Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor

<table class="table-group" id="tab1"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td align="left"><i>Development target</i></td><td align="left"></td></tr><tr><td align="left" colspan="2">
                                    Safety level shall be equal to future light water reactors (LWRs) and related fuel cycle system.</td></tr><tr><td align="left"><i>Design requirements</i></td><td align="left"></td></tr><tr><td align="left">SR-1.1</td><td align="left">Fundamental safety principles shall be observed. Safety standards and guidelines for former SFRs shall be reflected while specific features of new reactors shall be considered</td></tr><tr><td align="left">SR-1.2</td><td align="left">Prevention and mitigation against severe accident initiators shall be considered so as to avoid execution of offsite emergency plans</td></tr><tr><td align="left">SR-1.3</td><td align="left">Total core damage frequency shall be less than 10<sup>−6</sup>/reactor-year considering multiple units in a site, and total containment failure frequency in core damage conditions shall be less than 10<sup>−7</sup>/reactor-year</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

Safety-related development target and design requirements in the FaCT project.

Science and Technology of Nuclear Installations

tab1

Table 1

Table 1: Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor 