Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code

2019 ◽  
Vol 5 (2) ◽  
Author(s):  
Rosario Delgado-Tardáguila ◽  
Marisol Corisco ◽  
Antonio Espejo ◽  
Daniel Navarro ◽  
Javier Riverola

One of the limiting conditions during operation of a pressurized water reactor (PWR) is cladding integrity in class I (normal operations) or class II (most frequent). Cladding integrity is limited typically by the departure from the nucleate boiling (DNB), which criterion ensures an appropriate core cooling. Adequate heat transfer between the fuel cladding and reactor coolant is achieved by preventing DNB that is avoided if the local heat flux is lower than the critical heat flux (CHF). The DNB is estimated thanks to thermal-hydraulic (TH) design codes, as the VIPRE-W code that predicts the fluid behavior based on the geometry of the problem, the fuel rods and the fluid properties among others. One of the parameters that influences the DNB estimation is the thermal diffusion coefficient (TDC), which depends on the fuel design and is affected by the grid spacing. As a matter of fact, the TDC enters into the DNB calculation for thermal mixing between subchannels and in some special cases like the most primitive fuel designs, as a factor within the DNB correlation. Nevertheless, although the TDC is a variable, the TH design codes used for the DNB prediction consider the TDC as a constant. This investigation is founded on a new numerical program developed to explore the effect of the TDC on the DNB. In addition to this, variables as the effect of the turbulent momentum factor (FTM) and the correlation effect has been explored too. The most direct outcome of this research is the substantial extension of the existing studies of VIPRE-W TH code. The results show that TDC has an effect on the DNB dominated by the radial power distribution. The departure from nucleate boiling ratio (DNBR) increases up to 1.2% when TDC is a variable under normal operation radial shapes. For the design radial distribution, this effect is vanished but observable for values under 0.02 with an exponential increase of the DNBR with respect to the TDC. From this moment on, the energy exchanged between subchannels is negligible due to the flatness shape of the radial enthalpy distribution.

Author(s):  
Roman Mukin ◽  
Marcus Seidl ◽  
Ivor Clifford ◽  
Hakim Ferroukhi

In this work, a so-called mini-core consisting of a 3 × 3 array of 17 × 17 pressurized water reactor (PWR) fuel assemblies (FA) is considered with the aim of identifying the most conservative window size for hot channel analysis of bowed fuel assemblies. Overall, five different mini-core configurations are analyzed: one is the reference case, i.e. without FA displacement and four different cases with diagonal and parallel FA displacements. Rod power maps for these mini-cores were exported from neutronic calculations with CASMO-SIMULATE codes. Subchannel modelling with COBRA-TF code of all five mini-cores allows one to identify the rod position with a minimum departure from the nucleate boiling ratio (DNBR) and to construct input decks with different rod window sizes around the previously identified rod position. Overall, eight different window sizes are considered: 3 × 3, 5 × 5, 7 × 7, 9 × 9, 11 × 11, 13 × 13, 15 × 15 and 17 × 17. Results of subchannel analysis for a mini-core and different subchannel window configurations are compared with the help of DNBR parameter, which is the ratio between the critical heat flux (CHF) and the actual local heat flux on a rod. An assessment of three different CHF models is applied in this work: Groeneveld CHF look-up table (LUT), W3 CHF correlation, and Doroschuk CHF LUT. The general conclusion of this work is that for deformed core configurations, an appropriate rod window size needs to be determined to adequately capture the local flow redistribution. For large displacements (the largest displacement considered in this work is 10 mm), the DNBR ratio can drop to one. DNBRs obtained with the W3 CHF correlation give the most conservative results.


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