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Final design analyses of CRBRP fuel rod

Description: The key results are presented of the CRBRP fuel rod analyses performed in support of the CRBRP fuel assembly final design review in December, 1977. For the CRBRP fuel rod design environment, it is shown that the life limiting criteria on ductility limited strain (DLS) and cumulative damage function (CDF) are satisfied. The conservatism in these analyses is demonstrated by comparison to the upset enthalpy based failure potential criteria derived from cladding breach experience for TREAT simulated unterminated rapid reactivity insertion transients.
Date: January 1, 1980
Creator: Bishop, B.A. & Vijuk, R.M.
Partner: UNT Libraries Government Documents Department

Thermal and nuclear design review of the NRX-A5 Reactor

Description: 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.
Date: May 15, 1964
Creator: Black, D L; Minners, W; Stefanko, J S & Vijuk, R M
Partner: UNT Libraries Government Documents Department