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- W19195638 abstract "than 100 mg of Cf/sup 252/ will be produced by such an irradiation. In addition to the central irradiation facility for heavy-element production, the HIKIR will have eight hydraulic rabbit tubes located in the beryllium refiector and four beam holes for basic research. Preliminary design of the reactor was based on the results of a parametric study of the dimensions of the island and fuel region, heat-removal rates, and fuel loading on the achievable thermal-neutron fluxes in the island and reflector. A research and development program ding critical experiments, heat transfer, corrosion, a clufuel element studies has been in progress to verify the important parameters used in the design. The present design results in an average power density of 2.2 Mw/l in the active core and requires a maximum heat-transfer rate from fuel-plate surfaces of 1.5 x 10/ sup 6/ Btu/ft/sup 2//hr. This heattransfer rate is achieved by flowing H/sub 2/ O, at an inlet temperature of 120 F, and a pressure of 600 to 900 psig, through the 0.05-in. coolant channels at a velocity of 40 fps. A preliminary analysis of the hazards brought on by a reactor core meltdown shows that a controlled-leakage, filter-scrubber, stack release system of the ORR type will limit the consequences of such an accident to an acceptable degree. Construction is scheduled to start in early 1961 with operation at power scheduled for Jan. 1964. The estimated cost of the facility including engineering is" @default.
- W19195638 created "2016-06-24" @default.
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- W19195638 creator A5078180795 @default.
- W19195638 date "1968-01-01" @default.
- W19195638 modified "2023-09-26" @default.
- W19195638 title "THE HIGH-FLUX ISOTOPE REACTOR: A FUNCTIONAL DESCRIPTION. VOLUME 1B. ILLUSTRATIONS." @default.
- W19195638 doi "https://doi.org/10.2172/4516686" @default.
- W19195638 hasPublicationYear "1968" @default.
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