Abstract
Highly accurate activation calculations are the basis of radiation protection optimization design, and the accuracy of activation calculations depends on nuclear data. Based on the ENDF/B-VIII.0 and JEFF3.3 decay evaluation libraries, the influence of different nuclear data on the reactor structural material activation calculation is analyzed, and the nuclear data-related sensitivity and uncertainty quantification of radioactivity, decay heat and photon sources are carried out by the global sensitivity analysis method and the Latin Hypercube Sampling method. Based on uncertainty data in ENDF/B-VIII.0 and JEFF3.3, quantifying the uncertainty of radioactivity, decay heat and photon source in the shutdown dose calculation of reactor structural materials, the maximum uncertainty of radioactivity and decay heat reach 4.54 and 1.45%, respectively. The half-life and decay energy of 55Fe are the main sources of uncertainty.
Highlights
Nuclear data are the basic input parameters of activation calculations, and their accuracy directly affects the activation calculation results (Liem and Sembiring, 2013; Tsilanizara and Huynh, 2021)
The activation library of the depletion and decay code ORIGEN2 was updated based on ENDF/B-VIII.0 and JEFF3.3 decay evaluation libraries, and uncertainty quantification analysis of activation calculations and global sensitivity analysis of nuclear data were carried out
(1) The uncertainties of radioactivity, decay heat and photon source of the reactor structure material within 48 years of reactor shutdown due to nuclear data perturbation are obtained by uncertainty analysis, and the radioactivity will reach the maximum uncertainty of 4.54% at 10 years and the maximum uncertainty of 1.45% for decay heat at 5 years
Summary
Nuclear data are the basic input parameters of activation calculations, and their accuracy directly affects the activation calculation results (Liem and Sembiring, 2013; Tsilanizara and Huynh, 2021). The calculation process is shown in Figure 3: 1) Determine the nuclides that have important effects on the radioactivity, decay heat and photon source in the activation calculation model; 2) Specify the range of values and probability distribution of nuclear data of nuclides, select the sampling method and obtain different sample combinations; 3) Pass the sample combinations obtained by sampling to the ORIGEN2 code for calculation and obtain the output file; 4) Pass the output file to the SIMLAB program and use the program to perform sensitivity analysis on the results and obtain the correlation coefficients of the input and output values. The important characteristic parameters of radioactivity, decay heat and photon source are used as uncertainty output parameters in the analysis of NUREG/CR6115 reactor structural material activation calculations. The magnitude of the absolute value indicates the strength of the sensitivity; the positive sign of the value indicates a positive correlation, the negative sign indicates a negative correlation, and 0 indicates no correlation, and its expression is shown in Eq 4
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