Title of article
RETRAN-02 MOD5 and RETRAN-03 code benchmarks for Beaver Valley plant transients and FSAR analyses
Author/Authors
Feltus، نويسنده , , Madeline Anne; Beaumont، نويسنده , , Eric T، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 1995
Pages
8
From page
275
To page
282
Abstract
Abstract-A RETRAN-02 MODS model and a RETRAN-03 model for the Beaver Valley Unit I plant
were developed from an existing, but untested RETRAN deck. This study uses FSAR transient analyses,
actual plant event data, and similar plant analyses performed with RETRAN and TRAC-BFl MODI
to benchmark the RETRAN-2 MODS and RETRAN-3 plant model. Eight transients were chosen to
qualify the RETRAN models: (I) a standard reactor trip, (2) a loss of one reactor coolant pump, (3) a
loss of all reactor .coolant pumps, (4) an inadvertent opening of a pressurizer relief valve, (5) a loss of
normal feedwater with auxiliary feedwater available, (6) a turbine trip, (7) a main steam line isolation
valve closure, and (8) a main steam line break. These design basis transients were each chosen to isolate
specific phenomena or plant design aspects of the RETRAN models that are exhibited in depressurization
events, over-pressurization and over-temperature transients, and over-cooling accidents.
Both the RETRAN-02 MODS and RETRAN-03 Beaver Valley models were successfully benchmarked.
The RETRAN results compared well with the FSAR LOFTRAN analyses, an actual Beaver Valley single
pump trip event, and Ringhals 2 and 4 analyses. The RETRAN-03 model performed well and provided
a better best-estimate of plant phenomena than the RETRAN-02 MODS results; moreover, both the
RETRAN models predicted more realistic transient behavior than the FSAR LOFTRAN results.
Journal title
Annals of Nuclear Energy
Serial Year
1995
Journal title
Annals of Nuclear Energy
Record number
404901
Link To Document