Effects of rod worth and drop speed on the BWR off-center rod drop accident

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6496592

Cokinos, D M; Carew, J F

In recent years, several multidimensional coupled neutronic/thermal-hydraulic calculations of the boiling water reactor (BWR) control rod drop accident (RDA) have been performed. Typically, two-dimensional (r, z) RDA calculations require that the dropped rod be a center rod, as a result of geometric limitations; while in three-dimensional calculations, the dropped rod is generally taken to be the center rod in order to allow a quarter-core representation and limit computer running times. For typical BWR core loadings, however, the center rod is not necessarily the highest worth rod. The purpose of the present study was to determine the effect of increasing the control rod worth and the rod drop speed on the off-center RDA. An increase in either of these parameters results in an increase in peak core power and fuel enthalpy, and the objective of this study is to determine the margin to the fuel damage threshold.

• Research Organization: Brookhaven National Lab., Upton, NY
• OSTI ID: 6496592
• Report Number(s): CONF-860610-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
• Country of Publication: United States
• Language: English

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