Neutron calculations for the Pollux cask in the German final repository

Uwe Quade; M. Khamis

doi:10.1117/12.267923

27 February 1997 Neutron calculations for the Pollux cask in the German final repository

Uwe Quade, M. Khamis

Proceedings Volume 2867, International Conference Neutrons in Research and Industry; (1997) https://doi.org/10.1117/12.267923
Event: Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry, 1996, Crete, Greece

Abstract

Neutron dose calculations were performed within the framework of the 'Atkives Handhabungsexperiment AHE', which is part of the Research and Development program on the German Final Repository. The neutron dose fields of the German Pollux cask for disposal of spent fuel were calculated above ground and in a salt mine with spent fuel loadings and with a Cf²⁵² source. In an experiment performed in a former salt mine with a small shielding cask and a Cf²⁵² line source, the future exposure of the mining personnel can be estimated by measuring the neutron dose field. The neutron dose calculations ion this smaller shielding cask predicted the following experimental results and guaranteed that the neutron dose field of this smaller cask was able to simulate the realistic conditions with the POLLUX cask. They further revealed an important neutron dose rate resulting from backscattered neutrons on the salt drift walls.

Citation Download Citation

Uwe Quade and M. Khamis "Neutron calculations for the Pollux cask in the German final repository", Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); https://doi.org/10.1117/12.267923

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