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[en] Signals from the Dutch Borssele nuclear power plant are transmitted via a special telephone line to the ECN research establishment at Petten, where on-line noise analysis is performed using a mini-computer
[en] Alpha activity in wastes must be measured accurately before their disposal. SGN, working jointly with the CEA, has developed a range of equipment designed to meet the different needs of the waste generators. The analytical techniques exploit the properties of different alpha emitters, with the knowledge that these alpha particles themselves are not detectable because of their short paths in materials. One method, passive measurement by gamma scanning, consists in detecting the gamma radiation emitted by certain isotopes. A second method, passive neutron measurement, is based on the detection of the neutrons emitted during the spontaneous fission of even-numbered isotopes. A third method, active measurement by neutron interrogation, induces the fission of uneven-numbered isotopes of the contaminant by means of an external neutron source, and detects the neutron or gamma radiation caused by this fission
[en] GE Nuclear Energy's Advanced Nuclear Technology Operation's Decommissioning Service Group is decommissioning Shippingport (PWR, 90 MWe), the world's first commercial nuclear power plant. This key project is the first entire decommissioning of a large, commercial-size nuclear power plant in the world, and is being completed safely and cost effectively using existing dismantling practices. The Shippingport Decommissioning Project has consisted of two distinct phases: a surveillance, maintenance and operation phase, and a decommissioning phase. The former, also known as the caretaker phase, was completed by the end of 1984. Following a detailed operational preparatory review, decommissioning began during September 1985. Non-fuel-bearing irradiated core components were removed from the fuel-handling canal and placed into the reactor pressure vessel. The water level was then lowered to allow the drainage of water from the reactor coolant system pipes and components. At the same time, the electrical system was shut down, asbestos was removed, external surfaces were decontaminated, and the systems were drained. During 1987, all reactor coolant system pipes and components were removed. Early in 1988, the reactor pressure vessel and neutron shield tank (RPV/NST) was shielded and prepared for one-piece removal. The removal of the fuel-handling canal and non-radioactive concrete and structures is now well advanced. At present there are no major technical issues remaining. The project is expected to be completed with less than 200 man-rem exposure which is one-fifth of the radiation exposure than the US Department of Energy has estimated for the decommissioning. 3 figs
[en] This is the list of proposals made during the August 25-29 post-accident meeting - proposals for consideration by the IAEA. It is printed here as presented on August 29 by the review meeting's chairman, Dr. R. Rometsch (Switzerland), in his summary at the final plenary session. He described it as 'a condensed list'