Published February 1987 | Version v1
Report Metadata-only

Validation of TRAC-PD2 against experiment LP-02-6 of the OECD-LOFT series

Creators

  • 1. Madrid Polytechnical Univ., Spain

Description

Experiment LP-02-6 of the LOFT-OECD series has been analyzed with TRAC-PD2. Pretest, steady state and post-test calculations have been performed. Pump behavior was improved by modifying the inertia equation and the two-phase torque and head multipliers. Some improvement were also introduced regarding to pressure losses. Accumulator characterization and chocked flow were also studied. Some errors in the code were also corrected. Rod temperature profile and time to early rewet were improved by modifying correlations in the code, mainly minimum film boiling temperature. After testing several correlations, it was determined that Sakurai's gives acceptable results for pressures above 5,5 bars. For pressures below 5 bars the homogeneous nucleation correlation is superior and for intermediate values an interpolation between the two. An improvement in the time to rewet is also obtained, but it is not yet satisfactory. The research effort is now concentrated in improving this aspect

Additional details

Publishing Information

Imprint Title
Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting: Volume 5, Nuclear plant analyzer and code development, International Code Assessment Program, Industry safety research
Journal Page Range
p. 179-196.
Report number
NUREG/CP--0082-Vol.5

Conference

Title
14. water reactor safety information meeting.
Dates
27-31 Oct 1986.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19002220
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; REACTOR ACCIDENTS; REACTOR KINETICS; REACTOR SAFETY; STEADY-STATE CONDITIONS; T CODES; TRANSIENTS
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; KINETICS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS