Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Comparison of first criticality prediction and experiment of the Jordan research and training reactor (JRTR)

  • Kim, Kyung-O. (Korea Atomic Energy Research Institute) ;
  • Jun, Byung Jin (Korea Atomic Energy Research Institute) ;
  • Lee, Byungchul (Korea Atomic Energy Research Institute) ;
  • Park, Sang-Jun (Korea Atomic Energy Research Institute) ;
  • Roh, Gyuhong (Korea Atomic Energy Research Institute)
  • Received : 2019.05.10
  • Accepted : 2019.06.27
  • Published : 2020.01.25
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Abstract

Korea Atomic Energy Research Institute (KAERI) has carried out various neutronics experiments in the commissioning stage of the Jordan Research and Training Reactor (JRTR), and this paper introduces the results of first criticality prediction and experiment for the JRTR. The Monte Carlo Code for Advanced Reactor Design and analysis (McCARD) with the ENDF/B-VII.0 nuclear library was used for prediction calculations in the process of the first criticality approach, which was performed to provide reference for the first criticality experiment. In the experiment, fuel loading was carried out by measuring the inverse multiplication factor (1/M) to predict the number of fuel assemblies at the first criticality, and the first critical was reached on April 25, 2016. Comparing the first criticality prediction and experiment, the calculated and measured CAR (Control Absorber Rod) heights for the first criticality were 575 mm and 570.5 mm, respectively, that is, the difference between the two results was approximately 5 mm. From this result, it was confirmed that JRTR manufacturing and various experiments had successfully progressed as designed.

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Cited by

  1. Monte Carlo calculations of neutron spectrum parameters at the JRTR NAA channels vol.134, 2021, https://doi.org/10.1016/j.pnucene.2021.103688