Christoph Genreith

Measurement of thermal neutron capture cross sections of 237Np and 242Pu using prompt gamma neutron activation

Several samples of 237Np and 242Pu were irradiated in the guided cold neutron beam of the prompt gamma activation analysis facility at the Budapest Research Reactor. The thermal neutron capture cross sections of 237 Np and 242Pu were evaluated from the obtained prompt and delayed gamma ray data. The thermal neutron capture cross sections for 237Np(n,γ)238Np was found to be

Determination of (n,γ) Cross Sections of 241Am by Cold Neutron Activation

\sigma_{0} ({}^{237}{\text{Np}}) = 170.4 \pm 7.4\,{\text{b}}

High-flux PGAA for milligram-weight samples

and for 242Pu(n,γ)243Pu to be

First results of the prompt gamma characterization of 237Np

\sigma_{0} ({}^{242}{\text{Pu}}) = 19.6 \pm 3.9\,{\text{b}}

Determination of the thermal neutron cross section of trans-uranium actinides

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241Am: a difficult actinide for (n,gamma) cross section measurement

The need for accurate nuclear reaction data of actinides is well documented and several initiatives from international organizations for improvement have been initiated in the past. This need, particularly in view of method development for non-destructive assay of nuclear waste, has generated a joint effort to use prompt and delayed neutron activation techniques to enhance nuclear capture data of some long lived actinides such as 237Np, 242Pu and 241Am in the frame of a multilateral cooperation. This research initiative is targeted to lay grounds for the development of a non-destructive active neutron interrogation technique to quantify actinides in mixed waste and residues from decommissioning of nuclear installations for safe treatment and storage of such materials.