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in creator/contributor: "Vijuk, R.M."

open access

Final Design Analyses of CRBRP Fuel Rod

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 simulate… more

Date: January 1, 1980

Creator: Bishop, B. A. & Vijuk, R. M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermal and nuclear design review of the NRX-A5 Reactor

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 c… more

Date: May 15, 1964

Creator: Black, D L; Minners, W; Stefanko, J S & Vijuk, R M

Item Type: Report