TERMINAL REPORT ON THE BOILING SLURRY REACTOR EXPERIMENT (SLURREX)
Author(s) -
G.A. Freund,
J.D. Lokay,
G.C. Milak,
Jmk Macalpine
Publication year - 1960
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4077463
Subject(s) - nuclear engineering , scram , boiling water reactor , mockup , reactor pressure vessel , boiling , sizing , slurry , nuclear reactor core , pressure vessel , environmental science , materials science , engineering , mechanical engineering , chemistry , environmental engineering , organic chemistry
A plant layout of SLURREX was prepared on the basis of preliminary design and sizing of major components. The reactor vessel was designed in detail, assuming the use of commercially available fittings. A hydraulic analysis of this vessel indicated that the design power of 5 Mw could be extracted with 50% exit steam voids. A half-scale mockup of the reactor vessel was designed and constructed to verity experimentally the results of the theoretical hydraulic analysis. Physics calculations have allowed the selection of core parameters and have indicated that about 545 g of thoria (containing 10% of 93%-enriched urania) per kg of water is required for design power at 10.2-atm saturation pressure. An initial hazards analysis has shown that SLUBREX can be operated safely at the proposed site near EBR-II at the National Reactor Testing Station. Preliminary determinations of process variables for measurement, alarm, and scram were made, and some selection of instrument types was carried out. (auth
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