A Preliminary Performance Assessment for Salt Disposal of HighpLevel Nuclear Waste - 12173 2018-07-30T21:56:01+00:00

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Filename SAND2012-0158C.pdf
filesize 912.3 kB
Version 1
date February 26-March 1, 2012
Downloaded 237 times
Category Advanced Nuclear Energy, Defense Waste Management, ECIS, Energy Security, Events, Nuclear Energy, Nuclear Energy Safety, Workshop
author Joon H. Lee, Daniel Clayton, Carlos Jove-Colon, Yifeng Wang
report-id SAND2012-0158C
year 2012
event WM2012 Conference
location Phoenix, Arizona

A salt repository is one of the four geologic media currently under study by the U.S. DOE Office
of Nuclear Energy to support the development of a long-term strategy for geologic disposal of
commercial used nuclear fuel (UNF) and high-level radioactive waste (HLW). The immediate
goal of the generic salt repository study is to develop the necessary modeling tools to evaluate
and improve the understanding of the repository system response and processes relevant to
long-term disposal of UNF and HLW in salt formation. The current phase of this study considers
representative geologic settings and features adopted from previous studies for salt repository
sites. For the reference scenario, the brine flow rates in the repository and underlying interbeds
are very low, and transport of radionuclides in the transport pathways is dominated by diffusion
and greatly retarded by sorption on the interbed filling materials. I-129 is the dominant annual
dose contributor at the hypothetical accessible environment, but the calculated mean annual
dose is negligibly small. For the human intrusion (or disturbed) scenario, the mean mass
release rate and mean annual dose histories are very different from those for the reference
scenario. Actinides including Pu-239, Pu-242 and Np-237 are major annual dose contributors,
and the calculated peak mean annual dose is acceptably low.