Comparison of predicted and measured fission product behavior in the Fort St. Vrain HTGR during the first three cycles of operation
Description: Fission product release from the reactor core has been predicted by the reference design methods and compared with reactor surveillance measurements and with the results of postirradiation examination (PIE) of spent FSV fuel elements. Overall, the predictive methods have been shown to be conservative: the predicted fission gas release at the end of Cycle 3 is about five times higher than observed. The dominant source of fission gas release is as-manufactured, heavy-metal contamination; in-service failure of the coated fuel particles appears to be negligible which is consistent with the PIE of spent fuel elements removed during the first two refuelings. The predicted releases of fission metals are insignificant compared to the release and subsequent decay of their gaseous precursors which is consistent with plateout probe measurements.
Date: October 1, 1985
Creator: Hanson, D.L.; Jovanovic, V. & Burnette, R.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department