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Measurement of the 235U Neutron-Induced Fission Cross Section at 14.1 MeV

Oren A. Wasson, Allan D. Carlson, Kenneth C. Duvall

Nuclear Science and Engineering / Volume 80 / Number 2 / Pages 282-303

February 1982

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The 235U neutron-induced fission cross section was measured at a neutron energy of 14.1 MeV using the time-correlated associated-particle technique with the 3H(d,α) n reaction at the National Bureau of Standards 3-MV Van de Graaff Laboratory. The areal density and total mass of the 235U deposits were measured relative to the standard 235U reference deposit (Los Alamos National Laboratory Spare Number 1) using thermal-neutron-induced fission counting. The total mass was also determined from the alpha-particle decay rate. The measured 235U cross section at 14.1 ± 0.1 MeV is 2.080 ± 0.030 b where the uncertainty is one standard deviation. This value agrees within 1% with other recent measurements using this technique and with the ENDF/B-V evaluation.

 
 
 
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