Five commercial reactor criticals (CRCs) for the LaSalle Unit 1 boiling-water reactor
have been analyzed using KENO V.a, the Monte Carlo criticality code of the SCALE 4 code
system. The irradiated fuel assembly isotopics for the criticality analyses were provided by the
Waste Package Design team at the Yucca Mountain Project in the United States, who performed
the depletion calculations using the SAS2H sequence of SCALE 4. The reactor critical
measurements involved two beginning-of-cycle and three middle-of-cycle configurations. The

This report presents a formal analysis of the five sites nominated as
suitable for characterization for the first repository; the analysis is based
on the information contained or referenced in the environmental assessments
that accompany the site nominations (DOE, 1986a-e). It is intended to aid in
the site-recommendation decision by providing insights into the comparative
advantages and disadvantages of each site. Because no formal analysis can
account for all the factors important to a decision as complex as recommending

The Disposal Subcommittee of the Blue Ribbon Commission on America’s Nuclear Future (BRC) addressed a wide-ranging set of issues, all bearing directly on the central question: “How can the United States go about establishing one or more disposal sites for high-level nuclear wastes in a manner and within a timeframe that is technically, socially, economically, and politically acceptable?”

The Global Nuclear Energy Partnership (GNEP) Program, a United States (U.S.) Department of
Energy (DOE) program, is intended to support a safe, secure, and sustainable expansion of
nuclear energy, both domestically and internationally. Domestically, the GNEP Program would
promote technologies that support economic, sustained
production of nuclear-generated electricity, while
reducing the impacts associated with spent nuclear fuel
disposal and reducing proliferation risks. DOE envisions
changing the U.S. nuclear energy fuel cycle1 from an

The Reactor and Fuel Cycle Technology Subcommittee was formed to respond to the charge—set forth in the charter of the BRC—to evaluate existing fuel cycle technologies and R&D programs in terms of multiple criteria.

This report documents the work performed by ORNL for the Yucca Mountain Project (YMP)
M&O contractor, Framatome Cogema Fuels. The goal of this work was to obtain k values for inf
infinite arrays of flooded boiling-water-reactor (BWR) fuel assemblies as a function of various
burnup/enrichment and cooling-time combinations. These scenarios simulate expected limiting
criticality loading conditions (for a given assembly type) for drift emplacements in a repository. Upon

The "Summary Report of Commercial Reactor Criticality Data for McGuire Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the McGuire Unit 1 reactor.

The ANS/ANS-8.1 standard requires that calculational methods used in determining criticality
safety limits for applications outside reactors be validated by comparison with appropriate critical
experiments. This report provides a detailed description of 34 fresh fuel critical experiments and
their analyses using the SCALE-4.2 code system and the 27-group ENDF/B-IV cross-section library.
The 34 critical experiments were selected based on geometry, material, and neutron interaction