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RRFM 2009 Transactions - European Nuclear Society

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q<br />

q<br />

P<br />

SK<br />

nom i<br />

max = ⋅Ri<br />

⋅fi<br />

⋅Kth<br />

(1)<br />

P<br />

S<br />

nom i<br />

maxH2O<br />

= K ⋅ Kth<br />

⋅qmax<br />

= ⋅ Ri<br />

⋅fi<br />

(2)<br />

Where: P i [W] is the power generated in the fuel cell ‘i’; S [cm 2 ] is the total heated surface of<br />

the fuel element; K=1.055 is coefficient taking into account the fraction of the total power that<br />

is generated in the coolant channels; K th =1 to 0.945 is correction diffusion coefficient taking<br />

into account the non-uniform heat distribution over the plate thickness; R i =1.52 to 1.38 is<br />

axial peaking factor; f i =1.48 to 1.3 is azimuth peaking factor.<br />

2.2 Determination of fabrication tolerances and thermal-hydraulic<br />

uncertainties<br />

The errors affecting the maximum value of the heat flux include: (i) the errors of the neutronic<br />

measurements in determination of the fuel power per channel and the errors in axial and<br />

azimuth power peaking factors; (ii) the manufacturing tolerances in the fuel density and in the<br />

quantity of burnable absorber in the fuel elements. The following uncertainties have been<br />

determined: error in determination of the specific power of a fresh fuel element: ε 1 = 18.7% ;<br />

error in determination of the axial peaking factor, ε = 7 2<br />

% ; error in determination of the<br />

azimuth peaking factor, ε = 7 3<br />

% ; uncertainties of the surface of the fuel meat, ε = 4 4<br />

% ;<br />

error in the correction coefficient K, ε =1 5<br />

% ; uncertainties in determination of the fuel<br />

concentration in the fuel plates, ε 6 = 20 % .<br />

To establish an operational limit, in addition to the errors and tolerances, a correction<br />

factor is considered for the effective power deposited in the coolant flow and for the thermal<br />

diffusion of heat through the fuel cladding. Assuming a statistical distribution of all errors,<br />

influencing the calculated heat flux, the following ‘security factors’ have been determined: (i)<br />

'security factor' for the maximum probable heat flux at the hot spot: this flux has to be<br />

compared to the heat flux giving an allowed wall temperature of fuel cladding, which<br />

corresponds to the nominal hydraulic conditions:<br />

hot spot<br />

max<br />

5<br />

2<br />

i=<br />

1<br />

sq = 1+<br />

∑ εi<br />

= 1.22<br />

(3)<br />

(ii) 'security factor' for the maximum probable mean heat flux along the hot streamline: from<br />

the point of view of flow instability, taking into account the total void fraction in the water gap,<br />

this flux has to be compared with the heat flux giving a possible flow instability at the nominal<br />

hydraulic conditions, where all factors and tolerances are taken with the most unfavourable<br />

value:<br />

hot line<br />

max<br />

6<br />

2<br />

i=<br />

1<br />

sq = 1+<br />

∑ εi<br />

= 1.30<br />

(4)<br />

2.3 Determination of maximum admissible heat flux<br />

The Onset of Nucleate Boiling (ONB) (Bergles & Rohsenow) with sub-cooling occurs when<br />

the fuel temperature exceeds the saturation temperature of the coolant by ΔT onb . The model<br />

of Hsu, calculated by Bergles and Rohsenow for maximum heat flux 600 W/cm 2 at nominal<br />

0<br />

hydraulics conditions, gave ΔTonb = 9.5 C using the following expression:<br />

195 of 455

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