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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.
Govinda S. Srikantiah
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 216-227
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34744
Articles are hosted by Taylor and Francis Online.
The development, validation, and applications of the VIPRE code are presented. The development of specifications for a reactor core subchannel thermal-hydraulics analysis code for utility applications in the evaluation of reactor safety limits during normal operation and accident scenarios is traced. The capabilities of the VIPRE-01 code based on a homogeneous equilibrium model of two-phase flow with algebraic slip are presented along with a discussion of the extensive verification and validation of the code. Utility applications of the code, which received a safety evaluation report from the U.S. Nuclear Regulatory Commission in 1986, in the areas of fuel reload safety analysis, critical heat flux correlation development and testing, thermal margin analysis, and core thermal-hydraulic analysis are presented. The functional specifications and the development of VIPRE-02, an advanced version of the code based on a two-fluid model of two-phase flow that is capable of simulating the reactor core, vessel, and internal structure, are also described. A discussion of the developing applications for VIPRE-02, such as boiling water reactor instability analysis and pressurized water reactor steamline break analysis, is given with some initial results.