Departure from Nucleate Boiling (DNB) is one of the safety-related Challenge Problems (CP) that CASL is addressing in support of Pressurized Water Reactor (PWR) power uprate, high fuel burnup and plant lifetime extension.
MPACT (Michigan PArallel Characteristics Transport Code) is a new reactor analysis tool being developed at the University of Michigan as an advanced pin-resolved transport capability within VERA (Virtual Environment for Reactor Analysis).
CASL is developing the Virtual Environment for Reactor Applications (VERA) as a key capability to support the analysis of the CASL Challenge Problems.
Density functional theory (DFT) calculations have been employed to better understand the thermodynamic properties of AB2O4 (where A=Fe2+, Ni2+ or Zn2+, and B=Fe3+ or Cr3+) spinel oxides
Fuel rod wear due to grid-to-rod fretting (GTRF) is currently one of the main causes of fuel leakage and is responsible for over 70% of the fuel leaks in pressurized water reactors (PWRs) in the U.S.
CASL connects fundamental research and technology development through an integrated partnership of government, academia, and industry that extends across the nuclear energy enterprise.
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