Monte Carlo Calculations of Neutron Fields in VVER-440 Reactor Pressure Vessel

Matúš Stacho, Slovak University of Technology, Slovakia

19th Symposium of AER on VVER Reactor Physics and Reactor Safety (2009, Varna, Bulgaria)
Core Surveillance and Monitoring


One of the limiting factors in term of nuclear power plant lifetime is reactor pressure vessel condition. The most important ageing effect on the reactor pressure vessel is embrittlement. Radiation embrittlement cause especially fast neutrons. In this work we are focused on describing neutron field in reactor pressure vessel area of reactor VVER-440/V-213 using simulation code MCNP 5. Calculation of the neutron field was realized by detailed full-core model of this reactor. The fuel composition is corresponding to the 23th fuel camping of 3th unit in Bohunice nuclear power plant and 7th fuel camping in Mochovce nuclear power plant. Computer simulation of selected neutron-physical parameters will be verified for a consideration of the data from ionization chamber, received from mode department of nuclear power plant in Bohunice and Mochovce. The goal of this work is to improve the assessment of reactor VVER-440/V-213 pressure vessel radiation degradation and following valuation possibility of its lifetime extension and comparison of neutron flux and neutron spectra in most loaded place of reactor pressure vessel and surveillance specimen area.

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