Thermal and Nuclear Design Review of the NRX-A5 Reactor

Technical Report · Fri May 15 04:00:00 EDT 1964

DOI:https://doi.org/10.2172/1117519· OSTI ID:1117519

Black, D. L. ^[1]; Minners, W. ^[1]; Stefanko, J. S. ^[1]; Vijuk, R. M. ^[1]

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1. Westinghouse Electric Corp., Pittsburgh, PA (United States). Astronuclear Lab.

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 included 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.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (United States). Astronuclear Lab.
• Sponsoring Organization: US Energy Research and Development Administration (ERDA); US Atomic Energy Commission (AEC)
• OSTI ID: 1117519
• Report Number(s): WANL-TME--758
• Country of Publication: United States
• Language: English

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