Published March 2015 | Version v1
Journal article

Simulations of flashing experiments in TOPFLOW facility with TRACE code

  • 1. Jozef Stefan Institute, Reactor Engineering Division, Jamova cesta 39, 1000 Ljubljana (Slovenia)
  • 2. Institute of Fluid Dynamics, Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstraße 400, 01328 Dresden (Germany)

Description

Highlights: • Two decompression experiments performed at TOPFLOW are simulated with a TRACE code. • The depressurization triggers flashing of the slightly undersaturated liquid water. • Pressure, temperature and void fractions are compared with measurements. • Prediction of the choked flow is the most critical parameter of simulations. • Good agreement with measurements at high initial pressure (i.e. 65 and 40 bars). - Abstract: The decompression experiments performed at TOPFLOW facility in 2010 have been reproduced using the latest best-estimate thermohydraulic system code TRACE (V 5.0 Patch 3). The main component of TOPFLOW facility was about 8 m long vertical tube with an inner diameter of 195.3 mm. The evaporation of liquid water to steam caused by depressurization was simulated using two different procedures: from stagnant water and during circulating of water in tubes. The liquid water was almost saturated at initial pressure values of 1.0, 2.0, 4.0 and 6.5 MPa. Our approach applies one-dimensional code to simulate all the important parts of the facility not just the vertical test section, where the measurements were taken. The obtained simulated pressure, temperature and void fractions are compared with measured values. The simulations of the first procedure (stagnant water at beginning) are in a good agreement with measurements, especially for the cases with longer transients and higher initial pressure, however, choked flow model through the blow-off valve had to be adjusted. There is a short transient (about 2 s) after the fast opening valve opens, which was not reproduced correctly with TRACE. The simulations of the second procedure (circulating water in a loop) correctly predict pressure and temperature decrease, but underpredict void fraction. No modification of the default TRACE choked flow model was needed for procedure B

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2014.09.043

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2014.09.043;
PII
S0029-5493(14)00556-1;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
283
Journal Page Range
p. 60-70
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
22. international conference on nuclear energy for a new Europe
Acronym
NENE 2013
Dates
9-12 Sep 2013
Place
Bled (Slovenia)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
47016298
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; DEPRESSURIZATION; FLASHING; FLOW MODELS; LIQUIDS; ONE-DIMENSIONAL CALCULATIONS; PRESSURE RANGE MEGA PA 01-10; STEAM; T CODES; TRANSIENTS; TUBES; VALVES; VOID FRACTION; WATER
Descriptors DEC
COMPUTER CODES; CONTROL EQUIPMENT; EQUIPMENT; EVAPORATION; FLOW REGULATORS; FLUIDS; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PRESSURE RANGE; PRESSURE RANGE MEGA PA; SIMULATION

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.