Measurement of the 236U(n,f) cross section at fast neutron energies with Micromegas Detectors

Author:

Diakaki M.,Michalopoulou V.,Tsinganis A.,Axiotis A.,Kalamara A.,Kokkoris M.,Lagoyiannis A.,Patronis N.,Stamatopoulos A.,Vlastou R.

Abstract

In the present work, the measurement of the 236U(n,f) cross section was performed, with reference to the 238U(n,f) reaction. The measurements took place at the neutron beam facility of the National Centre for Scientific Research "Demokritos" (Greece) and the quasi-monoenergetic neutron beams were produced via the 2H(d,n)3He reaction in the energy range 4–10 MeV. Five actinide targets (two 236U, two 238U and one 235U) and the corresponding Micromegas detectors for the detection of the fission fragments were used. Detailed Monte Carlo simulations were performed, on one hand for the study of the neutron flux and energy distribution at the position of each target, and on the other hand for the study of the energy deposition of the fission fragments in the active volume of the detector. The mass and homogeneity of the actinide targets were experimentally determined via alpha spectroscopy and the Rutherford Backscattering Spectrometry, respectively. The experimental procedure, the analysis, the methodology implemented to correct for the presence of parasitic neutrons and the cross section results will be presented and discussed.

Publisher

EDP Sciences

Reference24 articles.

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2. Pronyaev V.G., IAEA report No. INDC(NDS)-408 (1999)

3. Fast Neutron–Induced Fission Cross Sections of 233, 234, 236, 238U up to 200 MeV

4. The Fission Cross Sections of Uranium-234 and Uranium-236 Relative to Uranium-235

5. The fission cross sections of 233U, 234U, 236U, 238U, 237Np, 239Pu, 240Pu and 241Pu relative to that of 235U for neutrons in the energy range 1–14 MeV

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