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 BME NTI > Research

Scientific research

Reactorphysics: Analysis of equipment with fissionable materials (training and research reactors, power reactors, containers, storage facilities) from the point of view of neutron physics, analysis relating the management, operation of the mentioned equipment, elaboration of means for the analysis (e.g. models for safety analysis), validation and verification of the involved computations.

Thermohydraulics

Training reactor: The pool-type nuclear reactor of the university is in operation since 1971. The core is built of EK-10 fuel assemblies with 10% enrichment. The maximum thermal power is 100 kW, the maximum thermal neutron flux is 2.7e12 n/cm2s. The main purpose of the facility is to support education in nuclear engineering and physics; however, extensive research work is carried out as well. Neutron and gamma irradiation can be performed using 20 vertical irradiation channels, 5 horizontal beam tubes, two pneumatic rabbit systems and a large irradiation tunnel. The facility has physical and radiochemical laboratories and a hot cell too.

Neutronmetrology

Radiochemistry

Radioation protection

Monte-Carlo methods: The Monte Carlo methods are primarily applied at the Institute for the solution of R+D tasks in the field of reactor physics, reactor technology, nuclear safeguards, radiation shielding and nuclear medicine. The most important areas at present are: reactor pressure vessel dosimetry, activation and decay of reactor components and shielding structures, and development/design of radiation shielding equipment and devices. We also use the Monte Carlo techniques for the research of transmutation and Generation IV reactors.

Fusion research

Nuclear diagnostic

Tomographic methods: Within the framework of an IAEA project a feasibility study (including modell simulation and experiments with spent fuel assemblies) demonstrated the use of the technique for imaging high energy gammas in any section of  spent fuel assemblies by nondestructive means. The recent project is aimed at constructing and testing a prototype which can be used in PWR and BWR power plants by IAEA inspectors.

Nuclear fuel cycles The INT is involved in the theoretical analysis of the nuclear fuel cycle. Most of the research is aimed at the efficient and economical use of the nuclear fuel resources, furthermore at nuclear safety. The analysis of complex nuclear fuel cycles substantiates long-term decisions of national significance. The other area of fuel cycle research is related to the transmutation of radioactive waste.