Computational validation of the fission rate distribution experimental benchmark at the JSI TRIGA Mark II research reactor using the Monte Carlo method
Annals of Nuclear Energy(2018)
摘要
•An improved TRIGA research reactor thermal power calibration method with electrical heaters is presented.•The heat capacity of the reactor pool is determined with various methods.•The heat losses from the reactor tank are assessed experimentally and computationally.•The total experimental uncertainty of the calibration method is evaluated.
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关键词
TRIGA reactor,Miniature fission chamber,Absolute fission rate,Monte Carlo calculations,Uncertainty analysis,MCNP
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