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September 8–11, 2025
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.
A. H. Spano
Nuclear Science and Engineering | Volume 15 | Number 1 | January 1963 | Pages 37-51
Technical Paper | doi.org/10.13182/NSE63-A26262
Articles are hosted by Taylor and Francis Online.
Knowledge of the Doppler coefficient associated with the nonuniform temperature distribution conditions obtained in a reactor runaway is of importance to reactor safety considerations of low-enrichment oxide cores. Measurement of this dynamic coefficient has been made at Spert in an investigation of the kinetic behavior of a water-moderated, UO2-fuel-rod reactor, by means of self-limiting power excursion tests covering a range of initial asymptotic reactor periods from 31 sec to 3.2 msec. In the long-period region, reactor shutdown was provided both by various heat-transfer-dependent mechanisms effecting loss of moderator from the core and by Doppler broadening. In the short-period region below 7 msec, where the reactor period is small compared to the thermal time constant of the UO2 fuel rods and reactor shutdown is provided essentially by the Doppler reactivity alone, the data indicate Rc(tm) = −6.2 , where Rc(tm) and Em are, respectively, the compensated reactivity and energy (Mw-sec) at the time of peak power. An additional reactivity effect, positive in sign and resulting from systematic bowing of the fuel rods during the transient power burst, yielded a significant change in burst shape behavior. The fuel rod bowing effect was separated from other feedback effects by performing two series of tests, with and without mechanical constraints on the fuel rods. In the shortest period test, the maximum power was about 7500 Mw, the total energy released in the burst was about 110 Mw-sec, and the maximum pressure measured was less than 8 psi. No damage occurred as a consequence of this or any other test.