REFLOD3B: A computer code simulating PWR system behavior during reflood
Creators
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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22060720
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BW STANDARD REACTOR; COMPUTER CODES; COMPUTERIZED SIMULATION; ECCS; FLOW RATE; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MODIFICATIONS; ONE-DIMENSIONAL CALCULATIONS; PIPES; PWR TYPE REACTORS; R CODES; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RUPTURES; SIMULATION; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.