Abstract
A double-flat-core type high conversion light water reactor (HCLWR) has been developed at JAERI to improve fuel utilization. Experimental and analytical studies on the departure from nucleate boiling ratio (DNBR) under operational and accident conditions for the HCLWR have been performed. It was found by comparing several critical heat flux (CHF) correlations with the CHF data obtained at JAERI and Bettis Atomic Power Laboratory that the KfK correlation has the most promising features for the application to the triangular tight lattice rod array. The minimum allowable DNBR (MDNBR) for the HCLWR was determined to be 1.28 by comparing the Bettis CHF data with the KfK correlation. The best-estimate code J-TRAC was used for system transient calculations under the primary coolant pump trip and locked rotor accident conditions. The subchannel code COBRA-IV-I was then used to obtain local flow conditions and fuel rod surface heat flux. The analytical results indicated that an enough safety margin was assured und...
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