Thermal performance of a depleted uranium shielded storage, transportation, and disposal package Page: 1 of 8
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THERMAL PERFORMANCE OF A DEPLETED URANIUM SHIELDED STORAGE,
TRANSPORTATION, AND DISPOSAL PACKAGE'S. D. Wix
GRAM, Inc.
8500 Menaul Blvd. NE
Albuquerque, New Mexico 87112
I. INTRODUCTION
The U.S. Department of Energy (DOE) is responsible
for management and disposal of large quantities of depleted
uranium (DU) in the DOE complex. Viable economic
options for the use and eventual disposal of the material are
needed. One possible option is the use of DU as shielding
material for vitrified Defense High-Level Waste (DHLW)
storage, transportation, and disposal packages. Use of DU
as a shielding material provides the potential benefit of
disposing of significant quantities of DU during the DHLW
storage and disposal process.
Two DU package concepts have been developed by
Sandia National Laboratories.1 The first concept is the
Storage/Disposal plus Transportation (S/D+T) package. The
S/D+T package consists of two major components: a stor-
age/disposal (S/D) container and a transportation overpack.
The second concept is the S/DT package which is an
integral storage, transportation, and disposal package. The
package concept considered in this analysis is the S/D+T
package with seven DHLW waste canisters.
The S/D+T package provides shielding and contain-
ment for the DHLW waste canisters. The S/D container is
intended to be used as an on-site storage and repository
disposal container. In this analysis, the S/D container is
constructed from a combination of stainless steel and DU.
Other material combinations, such as mild steel and DU, are
potential candidates. The transportation overpack is used to
transport the S/D containers to a final geological repository
and is not included in this analysis.H. R. Yoshimura
Sandia National I boratoriesb
P.O. Box 5800
Albuquerque, New Mexico 87185
The scope of this effort is to calculate the thermal
performance of the S/D container of the S/D+T package in
storage and in an underground repository. The results of the
thermal calculations can allow design changes in the S/D
container and the transportation overpack which will allow
heat dissipation in a more efficient manner.
II. DESCRIPTION
The S/D container and repository were modeled using
PATRAN2 as a pre- and post-processor and P/THERMAL3
as the thermal solver. Calculations of the S/D container and
repository thermal response were made and results from the
calculations are presented.
A. Thermal Model
The thermal model is a two-dimensional representation
of the S/D container and the repository. The thermal model
was used to calculate the thermal response of the S/D
container in on-site storage and in final disposal at the
repository. Axes of symmetry were used to simplify the
thermal model. Details of the S/D container are included in
the model. The thermal model consists of 7179 nodes and
8781 elements. Figure 1 presents the overall thermal model
geometry.
1. On-site storage thermal model. The on-site
storage thermal model assumes storage occurs outdoors in
a hot climate. A steady-state analysis was performed to
calculate the maximum S/b container on-site storage tem-
peratures. Instead of developing a separate on-site storage'This work performed at Sandia National Laboratories, Albuquerque, New Mexico, supported by the U.S. Department of
Energy under Contract DE-AC04-94AL85000.
bA United States Department of Energy facility.
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Wix, S.D. & Yoshimura, H.R. Thermal performance of a depleted uranium shielded storage, transportation, and disposal package, article, March 1, 1994; Albuquerque, New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc624188/m1/1/: accessed March 19, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.