COMMERCIAL SPENT NUCLEAR FUEL ASSEMBLY WASTE VOLUME AND WEIGHT ESTIMATION FOR 63,000 MTU Page: 3 of 21
This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided to Digital Library by the UNT Libraries Government Documents Department.
The following text was automatically extracted from the image on this page using optical character recognition software:
Title: Commercial Spent Nuclear Fuel Assembly Waste Volume and Weight Estimation for 63,000 MTU
Document Identifier: CAL-MGR-ME-000001 REV 00 Page 3 of 20
The purpose of this calculation is to create a high-level estimation of the weights and volume of
the commercial spent nuclear fuel (SNF) assemblies, at the time of repository receipt, that will
comprise 63,000 metric tons of uranium (MTU) waste. The results of this calculation are for
informational purposes only and are not intended to be used as input to design documents. This
calculation was prepared in accordance with procedure AP-3.12Q REV 00 ICN 0, Calculations.
As this calculation is considered a high-level estimation, only two specific assemblies will be
chosen to represent the commercial SNF assemblies. One assembly will be a pressurized water
reactor (PWR) assembly and the other will be a boiling water reactor (BWR) assembly. From
source term tables, generated in Refs. 4 and 6, radionuclide information will be extracted for the
two representative assemblies. Radionuclide information from the two assemblies will be
projected to the 63,000 MTU based on the distribution of PWR and BWR assemblies assumed in
the Viability Assessment (VA) design basis waste stream.
3.1 It is assumed that the densities used to determine waste volume will be based on 95% of
the theoretical densities. When fuel pellet densities are listed, generally there is a
specification as to what percent of theoretical density was obtained. The foundation of
this assumption is from Ref. 10, Sections 188.8.131.52 and 184.108.40.206, which reflects that fuel
pellet volumes range from 94 to 95 percent of their theoretical density. While this may
not be true for waste components, the basis of this assumption is to attempt to
approximate a more realistic volume. This assumption will be applied to all waste
volumes at the end of the calculation as an adjustment in Section 5.7.
3.2 It is assumed that one representative PWR assembly and one BWR assembly will
adequately reflect the weights and volumes for those types of assemblies over the entire
63,000 MTU of commercial assembly waste. The basis of this assumption is that while
the quantity of a specific radionuclide may be extremely important for a particular
application, for this estimate of weight and volume, these variations should not
significantly affect the results. This assumption is used throughout this calculation.
Waste Package Operations
Here’s what’s next.
This report can be searched. Note: Results may vary based on the legibility of text within the document.
Tools / Downloads
Get a copy of this page or view the extracted text.
Citing and Sharing
Basic information for referencing this web page. We also provide extended guidance on usage rights, references, copying or embedding.
Reference the current page of this Report.
Colton, B.A. COMMERCIAL SPENT NUCLEAR FUEL ASSEMBLY WASTE VOLUME AND WEIGHT ESTIMATION FOR 63,000 MTU, report, July 22, 1999; Las Vegas, Nevada. (digital.library.unt.edu/ark:/67531/metadc874660/m1/3/: accessed June 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.