Published 1990 | Version v1
Journal article

REFLOD3B: A computer code simulating PWR system behavior during reflood

Description

The REFLOD3B computer code was developed by the Babcock ampersand Wilcox (B ampersand 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 ampersand 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

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
62
Series
Trans. Am. Nucl. Soc.
Journal Page Range
721-722
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society (ANS) winter meeting.
Dates
11-15 Nov 1990.
Place
Washington, DC (USA).

Optional Information

Secondary number(s)
CONF-901101--.