Open AccessThermal and Nuclear Design Review of the NRX-A5 Reactor
Author(s) -
David L. Black,
W. Minners,
J.S. Stefanko,
R.P. Vijuk
Publication year - 1964
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/1117519
Subject(s) - nuclear engineering , beryllium , reflector (photography) , nuclear reactor , parametric design , nuclear power , graphite , nuclear reactor core , thermal , parametric statistics , control rod , materials science , mechanical engineering , engineering , chemistry , nuclear physics , composite material , physics , light source , statistics , mathematics , optics , meteorology , organic chemistry
A thermal and nuclear NRX-A5 Design Review was held at WANL on April 10, 1964. Analyses and planning performed to date on the NRX-A5 and subsequent reactors were presented. Systems analyses were performed on various "cooled periphery".and "hot periphery" seal configurations. A number of inner reflector designs were examined, as well as means for cooling the lateral support springs. Core component redesign incl,uded methods for controlling inter-element pressure distribution by undercutting or chamfering of fuel elements. Changes in tie rod diameters, use of as-extruded fuel elements, and performance analysis of the various systems were also described. Nuclear analysis was confined to parametric studies on excess reactivity and control drum span for inner reflector material combinations of graphite, aluminum, and/or beryllium. Changes required to more precisely define the NRX-A5 were discussed together with the effects associated with the twice power reactor capability envisioned for subsequent reactors
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