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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.
M. Tobin, V. Karpenko, A. Burnham, R. Peterson
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 457-463
National Ignition Facility | doi.org/10.13182/FST96-A11962983
Articles are hosted by Taylor and Francis Online.
The National Ignition Facility (NIF) will be configured in its baseline design to achieve ignition and gain using the indirect drive approach. However, the NIF primary criteria and functional requirements require the NIF design “to not preclude” the ability to conduct inertial confinement fusion experiments using the direct drive approach.
The direct drive approach requires symmetrical illumination of an inertial confinement fusion (ICF) capsule where each beam fully subtends the capsule. Therefore, the re-directing of 24 of the 48 NIF beamlines (each consisting of a 2 × 2 beamlet group) from ~30° and ~50° cone angles to ~75° cone angles located near the chamber ‘equator’ is required. This would be accomplished by adjusting intermediate transport mirrors such that the beams would intercept different final mirrors in the Target Bay and be directed into final optics assemblies attached to the chamber at the new port locations. Allowing space to be able to convert from one irradiation scheme to another while fully meeting the mechanical stability requirements for each approach is a significant challenge. Additionally, NIF user needs (features supporting weapons physics, weapons effects, inertial fusion energy, or Basic Energy Sciences) cannot be compromised by direct drive needs.
The target for direct drive, absent a hohlraum, emits much fewer cold x rays than in the indirect drive case. Further, the irradiation scheme, by its nature, may not result in the absorption of all of the 3ω light and therefore could create a unique hazard to the NIF chamber first wall of significant fluences of scattered UV laser light. This paper describes possible design features of the NIF Target Area to allow conversion to a direct drive capability, and discusses some of the differences in post-shot conditions created compared to indirect drive.