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NRC asks for comments on FY 2026 fees proposal
The Nuclear Regulatory Commission is looking for feedback on its proposed rule for fees for fiscal year 2026, which begins October 1. The proposal was published in the March 12 Federal Register.
Based on the FY 2026 budget request because a full-year appropriation has not yet been enacted for the fiscal year, the proposed request is $971.5 million, an increase of $27.4 million from FY 2025.
Leon Leenders, Udo Wehmann, Christopher Grove, Kevin Hesketh, Winfried Zwermann
Nuclear Science and Engineering | Volume 178 | Number 4 | December 2014 | Pages 509-523
Technical Paper | doi.org/10.13182/NSE14-15
Articles are hosted by Taylor and Francis Online.
The zero-power reactor VENUS (Vulcain Experimental Nuclear Study) was built in 1963–1964 at CEN-SCK, Mol, Belgium, as a nuclear mock-up of a projected spectral shift marine reactor called VULCAIN. The facility was modified in 1966 and 1967 in preparation for carrying out a series of critical experiments for the Belgian Plutonium Recycle Programme (PRP), which was partially supported by EURATOM. This was the VENUS-PRP program that took place between 1967 and 1975. VENUS-PRP-9 and VENUS-PRP-9/1, and VENUS-PRP-7 were two series of these PRP configurations that were carried out in 1967–1968 and that have recently been subject to evaluations as part of the Organisation for Economic Co-operation and Development, Nuclear Energy Agency International Reactor Physics Experiment Evaluation Project (IRPhEP). The VENUS-PRP-9 and VENUS-PRP-9/1 configurations focused on the study of the power distribution across the boundary between a standard UO2 fuel region, enriched to 4 wt% 235U, and a mixed oxide fuel region made of UO2, enriched to 3 wt% 235U with ∼1 wt% PuO2, simulating a one-cycle burnt fuel. The IRPhEP evaluation focused on evaluating reaction rates and powers measured along a line that crossed the boundary between the two regions. In the VENUS-PRP-7, VENUS-PRP-7/1, and VENUS-PRP-7/3 series—which used essentially the same fuel pins—reactivities, reactivity worths of substituted and removed fuel pins, and radial fission rate distributions were measured; these quantities were evaluated in the framework of the IRPhEP project.