German Contribution to Item 2 of the Agenda “Status of ... - IAEA
German Contribution to Item 2 of the Agenda “Status of ... - IAEA
German Contribution to Item 2 of the Agenda “Status of ... - IAEA
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„x“ core passes<br />
Temperature [°C]<br />
Lehrstuhl für Reak<strong>to</strong>rsicherheit und –technik<br />
Univ.-Pr<strong>of</strong>. Dr. rer. nat. Hans-Josef Allelein<br />
Institut für Energie- und Klimaforschung<br />
Nukleare Entsorgung und Reak<strong>to</strong>rsicherheit (IEK-6)<br />
Former Approach for FP Release Calculation<br />
(Fuel temperature [°C]<br />
HTR-Module, VSOP)<br />
• FRESCO-II: Fission product release calculation for one or several<br />
representative fuel element(s)<br />
• Time averaged release rate <strong>of</strong> sphere is multiplied with <strong>the</strong> <strong>to</strong>tal<br />
number <strong>of</strong> fuel elements <strong>to</strong> determine core release rate<br />
−<br />
−<br />
−<br />
Conservative approach<br />
No spatial distribution <strong>of</strong> fission product release<br />
More detailed calculation method necessary for best estimate<br />
calculations particularly with regard <strong>to</strong> design basis and beyond<br />
design basis accidents<br />
1200<br />
1000<br />
800<br />
600<br />
400<br />
200<br />
0<br />
0 250 500 750 1000 1250<br />
Time [d]<br />
H.-J. Allelein<br />
TWG-GCR-23<br />
March 5-7, 2013, Vienna<br />
24
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