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WIPP: Lessons in transportation safety
As part of a future consent-based approach by the federal government to site new deep geologic repositories for nuclear waste, local communities and states that are considering hosting such facilities are sure to have many questions. Currently, the Waste Isolation Pilot Plant in New Mexico is the only example of such a repository in operation, and it offers the opportunity for state and local officials to visit and judge for themselves the risks and benefits of hosting a similar facility. But its history can also provide lessons for these officials, particularly the political process leading up to the opening of WIPP, the safety of WIPP operations and transportation of waste from generator facilities to the site, and the economic impacts the project has had on the local area of Carlsbad, as well as the rest of the state of New Mexico.
Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto
Nuclear Science and Engineering | Volume 199 | Number 4 | April 2025 | Pages 586-598
Research Article | doi.org/10.1080/00295639.2024.2383102
Articles are hosted by Taylor and Francis Online.
The multigroup Monte Carlo (MC) neutron transport method with a regionwise even-parity discontinuity factor (REPDF), i.e. the discontinuity factor (DF)–MC method, is developed with the aim to provide a reference solution for deterministic transport calculations with DF. Applying the analogy with optics, neutrons are transmitted or reflected at a region surface during random walks. The probability of transmission or reflection is determined by REPDFs in adjacent regions. The DF is traditionally used in deterministic neutron transport methods to reduce the discretization error due to spatial homogenization and energy condensation. The DF-MC method can treat DF in the framework of the multigroup MC method.
In this paper, the weight cancellation technique based on the closest pair of points using the divide-and-conquer algorithm is used because negative weights appear due to the neutron reflection. The REPDF is calculated by the method of characteristics (MOC). The verification calculations are carried out in the pin-by-pin homogenized and assembly homogenized KAIST-2A core geometry. The DF-MC calculation can reproduce the results of the MOC with the REPDF. These results demonstrate the principle of the DF-MC method and extend the application of the DF to the probabilistic neutron transport method.