Original scientific paper
Analysis of Manual Reactor Trip of NEK NPP in APROS Computer Code
Tadeja Polach
; ZEL-EN d.o.o., Vrbina 18, 8270 Krško, Slovenia
Dejan Slovenc
; ZEL-EN d.o.o., Vrbina 18, 8270 Krško, Slovenia
Jure Jazbinšek
; ZEL-EN d.o.o., Vrbina 18, 8270 Krško, Slovenia
Ivica Bašić
; APoSS d.o.o, Repovec 23b, 49210 Zabok, Croatia
Luka Štrubelj
; GEN energija d.o.o, Vrbina 17, 8270 Krško, Slovenia
Abstract
The Slovenian Krško Nuclear Power Plant (NEK) model was built in using APROS -
Advanced PROcess Simulation environment. The basis for the this model was the
RELAP5/MOD3.3 Engineering Handbook, the model was updated to the 26th cycle and also
includes the upflow conversion modification.
A detailed model nodalisation was created for each system and every system was separately
validated. The current model covers the primary circuit with the core kinetics model, the secondary
circuit and their control systems. The steady state of the APROS NEK model already having been
validated, the plan now is to validate the model for some transients and design basis accidents. In
this article the plant behaviour after the manual reactor trip is analysed in detail. Two scenarios of
the manual reactor trip transient are performed, where either the Main Steam Isolation Valve
(MSIV) closes after 60s – case A, or remains open – case B.
After the manual reactor trip from the 100% power, the control system signal actuations and
their times were followed and then the responses of different affected systems were being observed.
All those recorded values were then compared with the identical transient performed on the similar
NEK model with the RELAP5/MOD3.3 system code. This procedure allowed to bring the current
APROS NEK model one step forward towards being assured to have accurate calculations.
Keywords
APROS 6; NEK; reactor trip; point kinetics; steam dump; PORV
Hrčak ID:
199645
URI
Publication date:
1.9.2017.
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