Re-evaluation of the thermal neutron capture cross section of Nd-147
2016 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 94, 612-617 p.Article in journal (Refereed) PublishedText
In this paper we are proposing a re-evaluation of the thermal-neutron induced capture cross section of Nd-147. A unique measurement exists from which this cross section was calculated in 1974. This original calculation is based on an assumed value for a specific gamma-ray fraction (called F-2), taken from the neighboring nucleus Nd-145. With the availability of reaction codes such as TALYS, such fraction can nowadays be calculated using specific reaction models and parameters. The new value of F-2 indicates a decrease of the thermal cross section by 45%, leading to 243 barns, instead of the 440 barns previously reported. This new cross section impacts the calculation of the number density for the well-known burn-up indicator Nd-148, but as shown, the change is close to the usual experimental uncertainties for the 148Nd number densities, thus having a limited impact on burn-up calculation.
Place, publisher, year, edition, pages
2016. Vol. 94, 612-617 p.
Nd147, Burn-up indicator, Capture cross section
IdentifiersURN: urn:nbn:se:uu:diva-299022DOI: 10.1016/j.anucene.2016.03.024ISI: 000377231600066OAI: oai:DiVA.org:uu-299022DiVA: diva2:948873