Gamma-spectrometric measurement procedure for a clearance concept of radioactively contaminated mercury from nuclear facilities

Abstract Radioactive mercury waste constitutes a significant challenge, as no approved disposal concept yet exists for such in Germany. This work describes decontamination and measurement procedure possible clearance of from nuclear facilities release into reuse or conventional hazardous to reduce the amount repository. The setup were developed evaluated including Monte-Carlo N-Particle® Transport Code ( MCNP® Monte Carlo are registered trademarks owned by Los Alamos National Security, LLC, manager operator Laboratory, (Werner 2018, Werner 2017)), simulations ensure conservative assumptions during measurements. Results decontaminated samples show that pursuant German regulations would be feasible.