Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle

被引:5
作者
Miftasani, Fitria [1 ]
Widiawati, Nina [1 ]
Trianti, Nuri [1 ]
Salsabila, Dhiya Salma [2 ]
Setiadipura, Topan [1 ]
Wulandari, Cici [1 ]
Irwanto, Dwi [3 ]
Permana, Sidik [3 ]
Su'ud, Zaki [3 ]
机构
[1] BRIN, Res Ctr Nucl Reactor Technol PRTRN, Jakarta, Indonesia
[2] Jakarta Muhammadiyah Univ, Jakarta, Indonesia
[3] Bandung Inst Technol, Bandung, Indonesia
关键词
Thermal hydraulic; HTGR; ZrC; SiC; TRISO; Thorium; CORE; IRRADIATION; CODE; HTTR;
D O I
10.1016/j.nucengdes.2023.112463
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The High-Temperature Gas-cooled Reactor (HTGR) uses Tri-structural Isotropic (TRISO) coated fuel, the first barrier to fission products with unique ruggedness. One of the layers of TRISO is a SiC layer, which maintains the fuel's dimensional stability and mechanical integrity and acts as a fission product barrier. At extremely high temperatures, the SiC layer in the TRISO coating system tends to decompose, vaporizing silicon elements and forming a porous carbon structure. The weakness of the SiC layer leads to more expensive and difficult main-tenance processes. ZrC is considered the primary alternative to replace the SiC layer due to its superior stability at high temperatures and more resistance to fission products especially palladium. Previous research has shown that from a neutronic perspective, the performance of ZrC and SiC layers is equally good with insignificant differences. The following research step analyzes the temperature distribution in the hot spot channel of the fuel and the overall core using both types of layers. The temperature analysis is essential to ensure that the maximum fuel temperature during normal operation does not exceed the thermal design target of 1495 degrees C. This research also simulates the temperature of both layers above the fuel design limit of 1600 degrees C. In addition to thermal --hydraulic analysis, calculations were also conducted to determine the coolant pressure drop caused by friction, elevation and form. The calculation showed that the peak temperature value during normal operation for TRISO with SiC and ZrC layer is below the thermal design target value. Both temperatures are not significantly different, with the TRISO (ZrC) temperature being higher during normal operation and the TRISO (SiC) temperature being higher during accident/high-temperature conditions. The pressure drop profile indicates that both coated fuel particles do not exhibit significant differences.
引用
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页数:12
相关论文
共 23 条
  • [11] Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
    Miftasani, Fitria
    Widiawati, Nina
    Trianti, Nuri
    Setiadipura, Topan
    Zuhair, Zuhair
    Irwanto, Dwi
    Permana, Sidik
    Su'ud, Zaki
    [J]. KERNTECHNIK, 2023, 88 (04) : 503 - 517
  • [12] Comparison of neutronic aspects in high-temperature gas-cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power
    Miftasani, Fitria
    Su'ud, Zaki
    Irwanto, Dwi
    Permana, Sidik
    [J]. INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2022, 46 (04) : 4852 - 4868
  • [13] Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors
    Minato, K
    Ogawa, T
    Sawa, K
    Ishikawa, A
    Tomita, T
    Iida, S
    Sekino, H
    [J]. NUCLEAR TECHNOLOGY, 2000, 130 (03) : 272 - 281
  • [14] Morrison B.H., 1970, THERMAL DIFFUSIVITY
  • [15] Permana S., 2022, J PHYS C SER, V2243
  • [16] Research and development for safety and licensing of HTGR cogeneration system
    Sato, Hiroyuki
    Aoki, Takeshi
    Ohashi, Hirofumi
    Yan, Xing L.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2020, 360 (360)
  • [17] Safety criteria and quality control of HTTR fuel
    Sawa, K
    Suzuki, S
    Shiozawa, S
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2001, 208 (03) : 305 - 313
  • [18] Core thermal-hydraulic design
    Takada, E
    Nakagawa, S
    Fujimoto, N
    Tochio, D
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2004, 233 (1-3) : 37 - 43
  • [19] Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor
    Ueta, Shohei
    Aihara, Jun
    Yasuda, Atsushi
    Ishibashi, Hideharu
    Takayama, Tomoo
    Sawa, Kazuhiro
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2008, 376 (02) : 146 - 151
  • [20] In situ ion irradiation of zirconium carbide
    Ulmer, Christopher J.
    Motta, Arthur T.
    Kirk, Mark A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 466 : 606 - 614