44 BWR Waste Package Loading Curve Evaluation
The objective of this calculation is to evaluate the required minimum burnup as a function of average initial boiling water reactor (BWR) assembly enrichment that would permit loading of fuel into a potential 44 BWR waste package (WP). The potential WP design is illustrated in Attachment I. The scope of this calculation covers a range of initial enrichments from 1.5 through 5.0 weight percent U-235, and a burnup range of 0 through 50 GWd/mtU.
- Research Organization:
- Yucca Mountain Project, Las Vegas, Nevada (US)
- Sponsoring Organization:
- US Department of Energy (US)
- OSTI ID:
- 804724
- Report Number(s):
- CAL-UDC-NU-000005, Rev. 00; MOL.20011114.0132, DC# 25017
- Country of Publication:
- United States
- Language:
- English
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