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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
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.
Yuri Orechwa
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 383-396
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A10325
Articles are hosted by Taylor and Francis Online.
Traditionally, the safety of a nuclear reactor system has been assessed through a set of mechanistic calculations of bounding accident sequences using conservative models. Extensive experience in the operation and analysis of nuclear reactor systems has led to two complementary approaches: best-estimate mechanistic calculations with a quantitative estimate of the uncertainty for assessing conformance with acceptance criteria based on technical limits and probabilistic risk analysis of the event sequences due to the probability of failure of safety systems. Both assess the safety of the reactor system; however, the emphasis, especially in the estimation of probabilities, is different in the two approaches. Yet both address the same concern: the safety of the reactor system. We discuss the formal relations that are necessary for a risk-consistent analysis of the safety of the nuclear reactor systems with respect to the two current approaches.