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2021QU03      Appl.Radiat.Isot. 173, 109711 (2021)

N.Quartemont, N.Gharibyan, K.Moody, J.E.Bevins

Uranium integral fission product yields for a spectrally-shaped 14.1 MeV neutron source at the National Ignition Facility

NUCLEAR REACTIONS ¹⁹⁷Au(n, 2n), (n, γ), ⁹⁰Zr, ⁵⁵Mn(n, 2n), ⁵⁵Mn(n, γ), ^113,115In(n, n'), ¹¹⁵In(n, γ), ²³⁸U, ¹⁸⁶W(n, γ), ⁵⁸Ni(n, 2n), (n, p), ²⁷Al(n, α), ²³⁵U(n, F), E=14.1 MeV; measured reaction products, Eγ, Iγ. ^85,87,88Kr, ^91,92Sr, ^92,93Y, ^95,97Zr, ⁹⁹Mo, ^103,105Ru, ¹⁰⁵Rh, ^109,112Pd, ^111,113Ag, ¹¹⁵Cd, ^127,129Sb, ^{131,132,133,135}I, ^131,132Te, ¹³⁵Xe, ¹³⁶Cs, ^139,140Ba, ^{141,142,143,144}Ce, ¹⁴²La, ¹⁴⁷Nd, ^149,151Pm, ^153,156Sm, ^156,157Eu, ¹⁵⁹Gd, ¹⁶¹Tb; deduced cumulative and independent fission product yields using the neutron spectrum modeled in MCNP5 using ENDF-B/VIII.0 and IRDFF-II nuclear data libraries.

doi: 10.1016/j.apradiso.2021.109711
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14720.