The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor

<table class="fixed-width table-group" id="tab5"><tr><td><table class="table"><colgroup><col style="width:7.41em"/><col style="width:7.41em"/><col style="width:10.19em"/></colgroup><tr><td class="thead-hr" colspan="3"><hr/></td></tr><tr class="thead"><td class="align_left"><b>Airborne radioactive material</b></td><td class="align_center"><b>Design value (Bq/a) [<a href="/journals/stni/2018/7389121/#B23" target="_blank">15</a>]</b></td><td class="align_center"><b>NORMAL  </b><b>(Bq/a)</b></td></tr><tr><td class="thead-hr" colspan="3"><hr/></td></tr><tr><td class="align_left">H-3</td><td class="align_center">9.75E+11</td><td class="align_center">9.76E+11</td></tr><tr><td class="align_left">C-14</td><td class="align_center">6.25E+11</td><td class="align_center">6.23E+11</td></tr><tr><td class="align_left">Ar-41</td><td class="align_center">4.10E+12</td><td class="align_center">4.52E+12</td></tr><tr><td class="align_left">Iodine isotopes</td><td class="align_center">2.01E+09</td><td class="align_center">2.00E+09</td></tr><tr class="table-tr"><td colspan="3"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>The comparison of design value and NORMAL calculation results of the airborne radioactive discharge of HTR-PM under normal operation condition.</div>

Science and Technology of Nuclear Installations

tab5

Table 5

Table 5: The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor 