Thermal limit of helical-nut surfaced tubes for divertor cooling

Abstract The exigencies imposed by the elevated thermal flux directed at a divertor under a unidirectional heating paradigm necessitate a rigorous thermo-hydraulic scrutiny of cooling channels with enhanced cooling efficacy. In this exposition, we systematically scrutinize the thermal limit characteristics of a helical-nut surfaced (HNS) tube, a prospective cooling conduit for fusion reactors. To accurately simulate the unidirectional high thermal load and subcooled flow conditions endemic to a tokamak, we have meticulously engineered a Joule heating apparatus capable of imparting heat loads up to 14.8 MW m −2 alongside a hermetically sealed experimental loop. Our empirical investigations delineate the influence of systemic parameters on the thermal limit. It is discerned that the thermal limit appreciably escalates in concordance with rising subcooling and mass flow rates. This phenomenon stems from the fact that elevated subcooling expedites vapor condensation within the channel, while an augmented flow rate enhances forced convective heat transfer dynamics. Concomitantly, the onset of nucleate boiling heat flux is observed to diminish, which can be attributed to the decrement in latent heat and liquid surface tension as pressure rises. Nonetheless, it is observed that system pressure does not exert a substantive impact on the thermal limit. Historical investigations have grappled with the challenge posed by predicting the thermal limit for HNS tubes under unidirectional high thermal loads, as extant thermal limit correlations—analyzed under subcooled flow boiling conditions—fail to account for the intricate helical fin surface structures intrinsic to HNS tubes. Consequently, these correlations consistently underestimate the thermal limit. In response, this study pioneers the formulation of a novel correlation, capable of prognosticating the thermal limit of HNS tubes subjected to unilateral high thermal loads. This correlation is meticulously derived deploying Python-based artificial intelligence regression techniques. The veracity of this innovative thermal limit correlation is rigorously validated, showcasing its proficiency in precisely predicting both the experimental results delineated in this study and the thermal limit data previously documented in extant literature with commendable accuracy.

Authors

Institutions

Publication Details

Journal
Nuclear Fusion
Published
2025-03-17
DOI
https://doi.org/10.1088/1741-4326/adc145
Citations
1
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.52
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Thermal limit of helical-nut surfaced tubes for divertor cooling

Seung-Hwan Yu, Ji Hwan Lim
1 citations
Nuclear Fusion
Fusion materials and technologies
0.52
article

Thermal limit of helical-nut surfaced tubes for divertor cooling

Seung-Hwan Yu, Ji Hwan Lim
article en
1 citations

Abstract

Abstract The exigencies imposed by the elevated thermal flux directed at a divertor under a unidirectional heating paradigm necessitate a rigorous thermo-hydraulic scrutiny of cooling channels with enhanced cooling efficacy. In this exposition, we systematically scrutinize the thermal limit characteristics of a helical-nut surfaced (HNS) tube, a prospective cooling conduit for fusion reactors. To accurately simulate the unidirectional high thermal load and subcooled flow conditions endemic to a tokamak, we have meticulously engineered a Joule heating apparatus capable of imparting heat loads up to 14.8 MW m −2 alongside a hermetically sealed experimental loop. Our empirical investigations delineate the influence of systemic parameters on the thermal limit. It is discerned that the thermal limit appreciably escalates in concordance with rising subcooling and mass flow rates. This phenomenon stems from the fact that elevated subcooling expedites vapor condensation within the channel, while an augmented flow rate enhances forced convective heat transfer dynamics. Concomitantly, the onset of nucleate boiling heat flux is observed to diminish, which can be attributed to the decrement in latent heat and liquid surface tension as pressure rises. Nonetheless, it is observed that system pressure does not exert a substantive impact on the thermal limit. Historical investigations have grappled with the challenge posed by predicting the thermal limit for HNS tubes under unidirectional high thermal loads, as extant thermal limit correlations—analyzed under subcooled flow boiling conditions—fail to account for the intricate helical fin surface structures intrinsic to HNS tubes. Consequently, these correlations consistently underestimate the thermal limit. In response, this study pioneers the formulation of a novel correlation, capable of prognosticating the thermal limit of HNS tubes subjected to unilateral high thermal loads. This correlation is meticulously derived deploying Python-based artificial intelligence regression techniques. The veracity of this innovative thermal limit correlation is rigorously validated, showcasing its proficiency in precisely predicting both the experimental results delineated in this study and the thermal limit data previously documented in extant literature with commendable accuracy.

Nuclear FusionVol. 65(4)
Korea Atomic Energy Research Institute (KR)
Openalex Percentile: Top 41%
Fusion materials and technologies
0.52
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.