44-BWR Waste Package Loading Curve Evaluation

Technical Report · Wed Aug 25 04:00:00 EDT 2004

DOI:https://doi.org/10.2172/841260· OSTI ID:841260

Scaglione, J. M. ^[1]

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1. Yucca Mountain Project, Las Vegas, NV (United States)

The objective of this calculation is to evaluate the required minimum burnup as a function of initial boiling water reactor (BWR) assembly enrichment that would permit loading of spent nuclear fuel into the 44 BWR waste package configuration as provided in Attachment IV. This calculation is an application of the methodology presented in ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent (wt%) U-235, and a burnup range of 0 through 40 GWd/MTU. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing BWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report; (2) The results of 100 percent of the current BWR projected waste stream being able to be disposed of in the 44-BWR waste package with Ni-Gd Alloy absorber plates is contingent upon the referenced waste stream being sufficiently similar to the waste stream received for disposal; (3) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials.

• Research Organization: Yucca Mountain Project, Las Vegas, Nevada
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 841260
• Report Number(s): CAL-DSU-NU-000008-REV-00A; DOC.20040825.0005, DC#41029
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
ALLOYS
Alloy
Analysis
BOILING
BURNUP
BWR
Boiling Water Reactor
CONFIGURATION
CRITICALITY
Criticality
Disposal
EVALUATION
FISSION PRODUCTS
Methodology
NUCLEAR FUELS
Nuclear Criticality Safety Program (NCSP)
Nuclear Fuel
PLATES
SPECIFICATIONS
TUFF
VALIDATION
WASTES
WATER