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[en] Full text of a summary description by representatives of the International Atomic Energy Agency (dated May 9, 1986)
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Journal Article
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Nuclear Europe; CODEN NUEUD; v. 6(6); p. 30
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[en] This article gives a concise summary of the Status Report of the Superheated Steam Reactor Safety Program (PHDR) Project, held at KfK on Dec. 5, 1985. The results discussed dealt with fire experiments, shock tests simulating airplane crashes, temperature shocks in the reactor pressure vessel, studies of crack detection in pressure vessels and blasting experiments associated with nuclear plant decommissioning
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Nuclear Europe; CODEN NUEUD; v. 6(1); p. 42
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[en] A robot developed by the company ACEC is described. Its main objective is to replace man during tasks being carried out in radioactive, dangerous or unhealthy environments
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Nuclear Europe; CODEN NUEUD; v. 6(6); p. 22
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[en] The R and D work for Superphenix was conducted by CEA and embraced the basic system, components, fuel design and safety studies
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Journal Article
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Nuclear Europe; CODEN NUEUD; v. 5(11); p. 19
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[en] The plant concept, layout and design, component fabrication and plant construction of Superphenix are described
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Nuclear Europe; CODEN NUEUD; v. 5(11); p. 20
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[en] The CORA facility, erected within four years in the containment of the decommissioned FR 2 reactor, is now in operation. It allows simulation of LOCA situations. 15 - 20 experiments are planned during the next two years
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Nuclear Europe; CODEN NUEUD; v. 6(4); p. 42
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[en] Tests of the auxiliary circuits of Superphenix's NSSS were carried out from 1981 to 1983. In 1984 two secondary loops were tested. Isothermal tests started early 1985
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Journal Article
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Nuclear Europe; CODEN NUEUD; v. 5(11); p. 21
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[en] A brief description of the Superphenix project organization is given, the main stages are recalled and some conclusions are drawn
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Nuclear Europe; CODEN NUEUD; v. 5(11); p. 18
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[en] Superphenix's plant organization based on a staff of 430 people is described. Also included are details of personnel training and the maintenance scheme
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Nuclear Europe; CODEN NUEUD; v. 5(11); p. 22
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[en] In France reprocessing of spent FBR fuel was first carried out at the AT1 unit in La Hague. A pilot facility at Marcoule reprocessed part of the Phenix fuel. The TOR project aimed at an increase of the Marcoule facility's capacity to 5 t/year. A future plant (MAR 600 project) will reprocess all spent fuel from French FBR's
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Nuclear Europe; CODEN NUEUD; v. 5(11); p. 36
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