Abstract
Nuclear data-induced uncertainty of neutronics parameters of one specific ADS design is quantified. The nuclear data adjustment method with available integral data is employed to reduce the uncertainties, and usefulness of these integral data is investigated. Numerical results reveal that the uncertainty reduction by the present nuclear data adjustment is insignificant and restrictive. Future perspecitives are also provided.
Highlights
An accelerator-driven system (ADS) is one of promising nuclear systems, which has a potential to drastically reduce the burden of nuclear waste disposal by burning minor actinoid nuclides
We focus on keff, βeff and coolant void reactivity
It is interesting to point out that the adjusted ND set of case 3 gives larger values at the cycle 2 and the following cycles than other cases. This is because fission reaction rate ratios of Pu-238 to Pu239 are underestimated with the original ND in the FCAIX benchmark problem and this discrepancy is slightly improved by the ND adjustment
Summary
An accelerator-driven system (ADS) is one of promising nuclear systems, which has a potential to drastically reduce the burden of nuclear waste disposal by burning minor actinoid nuclides. Since accurate prediction of neutronics parameters of ADS is essential and important, so much effort have been devoted to quantify and reduce the uncertainties of the ADS neutronics parameters. We quantify nuclear data(ND)-induced uncertainty of neutronics parameters of one specific ADS design. This is accomplished with combined information on microscopic data (nuclear data) and macroscopic data (integral data). This combination is realized by using the ND adjustment method
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