Review of ENDF/B-VI Fission-Product Cross Sections[Evaluated Nuclear Data File]
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).
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Science (US)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 760512
- Report Number(s):
- ORNL/TM-13723; TRN: US0005074
- Resource Relation:
- Other Information: PBD: 1 Apr 2000
- Country of Publication:
- United States
- Language:
- English
Similar Records
Covariance matrices for use in criticality safety predictability studies
New Resolved Resonance Region Evaluation for 63Cu and 65Cu for Nuclear Criticality Safety Program