Accurate neutron-induced reaction data are important to many issues in stockpile stewardship, nuclear reactor design and re-certification, nuclear non-proliferation and nuclear forensics. Of particular interest are the production and destruction reactions for all of the major and most of the minor actinides, including both neutron-induced capture and fission. Recently, we have performed a re-measurement of the neutron-induced fission cross section of 237U (t� = 6.75 days).  This challenging experiment included irradiation of a pure 236U sample in the HFIR reactor at ORNL followed by chemical separation to remove fission products and the 237Np decay product. A 237U target was prepared and installed in a LANL designed compensated ionization chamber which was used in a four day measurement at the Lead Slowing-Down Spectrometer (LSDS) located at the LANSCE WNR facility. Preliminary results from the measurement will be presented.

Measurement of the <sup>237</sup>U(n,f) cross section at the Lead Slowing-Down Spectrometer

246th National Meeting (2013)

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Measurement of the 237U(n,f) cross section at the Lead Slowing-Down Spectrometer

Measurement of the ²³⁷U(n,f) cross section at the Lead Slowing-Down Spectrometer