Open AccessReview of ENDF/B-VI Fission-Product Cross Sections[Evaluated Nuclear Data File]
Author(s) -
R.Q. Wright,
R.E. MacFarlane
Publication year - 2000
Language(s) - English
Resource type - Reports
DOI - 10.2172/760512
Subject(s) - nuclear data , criticality , computer science , data file , nuclear fission product , nuclear criticality safety , nuclear engineering , oak ridge national laboratory , nuclide , nuclear physics , experimental data , covariance , neutron , physics , fission products , database , engineering , mathematics , statistics
In response to concerns raised in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 93-2, the US Department of Energy (DOE) developed a comprehensive program to help assure that the DOE maintain and enhance its capability to predict the criticality of systems throughout the complex. Tasks developed to implement the response to DNFSB recommendation 93-2 included Critical Experiments, Criticality Benchmarks, Training, Analytical Methods, and Nuclear Data. The Nuclear Data Task consists of a program of differential measurements at the Oak Ridge Electron Linear Accelerator (ORELA), precise fitting of the differential data with the generalized least-squares fitting code SAMMY to represent the data with resonance parameters using the Reich-Moore formalism along with covariance (uncertainty) information, and the development of complete evaluations for selected nuclides for inclusion in the Evaluated Nuclear Data File (ENDFB)