Development of MARS-KS Heatpipe Model and Evaluation of Heat Transfer Performance

To simulate a heat pipe with the MARS-KS (Multi-dimensional Analysis for Reactor Safety – KINS Standard) code, which is widely used for thermal-hydraulic analysis of nuclear power plant systems, the governing equations have been improved and relevant thermal-hydraulic models have been developed. For considering the effects of surface tension at the gas-liquid interface within the heat pipe, capillary pressure term was added to the governing equations. Furthermore, as the internal wick structure alters the existing flow regimes in MARS-KS, this paper describes the modification of the annular flow regime and the corresponding method for calculating the interfacial area. The enhanced model was validated against experimental data, which demonstrates the applicability of the developed model and also suggests the need of improvement of heat transfer model in condenser part. Future work will focus on implementing a liquid momentum correlation to better predict evaporator dryout and applying specialized heat transfer models, such as nucleate boiling and film condensation, to improve simulation fidelity. These developments aim to establish MARS-KS as a robust tool for heat pipe design and safety analysis.

Authors

Publication Details

Journal
The KSFM Journal of Fluid Machinery
Published
2026-02-23
DOI
https://doi.org/10.5293/kfma.2026.29.1.100
Primary Topic
Heat Transfer and Boiling Studies
Type
article
Field-Weighted Citation Impact
0.00
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Development of MARS-KS Heatpipe Model and Evaluation of Heat Transfer Performance

Nihat Erdem Berber, Haeyong Jeong, Doyeong Lee, Kwiseok Ha
The KSFM Journal of Fluid Machinery
Heat Transfer and Boiling Studies
article

Development of MARS-KS Heatpipe Model and Evaluation of Heat Transfer Performance

Nihat Erdem Berber, Haeyong Jeong, Doyeong Lee, Kwiseok Ha
article en

Abstract

To simulate a heat pipe with the MARS-KS (Multi-dimensional Analysis for Reactor Safety – KINS Standard) code, which is widely used for thermal-hydraulic analysis of nuclear power plant systems, the governing equations have been improved and relevant thermal-hydraulic models have been developed. For considering the effects of surface tension at the gas-liquid interface within the heat pipe, capillary pressure term was added to the governing equations. Furthermore, as the internal wick structure alters the existing flow regimes in MARS-KS, this paper describes the modification of the annular flow regime and the corresponding method for calculating the interfacial area. The enhanced model was validated against experimental data, which demonstrates the applicability of the developed model and also suggests the need of improvement of heat transfer model in condenser part. Future work will focus on implementing a liquid momentum correlation to better predict evaporator dryout and applying specialized heat transfer models, such as nucleate boiling and film condensation, to improve simulation fidelity. These developments aim to establish MARS-KS as a robust tool for heat pipe design and safety analysis.

The KSFM Journal of Fluid MachineryVol. 29(1)
Affordable and clean energy
Openalex Percentile: Top 47%
Heat Transfer and Boiling Studies
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.