Emulating loss of coolant simulations in a pressurized heavy water reactor

被引:1
作者
Anghel, C., V [1 ]
Deng, D. S. [1 ]
Golesorkhi, S. [1 ]
Shreeves, P. [2 ]
Bingham, D. [2 ]
Trottier, A. [1 ]
机构
[1] Canadian Nucl Labs, Chalk River, ON, Canada
[2] Simon Fraser Univ, Burnaby, BC, Canada
关键词
Software emulator; LBLOCA; Code coupling; PHWR; MODEL;
D O I
10.1016/j.anucene.2022.109311
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
In an ideal risk-informed approach to safety analysis, all possible operational states of the system and all sources of uncertainty would be factored. Brute force approaches are cost-prohibitive if high-fidelity multiphysics simulation systems are used. To address this barrier, we present a first attempt to develop emulators for coupled neutronics/thermalhydraulics simulations of large break loss-of-coolant accidents in a generic pressurized heavy water reactor. The emulators are based on a linear mean function coupled with a locally approximate Gaussian process model.The emulators are capable of predicting the power pulse amplitude and the maximum bundle enthalpy within mean absolute relative errors of 0.75 and 0.36%, and mean relative margins of error of 1.9 and 1.0%, respec-tively. In relation to the simulator, the evaluation time is reduced by a factor of nearly 1800. The paper covers the simulation system, training data generation framework, statistical models and uncertainties, and results.
引用
收藏
页数:13
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