Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model

<table class="table-group" id="tab1"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td class="align_left">Parameter</td><td class="align_center">Normal data</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">Diameter of kernel</td><td class="align_center">500 <i>μ</i>m</td></tr><tr><td class="align_left">Thickness of buffer layer</td><td class="align_center">95 <i>μ</i>m</td></tr><tr><td class="align_left">Thickness of OPyC layer</td><td class="align_center">40 <i>μ</i>m</td></tr><tr><td class="align_left">Thickness of IPyC layer</td><td class="align_center">40 <i>μ</i>m</td></tr><tr><td class="align_left">Thickness of SiC layer</td><td class="align_center">35 <i>μ</i>m</td></tr><tr><td class="align_left">Diameter of graphite grain</td><td class="align_center">15 <i>μ</i>m</td></tr><tr><td class="align_left">Failure fraction of TRISO at objective burn-up</td><td class="align_center">2.60<i>E</i> − 04</td></tr><tr><td class="align_left">Natural uranium contamination of fuel elements</td><td class="align_center">7.00<i>E</i> − 07</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>Parameters of fuel particles in HTR-PM.</div>

Science and Technology of Nuclear Installations

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Table 1

Table 1: Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model 

Table 1 | Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model 