Improved multiphysics model of the High Temperature Engineering Test Reactor for the simulation of loss-of-forced-cooling experiments

被引:1
|
作者
Laboure, Vincent [1 ]
Ortensi, Javier [1 ]
Martin, Nicolas [1 ]
Balestra, Paolo [1 ]
Gaston, Derek [1 ]
Miao, Yinbin [2 ]
Strydom, Gerhard [1 ]
机构
[1] Idaho Natl Lab, Nucl Sci & Technol Directorate, POB 1625, Idaho Falls, ID 83415 USA
[2] Argonne Natl Lab, Chem & Fuel Cycle Technol Div, 9700 South Cass Ave, Lemont, IL 60439 USA
关键词
Multiscale heat transfer coupling; Effective thermal conductivity; Reactor physics analysis; High Temperature Engineering Test Reactor; Loss-of-forced cooling;
D O I
10.1016/j.anucene.2023.109838
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
We present a multiphysics model of the High Temperature Engineering Test Reactor for comparison with past and predict future loss-of-forced-cooling (LOFC) experiments. The approach selected combines (1) 3-D full-core superhomogenization-corrected neutronics, (2) 3-D full-core homogenized or semi-heterogeneous heat transfer (macroscale), (3) 2-D axisymmetric fuel rod heat transfer (pin-scale), and (4) 1-D thermal -hydraulics channels. Although large uncertainties remain, the time and magnitude of the first power peak after re-criticality is predicted within 1.5 h and 175 kW, respectively. The novelty of our work includes (1) a new macroscale/pin-scale heat transfer coupling approach relying on gap conductance to drastically speed up numerical convergence by two orders of magnitude, (2) determination of a radial effective thermal conductivity, reproducing the semi-heterogeneous re-criticality time within one hour using a homogenized macroscale model, and (3) a preliminary study of the reactor's early behavior following a LOFC event, enabling further assessment of numerical models against fission power measurements.
引用
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页数:20
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