The Recommended Publication for Citing
- Bamidele Ebiwonjumi, Sooyoung Choi, Matthieu Lemaire, Deokjung Lee*, “Verification and Validation of Radiation Source Term Capabilities in STREAM,” Ann. Nucl. Energy, 124: 80-87,. https://doi.org/10.1016/j.anucene.2018.09.034 (2019)
- Bamidele Ebiwonjumi, Chidong Kong, Peng Zhang, Alexey Cherezov, Deokjung Lee*, “Uncertainty Quantification of PWR Spent Fuel due to Nuclear Data and Modelling Parameters”, Nucl. Eng. Tech,. https://doi.org/10.1016/j.net.2020.07.012 (2020)
Introduction
A radiation source term capability has been implemented in STREAM to perform SNF characterization, cask dose rate analysis, for waste management, radiological safety and burnup credit applications.
Features
- Pin wise/assembly wise SNF isotopic inventory
- Radioactivity
- Decay heat
- Gamma source intensity & spectra
- Neutron source intensity & spectra
UNIST-SNF Calculation Procedure
![크기변환_1](http://faculty.unist.ac.kr/reactorcore/wp-content/uploads/sites/229/2017/09/크기변환_11.png)
STREAM-SNF Decay Heat Validation
![](http://faculty.unist.ac.kr/reactorcore/wp-content/uploads/sites/229/2017/09/SNF-11.png)
Source Term Uncertainty Quantification
![](http://faculty.unist.ac.kr/reactorcore/wp-content/uploads/sites/229/2017/09/SNF-2.jpg)
Source Term Uncertainty vs Cooling Time
![](http://faculty.unist.ac.kr/reactorcore/wp-content/uploads/sites/229/2017/09/SNF-3.jpg)
Application of AI into Decay Heat Calculation
![](http://faculty.unist.ac.kr/reactorcore/wp-content/uploads/sites/229/2017/09/SNF-4.jpg)
![](http://faculty.unist.ac.kr/reactorcore/wp-content/uploads/sites/229/2017/09/SNF-5.jpg)