Fusion Programme - ENEA - Fusione

Fission TechnologyThe Very High Temperature Reactor (VHTR) is one of the nuclear reactor designsVery High considered for the research activity of the Generation-IV International Forum. This reactorTemperature is helium-cooled and graphite-moderated, with its design optimised for the industrialReactor utilisation of process heat (e.g., hydrogen production) besides the generation of electricity.Under FP6, the “Reactor for Process Heat, Hydrogen and Electricity Generation(RAPHAEL) Integrated Project” aims at developing technologies for gas systems with temperatures rangingfrom 850 to 1000°C, which are essential for the development of a European design.As one of the main partners in the RAPHAEL consortium under FP6, ENEA continued work on thedevelopment and qualification of high-temperature components, the validation of computational tools forthe core physics and the transient analysis for the VHTR.The HEATRIC tests at HEFUS3 ENEA Brasimone have to check the influence of helium on the mockupperformance (comparison with previous data on air and the manufacturer’s predictions). The original testgrid proposed by AREVA NP SAS, France, consists of hydraulic and thermal tests to determine friction andthe heat transfer law as a function of the Re number. After checking the feasibility of the tests against thecompressor performance, the number of tests planned was strongly reduced (table 8.III). However, ENEAis quite confident that it will be possible to provide additional tests at a higher flow rate because of a tooconservative computation of the pressure drops in the HEATRIC mockup and also in consideration of thefact that the compressor will be operated at its maximum speed (18000 rpm) and at higher pressure(24 bar).Concerning the benchmarking exercise for thermohydraulic transient-code validation, the experimentaldata have been released to the benchmark participants (ENEA, ANSALDO, CEA, IRSN, TRACTEBEL,AREVA with four codes RELAP5, CATHARE, MELCOR and MANTA). Preliminary calculations withTable 8.III - HEATRIC original test matrixHelium massflow(kg/s)HEATRICinlet temp.(°C)HEATRICout temp.(kPa)HEATRICpressuredrop (kPa)HEFUS3pressure drop(kPa)Totalpressuredrop (kPa)Compressorhead (*) (kPa)Feasibility0.025 510-121 105-494 130 0.7 131 195 yes0.050 510-127 105-488 257 2.6 259.6 175 no0.075 510-133 105-482 381 5.7 386.7 155 no0.1 510-137 105-479 505 9.9 514.9 145 no0.050 200-111 105-194 129 2.1 131.1 175 yes0.075 200-112 105-193 193 4.7 197.7 155 no0.100 200-113 105-192 397 8.2 405.2 145 no0.125 200-112 105-193 611 12.8 623.8 120 no0.025 Room T Room T 33 0.5 33.5 195 yes2007 Progress Report0.05 Room T Room T 65 1.8 66.8 175 yes0.075 Room T Room T 98 3.9 101.9 155 yes0.1 Room T Room T 250 6.8 256.8 145 no0.125 Room T Room T 370 10.6 380.6 120 no0.150 Room T Room T 509 15.2 524.2 95 no(*) 16000 rpm, 22 bar120