Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation

<table class="table-group" id="tab4"><tr><td><table class="table"><tr><td class="thead-hr" colspan="5"><hr/></td></tr><tr class="thead"><td class="align_left">Initial source</td><td class="align_center">Unit</td><td class="align_center">Volume no.</td><td class="align_center">CsI gas (Bq)</td><td class="align_center">CsOH aerosols (Bq)</td></tr><tr><td class="thead-hr" colspan="5"><hr/></td></tr><tr><td class="align_left">SFP</td><td class="align_center">1</td><td class="align_center">1</td><td class="align_center">1.64<i>E</i> + 15</td><td class="align_center">2.87<i>E</i> + 14</td></tr><tr><td class="align_left">SFP</td><td class="align_center">3</td><td class="align_center">9</td><td class="align_center">3.92<i>E</i> + 15</td><td class="align_center">6.86<i>E</i> + 14</td></tr><tr class="table-tr"><td colspan="5"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

<div>Cesium source term in the SFPs used for calculation in Modified ART Mod 2.</div>

Science and Technology of Nuclear Installations

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Table 4

Table 4: Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation 

Table 4 | Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation 