Machine learning predictions of irradiation embrittlement in reactor pressure vessel steels

Author:

Liu Yu-chen,Wu Henry,Mayeshiba Tam,Afflerbach BenjaminORCID,Jacobs RyanORCID,Perry Josh,George Jerit,Cordell Josh,Xia Jinyu,Yuan Hao,Lorenson Aren,Wu Haotian,Parker Matthew,Doshi Fenil,Politowicz AlexanderORCID,Xiao Linda,Morgan DaneORCID,Wells Peter,Almirall Nathan,Yamamoto Takuya,Odette G. Robert

Abstract

AbstractIrradiation increases the yield stress and embrittles light water reactor (LWR) pressure vessel steels. In this study, we demonstrate some of the potential benefits and risks of using machine learning models to predict irradiation hardening extrapolated to low flux, high fluence, extended life conditions. The machine learning training data included the Irradiation Variable for lower flux irradiations up to an intermediate fluence, plus the Belgian Reactor 2 and Advanced Test Reactor 1 for very high flux irradiations, up to very high fluence. Notably, the machine learning model predictions for the high fluence, intermediate flux Advanced Test Reactor 2 irradiations are superior to extrapolations of existing hardening models. The successful extrapolations showed that machine learning models are capable of capturing key intermediate flux effects at high fluence. Similar approaches, applied to expanded databases, could be used to predict hardening in LWRs under life-extension conditions.

Funder

National Science Foundation

U.S. Department of Energy

DOE | NE | Nuclear Energy University Program

Ministry of Science and Technology, Taiwan

Ministry of Education (Ministry of Education, Republic of China

U.S. Nuclear Regulatory Commission

Publisher

Springer Science and Business Media LLC

Subject

Computer Science Applications,Mechanics of Materials,General Materials Science,Modeling and Simulation

Reference28 articles.

1. Administration, U. S. E. I. U.S. Nuclear Industry - Energy Explained, Your Guide To Understanding Energy, http://www.eia.gov/energyexplained/index.cfm?page=nuclear_use (2016).

2. Administration, U. S. E. I. How old are U.S. nuclear power plants, and when was the last one built?, http://www.eia.gov/tools/faqs/faq.cfm?id=228&t=21 (2016).

3. Odette, G. R. et al. On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models. J. Nucl. Mater. 526, 151863 (2019).

4. Nanstad, R. K. & Server, W. L. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges. Report No. ORNL/LTR-2011/351, https://www.energy.gov/ne/articles/reactorpressure-vessel-task-light-water-reactor-sustainability-program-initial (Oak Ridge, TN, 2011).

5. News, W. N. Rosatom launches annealing technology for VVER-1000 units, https://www.world-nuclear-news.org/Articles/Rosatom-launches-annealing-technology-for-VVER-100 (2018).

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