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[en] The current state and temporal course of setting to work the Muelheim-Kaerlich nuclear power station is described. After a short description of the whole plant, there is a representation of the main points of tests and results from commissioning with steam raising unit water levels, turbine run-up on heat test and the emergency feedwater system. (DG)

[en] Fort St. Vrain Unit 1, a 330-MW(e) HTGR being built by General Atomic for the Public Service Co. of Colorado, is located about 40 miles north of Denver. Construction began in 1968 and fuel was loaded under the first phase of the two-phase license in January 1974. The reactor has been critical a number of times to perform physics tests, but has been restrained until recently from producing any sensible heat by the restrictions of the second phase of the license. All prerequisites to the second and last phase of the license were satisfied on November 14 and the 40-year, full-power license went into effect. Since then, hot physics tests have been performed and feedwater has been introduced into the steam generators. All prerequisite testing is complete and feedwater chemistry is within specification for steam generator boilout. The plant is presently shut down and in a standby condition while the backup pelton wheels on the four primary helium circulators are being changed to an improved material. Upon completion of this change, now scheduled for the end of January, the rise-to-power program will begin. (auth)3167 95 The Oconee Nuclear Station, a three unit station, is Duke Power Company's first nuclear generating facility. Selected control, instrumentation and electrical system operating experience is provided. (auth)99

[en] As soon as the operation permit for the KNK II plant had been issued in early October 1977, nuclear commissioning of the experimental nuclear power station was initiated. First, the blanket zone and the seven PuO₂/UO₂ elements of the test zone were loaded. On October 10, 1977 the reactor was first operated in the supercritical regime with a critical minimum assembly which was in good agreement with predictions. On October 16, 1977 the target core consisted of 29 fuel elements was made supercritical. The two shutdown systems were calibrated after the operating core had been built up. Various measurings techniques were employed for reactivity assessments so as to satisfy the different measuring problems at hand and increase the reliability of individual calibrations. (orig.)

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[en] The procedure is briefly characterized of jobs in nuclear power plant start-up and the differences are pointed out from those used in conventional power generation. Pressure tests are described oriented to tightness, tests of the secondary circuit and of the individual nodes and facilities. The possibility is shown of increased efficiency of such jobs on an example of the hydraulic tests of the second unit of the Dukovany nuclear power plant where the second and the third stages were combined in the so-colled integrated hydraulic test. (Z.M.). 5 figs

[en] Commissioning of the THTR took place in three main stages. The zero energy experiments included the criticality of the core without rods, the critical rod position of the fully loaded core under air and determining the excess reactivity and effectiveness of the rods. During the heat test, the isothermal temperature coefficient of the reactivity was determined. The load tests included the critical rod position at different load stages and the measurement of the temperature coefficient and the xenon reactivity. (DG)

[en] The Fast Flux Test Facility (FFTF), located on the Department of Energy (DOE) Hanford Reservation near Richland, Washington, is a 3 Loop 400 MWt sodium cooled fast reactor with a primary mission to test fuels and materials for development of the Liquid Metal Fast Breeder Reactor (LMFBR). Highlights of the ATP involving the system inerting, liquid metal and inerted cell testing and initial ascent to full power are discussed. 3 refs

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No abstract available