publication
CONTAINERS, CONTROL SYSTEMS, DECOMMISSIONING, DEMOLITION, ENRICHED URANIUM REACTORS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, INSTITUTIONAL FACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LICENSING, MAINTENANCE, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SHUTDOWN, TANK TYPE REACTORS, THERMAL REACTORS
Publication YearPublication Year
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] 1984 was a particularly sucessful year for the nuclear power plants in the Federal Republic of Germany. Four large units were newly added to the grid system, two of them boiling water reactor plants (Gundremmingen B and C with 1310 MW each) and two pressurized water reactor plants (Grohnde with 1365 MW and Philippsburg-2 with 1349 MW). The share of nuclear power contributed to electricity generation in the public grid system rose by 41% to a total of 27%. The number of commercial nuclear generating units increased to sixteen in 1984 their installed capacity went up to some 17.000 MW. As the backfitting phases, which had involved prolonged outages in several nuclear power plants, were all completed in 1983, the favorable mean availability of all plants expected for 1984 was in fact attained. The average availability of capacity of the commercial units was 83%. (orig.)
[de]
Im Jahr 1984 nahm der Stromverbrauch aus dem oeffentlichen Netz nach vorlaeufigen Angaben um 4,1% zu. Die Stromerzeugung aus Kernenergie erhoehte sich in der Bundesrepublik Deutschland von 65,9 TWh im Jahr 1983 um 40,6% auf 92,7 TWh im Jahr 1984 und erreichte damit einen Anteil von 27% an der gesamten oeffentlichen Stromerzeugung (23,2% der Gesamtstromerzeugung). Das fuer die Kernkraftwerke erfolgreich verlaufende Jahr 1984 ist weiterhin gekennzeichnet durch die Inbetriebnahme der Bloecke KRB B, KRB C, KWG und KKP-2. Die Abgaben an Radioaktivitaet lagen erneut weit unter den vorgeschriebenen Grenzwerten. Zu diesen Ergebnissen kommt der Jahresbericht 1984 des Ausschusses fuer Betriebserfahrungen (ABE-Ausschuss) in der VGB, aus dem im folgenden Auszuege veroeffentlicht werden. (orig.)Original Title
Betriebsergebnisse der deutschen Kernkraftwerke 1984. T. 1
Primary Subject
Source
Full text of annual report 1984 of the ABE-Committee published in At. Strom (Mar-Apr 1985) v. 31(2) p. 37ff.; CODEN: AWAKA.
Record Type
Journal Article
Journal
Atw. Atomwirtschaft, Atomtechnik; ISSN 0365-8414;
; v. 30(7); p. 383-399

Country of publication
BIBLIS REACTOR, BIBLIS-B REACTOR, BRUNSBUETTEL REACTOR, DIAGRAMS, FEDERAL REPUBLIC OF GERMANY, GRAFENRHEINFELD REACTOR, GROHNDE REACTOR, GUNDREMMINGEN-2 REACTOR, GUNDREMMINGEN-3 REACTOR, ISAR REACTOR, KRUEMMEL REACTOR, NECKAR REACTOR, NUCLEAR POWER PLANTS, OBRIGHEIM REACTOR, PHILIPPSBURG-1 REACTOR, PHILIPPSBURG-2 REACTOR, POWER REACTORS, REACTOR OPERATION, STADE REACTOR, UNTERWESER REACTOR, WUERGASSEN REACTOR
Publication YearPublication Year
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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