The Method to Predict First Critical Core Loading for Nuclear Reactors
Author(s) -
Senem Şentürk Lüle
Publication year - 2020
Publication title -
sakarya university journal of science
Language(s) - English
Resource type - Journals
eISSN - 2147-835X
pISSN - 1301-4048
DOI - 10.16984/saufenbilder.677487
Subject(s) - criticality , triga , nuclear engineering , monte carlo method , research reactor , nuclear reactor core , burnup , nuclear data , nuclear power plant , neutron transport , shutdown , computer science , nuclear reactor , environmental science , nuclear physics , neutron , physics , engineering , mathematics , statistics
Nuclear power plants have an important role in carbon free electricity production in the world. One of the important steps of commissioning a nuclear power plant is the first core loading. This is also called approaching the criticality. Since the number of fuel elements for the criticality is not known, precautions must be taken to prevent safety incidents. Although the procedure is performed on-line such that the neutron counts are measured at each loading of fuel elements to calculate sub-critical multiplication and the number of fuel element to reach criticality were predicted, computer simulations can also be used. In this study, inverse sub-critical multiplication method was applied to Istanbul Technical University TRIGA Mark II research reactor first criticality in 1979 by using Monte Carlo simulation code MCNP6.2. Full 3-D model of the reactor was generated for calculations. Both results, experimental and simulation, showed that reactor became critical with 62 fuel elements. The core excess reactivity of 23.1 cents was predicted as 21.7 with the code. The simulation results are in good agreement with experimental results. The methodology and simulations can be used for power reactor analysis as well.
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