<p>This article carries out a neutron-hydraulic coupling research of Xi’an Pulsed Reactor(XAPR). The coupling is based on Monte Carlo neutron transport code RMC and sub-channel thermal-hydraulic code COBRA-TF(CTF) because of the high accuracy of Monte Carlo method and the high efficiency of sub-channel method. The interface code of RMC and CTF used for XAPR coupling is developed by python. The simulation is first made under 1MW, 1.5MW and 2MW steady state and the temperature and power distribution is obtained. The result is compared with the experimental data. Temperature of the fuel rod has a difference in the range of 0.6℃ to 29℃ with the experimental values. Then we make burnup simulation of XAPR running for 3600 days continuously under the power of 2MW and obtain the neutron and thermal-hydraulic parameter after burnup. Two methods are applied in the burnup simulation. One is making neutron-hydraulic coupling using both RMC and CTF in each burn step and the other is only coupling in the first and last burn step while calculation in other steps is only carried out by RMC. The result show great difference between the two methods. Though currently there are no experimental data for this model to make comparison, the result obtained using the latter method is obviously unreasonable, implying the necessity of making neutron-hydraulic coupling in each burn step.</p>

Neutronic/thermal-Hydraulic Coupling Analysis of Xi’an Pulsed Reactor Based on Rmc and Cobra-Tf

Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE28/volume/85246

2021 28th International Conference on Nuclear Engineering (ICONE28)

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