@inproceedings{7a4aa2c92f6041e8af4434a880c22f95,
title = "Calculation of critical heat flux using an inverse heat transfer method to support treat experiment analysis",
abstract = "Heat transfer between cladding and coolant during transient scenarios remains a critical area of uncertainty in understanding nuclear reactor safety. To advance the understanding of transient and accident scenarios involving critical heat flux (CHF), an in-pile experiment for the Transient Reactor Test facility (TREAT) at Idaho National Laboratory (INL) was developed. The experiment, named CHF-Static Environment Rodlet Transient Test Apparatus (CHF-SERTTA), consists of a hollow borated stainless-steel heater rod submerged in a static water pool heated via the (n, α) reaction in boron-10. This paper presents a novel inverse heat transfer method to determine CHF by using the optimization and uncertainty software Dakota to calibrate a RELAP5-3D model of CHFSERTTA to temperature measurements obtained from a thermocouple welded to the surface of the rod.",
keywords = "CHF, Heat transfer, TREAT, Transient boiling",
author = "Robert Armstrong and Charles Folsom and Connie Hill and Colby Jensen",
note = "Publisher Copyright: {\textcopyright} 2020 American Society of Mechanical Engineers (ASME). All rights reserved.; 2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference ; Conference date: 04-04-2020 Through 05-04-2020",
year = "2020",
language = "English",
isbn = "9784888982566",
series = "International Conference on Nuclear Engineering, Proceedings, ICONE",
publisher = "American Society of Mechanical Engineers (ASME)",
booktitle = "Student Paper Competition; Thermal-Hydraulics; Verification and Validation",
}