Aluminum Data Measurements and Evaluation for Criticality Safety Applications

Details Aluminum Data Measurements and Evaluation for Criticality Safety Applications Aluminum Data Measurements and Evaluation for Criticality Safety Applications

Dec 2002

adsabs.harvard.edu/cgi-bin/nph-data_query?bibcode=2002asap.conf..115l&link_type=abstract

ASTROPHYSICS, SYMMETRIES, AND APPLIED PHYSICS AT SPALLATION NEUTRON SOURCES. Proceedings of the Workshop on ASAP 2002. Held 11-1

Astronomy and Astrophysics

Astrophysics

Scientific paper

The Defense Nuclear Facility Safety Board (DNFSB) Recommendation 93-2 motivated the US Department of Energy (DOE) to develop a comprehensive criticality safety program to maintain and to predict the criticality of systems throughout the DOE complex. To implement the response to the DNFSB Recommendation 93-2, a Nuclear Criticality Safety Program (NCSP) was created including the following tasks: Critical Experiments, Criticality Benchmarks, Training, Analytical Methods, and Nuclear Data. The Nuclear Data portion of the NCSP consists of a variety of differential measurements performed at the Oak Ridge Electron Linear Accelerator (ORELA) at the Oak Ridge National Laboratory (ORNL), data analysis and evaluation using the generalized least-squares fitting code SAMMY in the resolved, unresolved, and high energy ranges, and the development and benchmark testing of complete evaluations for a nuclide for inclusion into the Evaluated Nuclear Data File (ENDF/B). This paper outlines the work performed at ORNL to measure, evaluate, and test the nuclear data for aluminum for applications in criticality safety problems.

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