The 239Pu production rate is important data in neutronics design for a natural uranium blanket of a fusion-fission hybrid reactor, and the accuracy and reliability should be validated by integral experiments. The distribution of 239Pu production rates in a subcritical natural uranium blanket mock-up was obtained for the first time with a D-T neutron generator by using an activation technique. Natural uranium foils were placed in different spatial locations of the mock-up, the counts of 277.6 keV γ-rays emitted from 239Np generated by 238U capture reaction were measured by an HPGe γ spectrometer, and the self-absorption of natural uranium foils was corrected. The experiment was analyzed using the Super Monte Carlo neutron transport code SuperMC2.0 with recent nuclear data of 238U from the ENDF/B-VII.0, ENDF/B-VII.1, JENDL-4.0u2, JEFF-3.2 and CENDL-3.1 libraries. Calculation results with the JEFF-3.2 library agree with the experimental ones best, and they agree within the experimental uncertainty in general with the average ratios of calculation results to experimental results (C/E) in the range of 0.93 to 1.01.

Feng, S., Liu, R., Lu, X., Yang, Y., Xu, K., Wang, M., et al. (2016). A study of 239Pu production rate in a water cooled natural uranium blanket mock-up of a fusion-fission hybrid reactor. NUCLEAR FUSION, 56(3) [10.1088/0029-5515/56/3/036019].

A study of 239Pu production rate in a water cooled natural uranium blanket mock-up of a fusion-fission hybrid reactor

FENG, SONG
Primo
;
2016

Abstract

The 239Pu production rate is important data in neutronics design for a natural uranium blanket of a fusion-fission hybrid reactor, and the accuracy and reliability should be validated by integral experiments. The distribution of 239Pu production rates in a subcritical natural uranium blanket mock-up was obtained for the first time with a D-T neutron generator by using an activation technique. Natural uranium foils were placed in different spatial locations of the mock-up, the counts of 277.6 keV γ-rays emitted from 239Np generated by 238U capture reaction were measured by an HPGe γ spectrometer, and the self-absorption of natural uranium foils was corrected. The experiment was analyzed using the Super Monte Carlo neutron transport code SuperMC2.0 with recent nuclear data of 238U from the ENDF/B-VII.0, ENDF/B-VII.1, JENDL-4.0u2, JEFF-3.2 and CENDL-3.1 libraries. Calculation results with the JEFF-3.2 library agree with the experimental ones best, and they agree within the experimental uncertainty in general with the average ratios of calculation results to experimental results (C/E) in the range of 0.93 to 1.01.
Articolo in rivista - Articolo scientifico
239; Pu production rate; D-T neutrons; integral neutronics experiment; natural uranium blanket mock-up;
239Pu production rate; D-T neutrons; integral neutronics experiment; natural uranium blanket mock-up; Condensed Matter Physics; Nuclear and High Energy Physics
English
Feng, S., Liu, R., Lu, X., Yang, Y., Xu, K., Wang, M., et al. (2016). A study of 239Pu production rate in a water cooled natural uranium blanket mock-up of a fusion-fission hybrid reactor. NUCLEAR FUSION, 56(3) [10.1088/0029-5515/56/3/036019].
Feng, S; Liu, R; Lu, X; Yang, Y; Xu, K; Wang, M; Zhu, T; Jiang, L; Qin, J; Jiang, J; Han, Z; Lai, C; Wen, Z
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/10281/131961
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