@inproceedings{c72e4b1e8d1446a9a06aa8ead9a2db5b,
title = "First steps towards a coupled code system for transient calculations for FRM II",
abstract = "A new high density fuel element consisting of an alloy of uranium and molybdenum (UMo) is being developed for the conversion of FRM II's fuel element from high enriched uranium towards lower enriched uranium. Required slight changes of the core geometry demand both neutronical and thermo-hydraulical re-calculations. This is achieved by coupled calculations of the neutronic TORT-TD code and the thermo-hydraulic ATHLET code for transient calculations. In a first step, a substitutional geometry for the involute shaped fuel plates was introduced and validated with already existing and validated MCNP6 models. Afterwards a Serpent 2 model was set up in order to calculate multi group cross sections for the following TORT-TD calculations. It can be shown that the results for reactivity and thermal neutron flux distribution matches within statistical fluctuations. During these studies a non-negligible influence of the (n, 2n) reaction in the beryllium follower of FRM II's control rod could be identified and qualified.",
keywords = "Compact core, MCNP6, Research reactor, Serpent 2, Transients",
author = "C. Reiter and H. Breitkreutz and A. R{\"o}hrmoser and W. Petry",
year = "2016",
language = "English",
series = "Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century",
publisher = "American Nuclear Society",
pages = "4009--4019",
booktitle = "Physics of Reactors 2016, PHYSOR 2016",
note = "Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016 ; Conference date: 01-05-2016 Through 05-05-2016",
}