Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Calculations and experimental investigation of the irradiation rig with a fuel heater for the BOR-60 reactor

3/28/2016 2016 - #01 Physics and technology of nuclear reactors

Varivtcev A.V. Zhemkov I.Yu. Boev A.V. Ishunina O.V. Naboyshchikov Yu.V. Poglyad N.S. Sharonova M.G.

DOI: https://doi.org/10.26583/npe.2016.1.13

UDC: 621.039.51

Tests of perspective materials and new generation reactor core elements are conducted in the BOR-60 reactor. An irradiation rig (IR) with a fuel heater is proposed to be used for reactor tests of different structural materials at the high temperatures. This type of IR has a number of advantages in comparison with IR containing thermo-insulated capsules that is often used now. Calculations and experimental investigations of the IR were performed in the core of the BOR-60 reactor. Results of the special methodical experiment confirmed the possibility of providing the necessary temperature conditions for the samples during irradiation. The neutronics were calculated by MCU-RR code and the thermal hydraulic characteristics were calculated using ANSYS CFX complex. Comparison of calculated temperature values with experimental ones showed that they correlate well – the difference between them is less than experimental error. It means that the used computer codes, models and methods are suitable for such calculations. The calculations and experiments were carried out to see the temperature distribution in the IR with a fuel heater irradiated in the BOR-60 and then put into the dry storage channel. Decay heat rate values inside the IR fuel pins calculated by AFPA code, and the temperatures were calculated using ANSYS CFX. The performed calculations and experiments also showed it possible to remove the IR with a fuel heater from the reactor on the second day of outage, the limited cladding temperatures and required samples temperatures being not exceeded.

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reactor irradiation rig samples fuel pin heat rate power temperature thermocouple nuclear fuel enrichment fuel pin coolant