consisting of four Brayton loops operated at a turbine inlet temperature of MOOK [4], and a mercury/steel heat pipe non-deployable radiator [5]. Work carried out at this stage included conceptual design studies, analysis of the reactor control system, and of normal and accidental transients [6]. • Mid 1986 to 1989 - Establishment of the technical and economic bases for the development of nuclear SPS. This present phase comprises: • continuation of the studies on the 200 kWe reference system for improving the preliminary design (mass optimization and sensitivity studies), investigating design alternatives and evaluating a gas cooled reactor with direct conversion. • comparative study of three candidate nuclear source technologies for driving 20 kWe turboelectric sps [7,8,11]. As parts of this study are: - conceptual design of the whole power systems (with the assistance of AEROSPATIALE for the system general layout, overall integration and components spatialization) - preliminary design of the critical components contracted to industry: turbogenerator (ALSTHOM/RATEAU, TURBOMECA, AUXILEC), control drums and safety rods actuators (SAGEM) - component and system modelling for system design point optimization and analysis of normal and accidental system behaviour - reliability studies - small experimental programme including in and out of pile screening tests of candidate structural materials (superalloys and refractory alloys), compatibility tests of MoRe/Li and UN/MoRe/Li systems, preliminary fabricability tests of parts of critical components, and first comparative tests of the behaviour of Na and NaK cooled LMFBR derivative reactor mockups during immersion in water - sensitivity studies of the specific mass to system specifications - evaluation of design alternatives - elaboration of a development and qualification programme, and evaluation of the required lead time and development cost, with the assistance of the industry (NOVATOME/FRAMATOME) • feasibility study of a 20 kWe thermoelectric nuclear SPS heated by a LMFBR derivative nuclear source [ 12]
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