COMP-PHLGJul 10, 2020

Deep Surrogate Models for Multi-dimensional Regression of Reactor Power

arXiv:2007.05435v22 citations
AI Analysis

This work addresses the need for rapid response times in autonomous control of small modular reactors, though it is incremental as it applies existing neural network methods to a specific nuclear engineering domain.

The paper tackled the problem of developing fast surrogate models for autonomous reactor control by using neural networks to perform multi-dimensional regression of a nuclear reactor's power distribution, achieving a mean absolute percentage error (MAPE) of less than 1.16% with a standard deviation under 0.77% across test datasets.

There is renewed interest in developing small modular reactors and micro-reactors. Innovation is necessary in both construction and operation methods of these reactors to be financially attractive. For operation, an area of interest is the development of fully autonomous reactor control. Significant efforts are necessary to demonstrate an autonomous control framework for a nuclear system, while adhering to established safety criteria. Our group has proposed and received support for demonstration of an autonomous framework on a subcritical system: the MIT Graphite Exponential Pile. In order to have a fast response (on the order of miliseconds), we must extract specific capabilities of general-purpose system codes to a surrogate model. Thus, we have adopted current state-of-the-art neural network libraries to build surrogate models. This work focuses on establishing the capability of neural networks to provide an accurate and precise multi-dimensional regression of a nuclear reactor's power distribution. We assess using a neural network surrogate against a previously validated model: an MCNP5 model of the MIT reactor. The results indicate that neural networks are an appropriate choice for surrogate models to implement in an autonomous reactor control framework. The MAPE across all test datasets was < 1.16 % with a corresponding standard deviation of < 0.77 %. The error is low, considering that the node-wise fission power can vary from 7 kW to 30 kW across the core.

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