Abstract
The Yucca Mountain site in southern Nevada in the western United States is currently being characterized for its suitability as a site for a repository for spent nuclear fuel and high level waste. The information contained herein represents the current approach to surface and subsurface facility design for the potential repository at Yucca Mountain. These design concepts will continue to be assessed and modified as appropriate, so the design concepts described in this paper will evolve in the future. The Waste Handling Building will integrate the five primary systems that receive, lift, unload, handle, reload, package, and deliver high-level radioactive waste to subsurface waste handling systems. The Waste Handling Building will have one canister transfer line that moves the disposable fuel canisters through the building to prepare the waste for emplacement in the repository. The Waste Handling Building will have two assembly transfer lines. The disposal container handling system will receive loaded disposal containers from both the canister transfer system and the assembly transfer system. Each disposal container will again be purged with inert gas, after which the container's lids will be welded and the welds inspected. If the welds meet inspection criteria, the sealed disposal container will be reclassified
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Harrington, P G
[1]
- US Department of Energy, Yucca Mountain Site Characterization Office, Las Vegas, NV (United States)
Citation Formats
Harrington, P G.
Application of remote technology for spent fuel management as proposed for a potential repository at Yucca Mountain.
IAEA: N. p.,
2005.
Web.
Harrington, P G.
Application of remote technology for spent fuel management as proposed for a potential repository at Yucca Mountain.
IAEA.
Harrington, P G.
2005.
"Application of remote technology for spent fuel management as proposed for a potential repository at Yucca Mountain."
IAEA.
@misc{etde_20617731,
title = {Application of remote technology for spent fuel management as proposed for a potential repository at Yucca Mountain}
author = {Harrington, P G}
abstractNote = {The Yucca Mountain site in southern Nevada in the western United States is currently being characterized for its suitability as a site for a repository for spent nuclear fuel and high level waste. The information contained herein represents the current approach to surface and subsurface facility design for the potential repository at Yucca Mountain. These design concepts will continue to be assessed and modified as appropriate, so the design concepts described in this paper will evolve in the future. The Waste Handling Building will integrate the five primary systems that receive, lift, unload, handle, reload, package, and deliver high-level radioactive waste to subsurface waste handling systems. The Waste Handling Building will have one canister transfer line that moves the disposable fuel canisters through the building to prepare the waste for emplacement in the repository. The Waste Handling Building will have two assembly transfer lines. The disposal container handling system will receive loaded disposal containers from both the canister transfer system and the assembly transfer system. Each disposal container will again be purged with inert gas, after which the container's lids will be welded and the welds inspected. If the welds meet inspection criteria, the sealed disposal container will be reclassified as a waste package. A crane will transfer the waste package to the transporter loading area, where it will be decontaminated and placed on a transporter for emplacement in the subsurface repository. (author)}
place = {IAEA}
year = {2005}
month = {Mar}
}
title = {Application of remote technology for spent fuel management as proposed for a potential repository at Yucca Mountain}
author = {Harrington, P G}
abstractNote = {The Yucca Mountain site in southern Nevada in the western United States is currently being characterized for its suitability as a site for a repository for spent nuclear fuel and high level waste. The information contained herein represents the current approach to surface and subsurface facility design for the potential repository at Yucca Mountain. These design concepts will continue to be assessed and modified as appropriate, so the design concepts described in this paper will evolve in the future. The Waste Handling Building will integrate the five primary systems that receive, lift, unload, handle, reload, package, and deliver high-level radioactive waste to subsurface waste handling systems. The Waste Handling Building will have one canister transfer line that moves the disposable fuel canisters through the building to prepare the waste for emplacement in the repository. The Waste Handling Building will have two assembly transfer lines. The disposal container handling system will receive loaded disposal containers from both the canister transfer system and the assembly transfer system. Each disposal container will again be purged with inert gas, after which the container's lids will be welded and the welds inspected. If the welds meet inspection criteria, the sealed disposal container will be reclassified as a waste package. A crane will transfer the waste package to the transporter loading area, where it will be decontaminated and placed on a transporter for emplacement in the subsurface repository. (author)}
place = {IAEA}
year = {2005}
month = {Mar}
}