Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident

<table class="table-group" id="tab2"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td class="align_left">Fuel assembly dimensions (mm)</td><td class="align_center">1015 × 76.2 × 8.0</td></tr><tr><td class="align_left" colspan="2"><hr/></td></tr><tr><td class="align_left">No. of plates per fuel element</td><td class="align_center">21</td></tr><tr><td class="align_left">Fuel material</td><td class="align_center">U<sub>3</sub>Si<sub>2</sub></td></tr><tr><td class="align_left"><sup>235</sup>U enrichment (wt %)</td><td class="align_center">19.75</td></tr><tr><td class="align_left">Uranium density (g/cm<sup>3</sup>)</td><td class="align_center">4.8</td></tr><tr><td class="align_left">Fuel meat density (g/cm<sup>3</sup>)</td><td class="align_center">6.543</td></tr><tr><td class="align_left">Fuel plate dimensions (mm)</td><td class="align_center">680.0 × 70.7 × 1.27</td></tr><tr><td class="align_left">Fuel plate active dimensions (mm)</td><td class="align_center">640 × 62.1 × 0.51</td></tr><tr><td class="align_left">Cladding material (aluminum alloy)</td><td class="align_center">AG3NE</td></tr><tr><td class="align_left">Cladding density (g/cm<sup>3</sup>)</td><td class="align_center">2.700</td></tr><tr><td class="align_left">Cladding thickness (mm)</td><td class="align_center">0.38</td></tr><tr><td class="align_left">Fuel cycle length (EFPD)</td><td class="align_center">50</td></tr><tr><td class="align_left">Discharge EFPD</td><td class="align_center">900</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>Technical specifications and material data of the fuel element.</div>

Science and Technology of Nuclear Installations

tab2

Table 2

Table 2: Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident 