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- Title
Numerical Modeling and Calculation of the Fuel Cycle for the IRT-Sofia Research Reactor.
- Authors
Dimitrov, D.; Belousov, S.; Krezhov, K.; Mitev, M.
- Abstract
The IRT-Sofia research reactor at the Nuclear Scientific Educational and Experimental Centre of the Institute for Nuclear Research and Nuclear Energy is under reconstruction in order to achieve the contemporary national and international standards for safety and reliability. The reactor is foreseen to operate with low enriched nuclear fuel (less than 20% U-235) according to the project for reconstruction. A model of the IRT reactor core is presented in this paper to determine the level of fuel burn-up using the MCNPX code, which performs neutron-physical calculations by theMonte Carlo method without applying approximations either for description of the core composition and geometry or for the neutron crosssections energy dependence. The reactor core is modeled taking into account the control rods positions and the actual rounded profile of the IRT-4M type fuel assemblies and, with this input data, the nuclear fuel consumption of the IRT-Sofia research reactor is determined.
- Subjects
MATHEMATICAL models; NUCLEAR reactors; FUEL cycle; NUCLEAR fuels; NUCLEAR facilities; MONTE Carlo method
- Publication
Bulgarian Journal of Physics, 2013, Vol 40, Issue 4, p281
- ISSN
1310-0157
- Publication type
Article