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Title: A simplified radionuclide source term for total-system performance assessment; Yucca Mountain Site Characterization Project

Abstract

A parametric model for releases of radionuclides from spent-nuclear-fuel containers in a waste repository is presented. The model is appropriate for use in preliminary total-system performance assessments of the potential repository site at Yucca Mountain, Nevada; for this reason it is simpler than the models used for detailed studies of waste-package performance. Terms are included for releases from the spent fuel pellets, from the pellet/cladding gap and the grain boundaries within the fuel pellets, from the cladding of the fuel rods, and from the radioactive fuel-assembly parts. Multiple barriers are considered, including the waste container, the fuel-rod cladding, the thermal ``dry-out``, and the waste form itself. The basic formulas for release from a single fuel rod or container are extended to formulas for expected releases for the whole repository by using analytic expressions for probability distributions of some important parameters. 39 refs., 4 figs., 4 tabs.

Authors:
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
138255
Report Number(s):
SAND-91-0155
ON: DE92004755; TRN: 92:001191
DOE Contract Number:  
AC04-76DP00789
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Nov 1991
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; HIGH-LEVEL RADIOACTIVE WASTES; UNDERGROUND DISPOSAL; SOURCE TERMS; FAILURES; MATHEMATICAL MODELS; YUCCA MOUNTAIN; SPENT FUELS; DIFFUSION BARRIERS; SYSTEMS ANALYSIS; LEAKS; RADIONUCLIDE MIGRATION; GROUND WATER; ALPHA-BEARING WASTES; ENVIRONMENTAL TRANSPORT; SOLUBILITY; CONTAINERS; FUEL-CLADDING INTERACTIONS; WASTE FORMS; Yucca Mountain Project

Citation Formats

Wilson, M L. A simplified radionuclide source term for total-system performance assessment; Yucca Mountain Site Characterization Project. United States: N. p., 1991. Web. doi:10.2172/138255.
Wilson, M L. A simplified radionuclide source term for total-system performance assessment; Yucca Mountain Site Characterization Project. United States. https://doi.org/10.2172/138255
Wilson, M L. 1991. "A simplified radionuclide source term for total-system performance assessment; Yucca Mountain Site Characterization Project". United States. https://doi.org/10.2172/138255. https://www.osti.gov/servlets/purl/138255.
@article{osti_138255,
title = {A simplified radionuclide source term for total-system performance assessment; Yucca Mountain Site Characterization Project},
author = {Wilson, M L},
abstractNote = {A parametric model for releases of radionuclides from spent-nuclear-fuel containers in a waste repository is presented. The model is appropriate for use in preliminary total-system performance assessments of the potential repository site at Yucca Mountain, Nevada; for this reason it is simpler than the models used for detailed studies of waste-package performance. Terms are included for releases from the spent fuel pellets, from the pellet/cladding gap and the grain boundaries within the fuel pellets, from the cladding of the fuel rods, and from the radioactive fuel-assembly parts. Multiple barriers are considered, including the waste container, the fuel-rod cladding, the thermal ``dry-out``, and the waste form itself. The basic formulas for release from a single fuel rod or container are extended to formulas for expected releases for the whole repository by using analytic expressions for probability distributions of some important parameters. 39 refs., 4 figs., 4 tabs.},
doi = {10.2172/138255},
url = {https://www.osti.gov/biblio/138255}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Nov 01 00:00:00 EST 1991},
month = {Fri Nov 01 00:00:00 EST 1991}
}