Experimental Characterization of a Passive Emergency Heat Removal System for a GenIII<svg style="vertical-align:-0.73799pt;width:15.475px;" id="M1" height="13.3" version="1.1" viewBox="0 0 15.475 13.3" width="15.475"  xmlns="http://www.w3.org/2000/svg">
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<table>Steam generator pressure drops as a function of inlet subcooling (Data obtained with <math id="M58" xmlns="http://www.w3.org/1998/Math/MathML"><mrow><mi>p</mi></mrow></math> = 30.5 bar − power = 23 kW).</table>

Science and Technology of Nuclear Installations

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Figure 10

Figure 10: Experimental Characterization of a Passive Emergency Heat Removal System for a GenIII<svg style="vertical-align:-0.73799pt;width:15.475px;" id="M1" height="13.3" version="1.1" viewBox="0 0 15.475 13.3" width="15.475"  xmlns="http://www.w3.org/2000/svg">
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Science and Technology of Nuclear Installations

Experimental Characterization of a Passive Emergency Heat Removal System for a GenIII + Reactor

Figure 10

Experimental Characterization of a Passive Emergency Heat Removal System for a GenIII Reactor