Published October 2020 | Version v1
Miscellaneous Open

HTGR thermohydraulic study on steady-state conditions using ANSYS FLUENT

  • 1. Badan Pengawas Tenaga Nuklir - BAPETEN, Jl. Gadjah Mada No.8 Jakarta Pusat (Indonesia)

Description

HTGR is a reactor type that uses helium gas as its coolant that has a high operating temperature. Many countries are considering building HTGR because it has higher thermal efficiency compared to PWR or BWR. Many studies have been carried out related to HTGR, one of them is related to thermohydraulic performance. Because the thermohydraulic performance is closely related to its safety, therefore this study will be carried out to determine the temperature distribution on the HTGR core, and the graphite reflector temperature will also be compared to experimental data. The HTGR type which is used as a reference in this research is the HTR-10 which has been built in China. The calculation of temperature distribution on HTGR core was carried out using ANSYS FLUENT code applying a porous medium approach and a 2-dimensional model with axisymmetry. The 2-D was applied to simplify the geometrical model as the HTR-10 core was a cylinder, and consequently, it would also speed up the CFD calculation and reach convergence. From the CFD calculations, the results showed that the core outlet helium gas temperature was 795 °C. As for the temperature measurement in the side reflector, the calculation results at the height of 80 cm produced the least difference compared to the experimental results, which is 4 % (at a radius of 193 cm). And the biggest difference was 22 % (at a radius of 93 cm). As for the height of 170 cm, the least difference with the experimental data was 4,3 % (at a radius of 93 cm) and the greatest one was 12,76 % (at 189 cm). (author)

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Part of:
2020 Annual Nuclear Safety Seminar Proceeding: Innovations to Support Nuclear Safety and Security for Advanced Human Resources and Excellent Indonesia

Additional details

Additional titles

Original title (English)
Studi termohidraulik HTGR pada kondisi steady-state menggunakan ANSYS FLUENT

Publishing Information

Publisher
Nuclear Energy Regulatory Agency
Imprint Place
Jakarta (Indonesia)
Imprint Title
2020 Annual Nuclear Safety Seminar Proceeding: Innovations to Support Nuclear Safety and Security for Advanced Human Resources and Excellent Indonesia
Imprint Pagination
226 p.
Journal Page Range
p. 1-12
ISSN
1412-3258
Report number
INIS-ID--103

Conference

Title
Innovations to Support Nuclear Safety and Security for Advanced Human Resources and Excellent Indonesia
Original Conference Title
Seminar Keselamatan Nuklir Tahunan 2020: Inovasi untuk Mendukung Keamanan Nuklir dan Keamanan untuk Manusia Lanjutan Sumber Daya dan Indonesia Unggul
Acronym
2020 Annual Nuclear Safety Seminar
Dates
26 Oct 2020
Place
Jakarta (Indonesia)

Optional Information

Notes
7 refs.; 4 tabs.; 12 figs. Imprint:Prosiding Seminar Keselamatan Nuklir Tahunan 2020: Inovasi untuk Mendukung Keamanan Nuklir dan Keamanan untuk Manusia Lanjutan Sumber Daya dan Indonesia Unggul