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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.2
- 수록면
- 523 - 531 (9page)
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In order to study the sensitivity and the uncertainty of the Moroccan research reactor TRIGA Mark II, amodel of this reactor has been developed in our ERSN laboratory for use with the N-Particle MCNP MonteCarlo transport codes (version 6). In this article, the sensitivities of the effective multiplication factor ofthis reactor are evaluated using the ENDF/B-VII.0, ENDF/B-VII.1 and JENDL-4.0 libraries and in 44 energygroups, for the cross sections of the fuel (U-235 and U-238) and the moderator (H-1 and O-16). However,the quantification of the uncertainty of the nuclear data is performed using the nuclear code NJOY99 forthe generation and processing of covariance matrices. On the one hand, the highest uncertainty deviations, calculated using the ENDFB-VII.1 and JENDL4.0 evaluations, are 2275, 386 and 330 pcmrespectively for the reactions U235(n, f), U235(nn) and H1(n, g). On the other hand, these differences arevery small for the neutron reactions of O-16 and U-238. Regarding the neutron spectra, in CT-mid plane,they are very close for the three evaluations (ENDF/B-VII.0, ENDF/B-VII.1 and JENDL-4.0). These spectrapresent two peaks (thermal and fission) around the energies 0.05 eV and 1 MeV
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