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Fuel loading process begins at Palisades
The Palisades nuclear power plant has drawn closer to restart, as plant staff began the process of loading fuel into the reactor vessel on Sunday morning.
The commencement of fuel loading places the Covert, Mich., facility in Mode 6—or the refueling stage—under the plant’s technical specifications, plant owner and operator Holtec International said in a news release. The Palisades reactor core consists of 204 fuel assemblies that include new fuel and partially used fuel from the plant’s most recent operating cycles. According to Holtec, the fuel loading is being conducted in accordance with plant procedures and technical specifications.
J. A. Gomez, P. E. Koehler, T. E. Cutler, A. DeYoung, J. T. Goorley, J. D. Hutchinson, G. McKenzie, G. L. Morgan, S. M. Mosby, W. L. Myers, R. S. Rundberg, V. W. Yuan
Nuclear Science and Engineering | Volume 193 | Number 5 | May 2019 | Pages 537-548
Technical Paper | doi.org/10.1080/00295639.2018.1545956
Articles are hosted by Taylor and Francis Online.
Neutron diagnosed subcritical experiments (NDSEs) aim to measure the fission chain decay of subcritical test objects initiated by neutrons from an external source. The ultimate goal of future NDSEs is to make such measurements on dynamic subcritical objects as they are imploded. As a step toward that goal, we made measurements on three static subcritical assemblies containing highly enriched uranium. Specifically, we measured the die-off of both fission gamma rays and neutrons, with nanosecond resolution over several hundred microseconds, relative to the emission time of neutrons from a source in close proximity to the subcritical objects. As simulations are expected to play a key role in interpreting future NDSEs, we compared our data to detailed MCNP® calculations. There was good agreement between the data and MCNP over die-off times expected to be most important to future NDSEs, but there were significant differences at both earlier and later times. We attempted to reconcile these differences by several changes to the simulations. In particular, we found that reducing the 235U(n,n’) cross section to 80% of the current ENDF7.1 evaluation resulted in much better agreement.