Uncertainty in the nuclear data used for reactor calculations. Sensitivity and uncertainty analysis of reactor performance parameters
This chapter summarizes the techniques developed to estimate and codify nuclear data uncertainty. Focuses on the fifth version of the ENDF/B nuclear data file released in mid-1979. Discusses relevant aspects of a cross-section data base; mathematical properties of uncertainty matrices; the evaluation of nuclear data uncertainty; and existing nuclear data uncertainty files. Reports that distinct progress is being made toward development of comprehensive files of carefully evaluated cross-sections for nuclear system design. Notes that while contemporary evaluations of a cross-section should in principle be equal, they have in practice been unequal because of the variety of techniques used and the different estimates of the information content of each experiment. Concludes that if full value is to be gained from improved files representing differential data, inclusion of integral information must be correctly structured and documented with care so that each piece of information is given proper weight.
- Research Organization:
- Engineering Physics Division Oak Ridge National Laboratory Union Carbide Corp. P.O. Box X Oak Ridge, TN 37830
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6926127
- Journal Information:
- Adv. Nucl. Sci. Technol.; (United States), Vol. 14
- Country of Publication:
- United States
- Language:
- English
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