The purpose of this revision is to capture additional detail regarding the standard beryllium placed in the I-Loop to moderate neutron flux. The Ad…
Office of NEPA Policy and Compliance
January 13, 2020
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The purpose of this revision is to capture additional detail regarding the standard beryllium placed in the I-Loop to moderate neutron flux. The Advanced Test Reactor (ATR) I-Loop Booster Fuel Basket will hold an ATR Mark-VII fuel element.