CRC Depletion Calculations for LaSalle Unit I
Publication Date
Attachment(s)
| Attachment | Size |
|---|---|
| B00000000-01717-0210-00097_Part 1_MOL.19991018.0235.pdf (10.71 MB) | 10.71 MB |
| B00000000-01717-0210-00097_Part 2_MOL.19991018.0235.pdf (9.3 MB) | 9.3 MB |
| B00000000-01717-0210-00097_Part 3_MOL.19991018.0235.pdf (15.83 MB) | 15.83 MB |
| B00000000-01717-0210-00097_Part 4_MOL.19991018.0235.pdf (702.41 KB) | 702.41 KB |
Abstract
The purpose of this calculation is to document the LaSalle Unit 1 boiling water reactor (BWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations constitute benchmark calculations that support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository. This calculation incorporates control blade effects and minor variations in the SAS2H assembly modeling.
