Accident diagnosis of a PWR fuel pin during unprotected loss of flow accident with support vector machine
Creators
- 1. Department of Nuclear Engineering, University of New Mexico, Albuquerque, NM 87131 (United States)
- 2. School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai (China)
- 3. Department of Nuclear Engineering, Seoul National University, Seoul (Korea, Republic of)
Description
Highlights: • Flow rate change simulations for a fuel pin during unprotected LOFA using MARS. • Training SVM with core outlet T for peak cladding T and flow change. • Demonstrating high predictability for peak cladding T and flow change during LOFA. • SVM revealing strong dependency between reactor parameters during unprotected LOFA. • SVM allowing the possibility of interdependent detector systems. - Abstract: In this study, we conducted various flow rate change simulations for a fuel pin during unprotected LOFA using MARS. The obtained transient outlet temperature profiles were used to establish a relationship with peak fuel temperatures and flow rate changes, using Support Vector Machine (SVM). Unless the number of training data is scarce, the SVM trained with the core outlet temperature gives an accurate prediction (R2 > 0.9) for peak cladding surface temperature, and mass flow rate changes in the early phase of LOFA transience (~0.5 s). It illuminates that key accident characteristics are well reflected in the early response of reactor core behavior (i.e., core outlet temperature). This implies that the possibility of (1) realizing an accident diagnosis framework different from today's practice which relies on the accumulated response of reactor behavior over an extended accident progression, and (2) providing an effective guideline for accident mitigation strategies in the early phase of accident progression. The high predictability (i.e., R2 > 0.9) presented in the early phase of unprotected LOFA indicates core outlet temperature is strongly correlated to both flow rate change, and peak cladding surface temperature during the entire transience. With these strong correlations between different physical parameters, the traditional boundaries of physical locations and physical quantities in detecting accident response and progression may be reduced, allowing the possibility of interdependent detector systems.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2019.110184Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2019.110184;
- PII
- S0029549319301931;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 352
- Journal Page Range
- p. 110184
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51056302
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- CLADDING; DIAGNOSIS; FLOW RATE; FUEL PINS; LEARNING; LOSS OF FLOW; MARS PLANET; PEAKS; PWR TYPE REACTORS; REACTIVITY; REACTOR CORES; SUPPORTS; TEMPERATURE MONITORING; TRAINING; TRAINS; VECTORS
- Descriptors DEC
- ACCIDENTS; DEPOSITION; EDUCATION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MECHANICAL STRUCTURES; MONITORING; PLANETS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; TENSORS; THERMAL REACTORS; VEHICLES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © 2019 Elsevier B.V. All rights reserved.