Calcium bis[bis(trimethylsilyl)amide] (Ca(HMDS)2) is a widely used reagent in diverse stoichiometric and catalytic applications. These processes necessitate a straightforward and large-scale access of this complex. Calcium does not react with primary and secondary amines, but the addition of excess bromoethane to a mixture of calcium turnings and amines in THF at room temperature yields the corresponding calcium bis(amides), calcium bromide and ethane. This in situ Grignard metalation method (iGMM) allows the preparation of calcium bis(amides) from secondary and primary trialkylsilyl-substituted amines and anilines on a multigram scale.1 Background2 The In Situ Grignard Metalation Method (iGMM)3 Properties of [(thf)2M(HMDS)2]4 Applications and Perspective

The stabilization of molten core material in the lower head in case of a severe accident by external cooling of the reactor vessel is regarded as an effective severe accident management measure. In the experiments LIVE-L10 and -L11 the late phase melt pool behaviour of the corium is investigated under different cooling conditions – the former under sub-cooled convection, the latter under nucleate boiling conditions. In this work the experiments are calculated with the severe accident analysis code AC2 – ATHLET-CD 3.1A. Objective of the simulations conducted is the analysis and assessment of the code's capability to simulate the most relevant phenomena that occur during the tests. The simulations are performed with two different lower head modules implemented in ATHLET-CD, AIDA (Analysis of the Interaction between Core Debris and the reactor pressure vessel during severe Accidents) and LHEAD (extended Lower Head module). The simulation results, analysed in comparison with the experimental results, show the capability of both modules to reproduce the respective experiments.

As part of a national research project RUB PSS investigates the cooling process of degraded core sections like debris beds and melt pools. Focus of these works is the simulation of the DEBRIS test facility located at IKE in Stuttgart with both the integral code ASTEC V2.1, developed by IRSN in France, and COCOMO, developed by IKE. In this work, the simulation of two bottom flooding experiments with similar temperature and pressure conditions but different particle types will be presented. The selected tests will be simulated with both a fixed input signal and a gravity-driven quench water flow similar to the actual test conditions. Focus of the analysis is on a comparison of the calculated and experimental results to validate the codes capabilities to simulate the most relevant phenomena which occur while quenching dry and overheated particle formations under varying thermohydraulic conditions. ASTEC is validated using numerous experiments like the PEARL tests that are comparable to those conducted within the DEBRIS test facility and disposes a well-developed model basis for the simulation of late phase phenomena. The resulting temperature evolutions are in good accordance with the experimental results. This is also reflected by the evolution of the quench front and also applies to the conducted COCOMO simulations. The released amount of steam is overestimated by both codes and leaves room for improvement.