[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

No abstract available

[en] The review deals with fuel and material irradiation testing techniques using reactors. Major studies made in overseas countries are outlined first, and then current efforts and future plans in major research and experimental reactor facilities in Japan are described focusing on techniques for improving the quality of fuel and material. Irradiation tests can be grouped into three categories in terms of the technique used: (1) use of a practical reactor or an irradiation rig to examine the properties of fuel or material under irradiation, (2) use of a rig equipped with on-line instrumentation for continuous monitoring of changes in the behaviors of fuel or material under irradiation, and (3) use of a loop to simulate transient states of a reactor. Studies in overseas nations on the properties of fuel and material for light water reactor, fast breeder reactor, nuclear fusion reactor and high temperature gas-cooled reactor are outlined separately. Then, description is made of the role and results of research, major equipment used, and future plans in various facilities in Japan, including Kyoto University Reactor, JRR-3, JMTR, and Joyo. (N.K.)

No abstract available

[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

No abstract available

[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

No abstract available

[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)

[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)