Abstract
Measurements carried out in an original-size VVER-1000 mock-up (V-1000
facility, Kurchatov Institute, Moscow) were used for the validation of
three-dimensional neutron-kinetic codes, designed for VVER safety
calculations. The significant neutron flux tilt measured in the V-1000
core, which is caused only by radial-reflector asymmetries, was
successfully modeled. A good agreement between calculated and measured
steady-state powers has been achieved, for relative assembly powers and
inner-assembly pin power distributions. Calculated effective
multiplication factors exceed unity in all cases. The time behaviour of
local powers, measured during two transients that were initiated by
control rod moving in a slightly super-critical core, has been well
simulated by the neutron-kinetic codes.
| Original language | English |
|---|---|
| Pages (from-to) | 485-506 |
| Journal | Nuclear Engineering and Design |
| Volume | 235 |
| Issue number | 2-4 |
| DOIs | |
| Publication status | Published - 2005 |
| MoE publication type | A1 Journal article-refereed |
Keywords
- nuclear power plants
- nuclear reactor safety
- nuclear safety
- validation
- code validation
- pressurized water reactors
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