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Atlanta, GA|Atlanta Marriott Marquis
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DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
Claus Petersen, Gerhard Schanz, Siegfried Leistikow
Nuclear Technology | Volume 80 | Number 1 | January 1988 | Pages 161-172
Technical Paper | Advanced Light Water Reactor / Fission Reactor | doi.org/10.13182/NT88-A35556
Articles are hosted by Taylor and Francis Online.
To investigate the potential of the austenitic 15Cr-15Ni steel DIN Material No. 1.4970 as fuel cladding material for an advanced pressurized water reactor (APWR), rod and tube samples were mechanically tested under inert and oxidizing conditions by uniaxial loading and internal pressure up to 1200°C, to receive recent information about its safety potential under emergency cooling conditions. Uniaxial strength values are not influenced by test atmosphere. The total strain is quite low up to 950°C and increases sharply above this temperature to a maximum of ∼80% at 1100°C. The uniaxial creep strength shows a transition to more pronounced temperature and time dependence at 800°C, which is due to recrystallization. Creep rupture strain, which remains around 20% below 950°C, rises above that temperature to a level of 80 to 90%. Steam oxidation slightly decreases burst creep strength, mainly due to metal consumption, and markedly decreases the circumferential strain, especially due to the pronounced tendency to localized deformation at cracks through the defective oxide scale. Even then the circumferential strain of steel tubes is not small enough to meet reactor safety considerations with respect to the emergency cooling of a densely packed APWR core.