Published April 1989 | Version v1
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Benchmarking the RELAP5 L-Reactor model with Savannah River reactor test data

Description

A quality-assured RELAP5 input model of the L-Reactor at the Savannah River Plant (SRP) was developed to support the analysis of a loss-of-coolant accident (LOCA). The RELAP5/MOD2.5 computer code and the L-Reactor model were benchmarked against SRP data to demonstrate their applicability for thermal-hydraulic analysis of SRP reactors. The code and model were benchmarked against data from several different reactor system tests including the 1985 AC Process Flow Tests, the 1983 Cavitation Tests, the 1987 AC Pump Trip Tests, and the 1970 Starved Pump Tests. Results of the benchmark calculations were favorable, yielding confidence in the capability of RELAP5 and the L-Reactor model to determine system response during normal and transient operation, including a LOCA. 17 refs., 30 figs., 11 tabs

Availability note (English)

MF available from INIS under the Report Number; NTIS, PC A05/MF A01 as DE90009789; OSTI; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
80 p.
Report number
EGG-EAST--8336

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570