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Incorporation of lithium lead eutectic as a working fluid in RELAP5 and preliminary safety assessment of LLCS
Affiliation:1. Nuclear Engineering and Technology Programme, Indian Institute of Technology, Kanpur 208016, India;2. Institute for Plasma Research, Gandhinagar 382428, India;3. Innovative Systems Software, Idaho Falls, ID 83406, USA;1. SSC RF TRINITI Troitsk, Moscow 142 190, Russia;2. JSC “Red Star”, Elektrolitnyj pr. 1A, Moscow 113 230, Russia;3. NRNU MEPhI, Kashirskoye sh. 31, Moscow 115409, Russia;1. Department of Mechanical Engineering, University of Thessaly, Volos 38334, Greece;2. Associação EURATOM/IST, Centro de Fusão Nuclear, Av. Rovisco Pais, 1049-001 Lisboa, Portugal;1. Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, D-85748 Garching, Germany;2. Wigner Research Centre for Physics, Hungarian Academy of Sciences, Konkoly-Thege Miklós 29–33, H-1121 Budapest, Hungary;1. Center for Plasma Material Interactions, University of Illinois, Urbana, Champaign, IL 61801, USA;2. Princeton Plasma Physics Laboratory, Princeton, NJ 08543, USA
Abstract:The current work involves thermal hydraulic calculation of Lithium Lead Cooling System (LLCS) for the Indian test blanket module (TBM) for testing in International Thermonuclear Experimental reactor (ITER). It uses the RELAP portion of RELAP/SCDAPSIM/MOD4.0. Lithium-lead eutectic (LLE) has been used as multiplier, breeder and coolant in TBM. Thermodynamic and transport properties of the LLE have been incorporated into the code. The main focus of this study is to check the heat transfer capability of LLE as coolant for TBM system for steady state and the considered anticipated operational occurrences (AOO's), namely, loss of heat source, loss of primary flow and loss of secondary flow. The six heat transfer correlation (reported for liquid metals in the literature) has been tested for steady state analysis of LLCS loop and results are roughly same for all of them. A good agreement has been observed between the operating conditions of LLCS with those of RELAP5 calculations. Results from transient calculations show that a maximum temperature of 875 K is attained during a 300 s loss of primary flow (LLE).
Keywords:LLCS  RELAP5  Anticipated operational occurrences  TBM  ITER
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