Chemical Isotopic Analysis of Fission Products in PWR-MOX Spent Fuels and Computational Evaluation Using JENDL, ENDF/B, JEF, and JEFF
| Autor: | Tetsuo Matsumura, Yoshiaki Kiyanagi, Akihiro Sasahara, Giorgos Nicolaou |
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| Rok vydání: | 2008 |
| Předmět: | |
| Zdroj: | Journal of Nuclear Science and Technology. 45:390-401 |
| ISSN: | 1881-1248 0022-3131 |
| DOI: | 10.1080/18811248.2008.9711449 |
| Popis: | A chemical isotopic analysis of high-burn-up MOX spent fuels with a burn-up of 45 MWd/kgHM was carried out to accumulate nuclide composition data. Furthermore, computational analysis was performed using the integrated burn-up calculation code system SWAT. The differences between the amounts of fission products obtained by the chemical isotopic analysis and SWAT calculation using JENDL-3.2, JENDL-3.3, ENDF/B-VI.5, ENDF/B-VI.8, JEF-2.2, and JEFF-3.0 were evaluated as the ratios of the calculated values to the experimental ones (C/E ratios). The fission products such as 88Sr, 90Sr, 106Ru, 133Cs, 134Cs, and 135Cs, which are gamma and decay heat sources, neutron absorption nuclides, or burn-up indicators in spent fuels, were further investigated to improve their C/E ratios using the simplified burn-up chains of fission products using JENDL-3.3; consequently, the correction values for the fission yields or capture cross sections of the fission products were estimated using sensitivity coefficients. The C/E rati... |
| Databáze: | OpenAIRE |
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