TY - JOUR
T1 - Isotopic molybdenum total neutron cross section in the unresolved resonance region
AU - Bahran, R.
AU - Barry, D.
AU - Block, R.
AU - Leinweber, G.
AU - Rapp, M.
AU - Daskalakis, A.
AU - Blain, E.
AU - Williams, D.
AU - McDermott, B.
AU - Leal, L.
AU - Danon, Y.
N1 - Publisher Copyright:
© 2015 American Physical Society. ©2015 American Physical Society.
PY - 2015/8/4
Y1 - 2015/8/4
N2 - Accurate isotopic molybdenum nuclear data are important because molybdenum can exist in nuclear reactor components including fuel, cladding, or as a high yield fission product. High-resolution time-of-flight neutron transmission measurements on highly enriched isotopic metallic samples of Mo95, Mo96, Mo98, and Mo100 were performed in the resonance energy range from 1 to 620keV. The measurements were taken with the newly developed modular Li6-glass transmission detector positioned at the 100-m experimental flight station. In the unresolved energy region (URR), new comprehensive methods of analysis were developed and validated in order to obtain accurate neutron total cross-section data from the measurement by correcting for background and transmission enhancement effects. Average parameters and fits to the total cross section for Mo95 were obtained using the Hauser-Feshbach statistical model code fitacs, which is currently incorporated into the sammy code. The fits to the experimental data deviate from the current evaluated nuclear data file/B-VII.1 isotopic Mo evaluations by several percent in the URR.
AB - Accurate isotopic molybdenum nuclear data are important because molybdenum can exist in nuclear reactor components including fuel, cladding, or as a high yield fission product. High-resolution time-of-flight neutron transmission measurements on highly enriched isotopic metallic samples of Mo95, Mo96, Mo98, and Mo100 were performed in the resonance energy range from 1 to 620keV. The measurements were taken with the newly developed modular Li6-glass transmission detector positioned at the 100-m experimental flight station. In the unresolved energy region (URR), new comprehensive methods of analysis were developed and validated in order to obtain accurate neutron total cross-section data from the measurement by correcting for background and transmission enhancement effects. Average parameters and fits to the total cross section for Mo95 were obtained using the Hauser-Feshbach statistical model code fitacs, which is currently incorporated into the sammy code. The fits to the experimental data deviate from the current evaluated nuclear data file/B-VII.1 isotopic Mo evaluations by several percent in the URR.
UR - https://www.scopus.com/pages/publications/84939609545
U2 - 10.1103/PhysRevC.92.024601
DO - 10.1103/PhysRevC.92.024601
M3 - Article
AN - SCOPUS:84939609545
SN - 0556-2813
VL - 92
JO - Physical Review C - Nuclear Physics
JF - Physical Review C - Nuclear Physics
IS - 2
M1 - 024601
ER -