REFLOD3B: A computer code simulating PWR system behavior during reflood

Conference · Mon Jan 01 04:00:00 EST 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6005428

Nithianandan, C K; Biller, J R

The REFLOD3B computer code was developed by the Babcock Wilcox (B W) Fuel Company to calculate the system behavior of a pressurized water reactor (PWR) during the refill and reflood phases of a large-break loss-of-coolant accident (LOCA). REFLOD3B solves one-dimensional mass, momentum, and energy conservation equations. The code has been extensively used to analyze B W-designed plants and was recently modified to analyze recirculating steam generator PWRs. Modification included a new carryout rate fraction (CRF) correlation, CRFCKN; the addition of FLECHT and ANC correlations to determine core heat transfer; and a model to simulate the mass flow rate into the core bypass region. The code was assessed against FLECHT-SEASET gravity reflood test 33338. The CRFCKN correlation and the results of the FLECHT-SEASET test simulation are summarized here.

• OSTI ID: 6005428
• Report Number(s): CONF-901101--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 62
• Country of Publication: United States
• Language: English

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