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AbstractAbstract
[en] Information is presented on fuels for the IBR-2 reactor, the TREAT converter fuel element studies, the ACPR reactor fuel modifications, and the fuel elements to provide high fluence pulses in the VIPER reactor
Primary Subject
Record Type
Journal Article
Journal
Nuclear Technology; v. 28(1); p. 87-91
Country of publication
AIR COOLED REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, MIXED SPECTRUM REACTORS, ORGANIC MODERATED REACTORS, PULSED REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
ANS international conference; Washington, DC (USA); 17 - 21 Nov 1980; CONF-801107--; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; ISSN 0003-018X; 
; v. 35 p. 370-371
; v. 35 p. 370-371
Country of publication
ACCIDENTS, BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LIQUID METAL COOLED REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Aerojet Nuclear Co., Idaho Falls, Idaho (USA); p. 247-265; Dec 1973
Record Type
Report
Literature Type
Progress Report
Report Number
Country of publication
BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LIQUID METAL COOLED REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kaplan, S.; Stephen, J.D.; Vijuk, R.M.; Jackson, R.J.
International conference on fast breeder reactor fuel performance1979
International conference on fast breeder reactor fuel performance1979
AbstractAbstract
[en] Improvements in assembly design can be made to reduce the deleterious effects of bundle-duct and duct-duct interactions on assembly lifetime, and to improve performance in general. Several advanced wire and grid spacer concepts have been tested out-of-reactor and in EBR-II. Testing will continue in FTR. All test results thus far are positive. 8 figures
Primary Subject
Source
Norman, E.C.; Adamson, M.G.; Boltax, A.; Cox, C.M.; Little, W.W. Jr; Weber, E.T.; Lambert, J.D.B.; Roberts, J.T.A. (eds.); p. 758-776; 1979; p. 758-776; American Nuclear Society; La Grange Park, IL; International conference on fast breeder reactor performance; Monterey, CA, USA; 5 - 8 Mar 1979
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Two US DOE projects in the Pacific Northwest offer unique on-the-scene training opportunities at sodium-cooled fast-reactor plants: the Fast Flux Test Facility (FFTF) near Richland, Washington, which has operated successfully in a wide range of irradiation test programs since 1980; and the Experimental Breeder Reactor II (EBR-II) near Idaho Falls, Idaho, which has been in operation for approximately 20 years. Training programs have been especially designed to take advantage of this plant experience. Available courses are described
Primary Subject
Secondary Subject
Source
1984; 25 p; Available from NTIS, PC A02; 3 as DE84008500
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Carelli, M.D.; Brandt, H.W.; Bach, C.W.; Kulikowski, H.D.
Westinghouse Electric Corp., Pittsburgh, Pa. (USA). Advanced Reactors Div1973
Westinghouse Electric Corp., Pittsburgh, Pa. (USA). Advanced Reactors Div1973
AbstractAbstract
No abstract available
Primary Subject
Source
1973; 5 p; Annual meeting of the American Nuclear Society; Philadelphia, Pennsylvania, USA; 23 Jun 1974
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
p. 211-228; 1973; American Nuclear Society; Hinsdale, IL; International conference on irradiation experimentation in fast reactors; Jackson Hole, Wyoming, USA; 10 Sep 1973
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Furet, J.; Landauer, C.
CEA Saclay, 91 - Gif-sur-Yvette (France)1968
CEA Saclay, 91 - Gif-sur-Yvette (France)1968
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
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Aden, V.G.; Blintsova, O.A.; Kartashov, E.F.; Lukichev, V.A.; Malinkin, V.M.; Sokolov, S.A.; Firsov, A.S.
Reduced Enrichment for Research and Test Reactors. Proceedings of the XVIII international meeting2004
Reduced Enrichment for Research and Test Reactors. Proceedings of the XVIII international meeting2004
AbstractAbstract
[en] A design of the test fuel assembly of MR type for in-pile tests to determine design safe operation margins is presented in the paper. The tests will be performed in the pulsed uranium-graphite reactor of IGR type in Semipalatinsk (Kazakh Republic) under emergency models of a loss-of-coolant accident and a reactivity initiated accident. (author)
Primary Subject
Source
French Atomic Energy Commission (CEA), Paris (France); Compagnie pour l'Etude et la Realisation de Combustibles Atomiques (CERCA), Paris (France); COGEMA (France); FRAMATOME (France); TECHNICATOME(France); TRANSNUCLEAIRE (France); International Atomic Energy Agency, Vienna (Austria); 557 p; 2004; [9 p.]; 18. international meeting on Reduced Enrichment for Research and Test Reactors; Paris (France); 17-21 Sep 1995; 9 refs, 5 figs
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, GRAPHITE MODERATED REACTORS, IRRADIATION REACTORS, MATERIALS TESTING REACTORS, PULSED REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR EXPERIMENTAL FACILITIES, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Smith, D.E.
Hanford Engineering Development Lab., Richland, WA (USA)1983
Hanford Engineering Development Lab., Richland, WA (USA)1983
AbstractAbstract
[en] The W-2 SLSF (Sodium Loop Safety Facility) experiment was an instrumented in-reactor test performed to characterize the failure response of full-length, preconditioned LMFBR prototypic fuel pins to slow transient overpower (TOP) conditions. Although the test results were expected to confirm analytical predictions of upper level failure and fuel expulsion, an axial midplane failure was experienced. Extensive post-test analyses were conducted to understand all of the unexpected behavior in the experiment. (1) The initial post-test effort focused on the temperature oscillations recorded by the 54 thermocouples used in the experiment. In order to synthesize the extensive data records and identify patterns of behavior in the data records, a computer-generated film was used to present the temperature data recorded during the experiment
Original Title
Sodium Loop Safety Facility
Primary Subject
Secondary Subject
Source
23 Jun 1983; 7 p; American Nuclear Society winter meeting; San Francisco, CA (USA); 30 Oct - 4 Nov 1983; CONF-831047--131; Available from NTIS, PC A02/MF A01; 1 as DE84006346
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, LIQUID METAL COOLED REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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