Thermomechanical calculation within the HERA programme

Authors

  • Tereza Kinkorová Czech Technical University in Prague, Faculty of Nuclear Sciences and Physical Engineering, Department of Nuclear Reactors, V Holešovičkách 2, 180 00 Prague 8, Czech Republic

DOI:

https://doi.org/10.14311/APP.2023.44.0005

Keywords:

RIA, nuclear fuel performance, thermomechanical calculations

Abstract

HERA (High Burnup Experiments in Reactivity Initiated Accident) is one of the programmes which should replace closed Halden reactor. As the name implies HERA is focused on the tests simulated RIA (Reactivity Initiated Accident) and the aim of the programme is to investigate the performance and behaviour of high burnup fuel in RIA transients. The first phase of HERA programme consists of two steps which are the blind calculation of different RIA scenarios (different pulse width, enthalpy increase, hydrogen content and gap size) and in-reactor test with fresh fuel.
The set of thermomechanical calculation was performed with the FRAPTRAN computer code as part of the first phase of HERA. The influence of several parameters on the fuel behaviour was observed, the varying parameters were the pulse width, peak radial average enthalpy increase, hydrogen content and the hydrogen rim size and gap size. In addition, the effect of type and setting of boundary condition was investigated.

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Published

2023-12-01

How to Cite

Kinkorová, T. (2023). Thermomechanical calculation within the HERA programme. Acta Polytechnica CTU Proceedings, 44, 5–12. https://doi.org/10.14311/APP.2023.44.0005