Parametric Thermal and Flow Analysis of ITER Diagnostic Shield Module
Abstract
As part of the diagnostic port plug assembly, the ITER Diagnostic Shield Module (DSM) is designed to provide mechanical support and the plasma shielding while allowing access to plasma diagnostics. Thermal and hydraulic analysis of the DSM was performed using a conjugate heat transfer approach, in which heat transfer was resolved in both solid and liquid parts, and simultaneously, fluid dynamics analysis was performed only in the liquid part. ITER Diagnostic First Wall (DFW) and cooling tubing were also included in the analysis. This allowed direct modeling of the interface between DSM and DFW, and also direct assessment of the coolant flow distribution between the parts of DSM and DFW to ensure DSM design meets the DFW cooling requirements. Design of the DSM included voids filled with Boron Carbide pellets, allowing weight reduction while keeping shielding capability of the DSM. These voids were modeled as a continuous solid with smeared material properties using analytical relation for thermal conductivity. Results of the analysis lead to design modifications improving heat transfer efficiency of the DSM. Furthermore, the effect of design modifications on thermal performance as well as effect of Boron Carbide will be presented.
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1416156
- Grant/Contract Number:
- AC02-09CH11466
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Fusion Science and Technology
- Additional Journal Information:
- Journal Volume: 72; Journal Issue: 3; Journal ID: ISSN 1536-1055
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; numerical analysis; heat transfer; computational fluid dynamics
Citation Formats
Khodak, A., Zhai, Y., Wang, W., Feder, R., Loesser, G., and Johnson, D. Parametric Thermal and Flow Analysis of ITER Diagnostic Shield Module. United States: N. p., 2017.
Web. doi:10.1080/15361055.2017.1330638.
Khodak, A., Zhai, Y., Wang, W., Feder, R., Loesser, G., & Johnson, D. Parametric Thermal and Flow Analysis of ITER Diagnostic Shield Module. United States. https://doi.org/10.1080/15361055.2017.1330638
Khodak, A., Zhai, Y., Wang, W., Feder, R., Loesser, G., and Johnson, D. Mon .
"Parametric Thermal and Flow Analysis of ITER Diagnostic Shield Module". United States. https://doi.org/10.1080/15361055.2017.1330638. https://www.osti.gov/servlets/purl/1416156.
@article{osti_1416156,
title = {Parametric Thermal and Flow Analysis of ITER Diagnostic Shield Module},
author = {Khodak, A. and Zhai, Y. and Wang, W. and Feder, R. and Loesser, G. and Johnson, D.},
abstractNote = {As part of the diagnostic port plug assembly, the ITER Diagnostic Shield Module (DSM) is designed to provide mechanical support and the plasma shielding while allowing access to plasma diagnostics. Thermal and hydraulic analysis of the DSM was performed using a conjugate heat transfer approach, in which heat transfer was resolved in both solid and liquid parts, and simultaneously, fluid dynamics analysis was performed only in the liquid part. ITER Diagnostic First Wall (DFW) and cooling tubing were also included in the analysis. This allowed direct modeling of the interface between DSM and DFW, and also direct assessment of the coolant flow distribution between the parts of DSM and DFW to ensure DSM design meets the DFW cooling requirements. Design of the DSM included voids filled with Boron Carbide pellets, allowing weight reduction while keeping shielding capability of the DSM. These voids were modeled as a continuous solid with smeared material properties using analytical relation for thermal conductivity. Results of the analysis lead to design modifications improving heat transfer efficiency of the DSM. Furthermore, the effect of design modifications on thermal performance as well as effect of Boron Carbide will be presented.},
doi = {10.1080/15361055.2017.1330638},
journal = {Fusion Science and Technology},
number = 3,
volume = 72,
place = {United States},
year = {Mon Jun 19 00:00:00 EDT 2017},
month = {Mon Jun 19 00:00:00 EDT 2017}
}
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