APPLICATION OF THE FUEL ASSEMBLY PIN-BY-PIN THERMAL-HYDRAULIC AND NEUTRON-PHYSICS MODEL DEVELOPED BY CODE KORSAR/GP FOR VVER NPP TRANSIENT SIMULATION

Authors & Affiliations

Sinegribova A.I., Uvakin M.A.
JSC Experimental & Design Organization “GIDROPRESS”, Podol’sk, Russia

Sinegribova A.I. – Engineer-designer of the 2nd category, JSC Experimental & Design Organization “GIDROPRESS”. Contacts: 21, Ordzhonikidze St., Podol’sk, Moscow Region, Russia, 142103. Tel.: +7(4967) 65-26-68; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Uvakin M.A. – Leading Engineer-designer, Cand. Sci. (Phys.-Math.), JSC Experimental & Design Organization “GIDROPRESS”.

Abstract

The pin-by-pin thermal-hydraulic and neutron-physics model of the fuel assembly was developed previously by means of the code KORSAR/GP. The new KORSAR/GP pin-by-pin thermal-hydraulic model was cross-validated with the code TIGR-SP which is used by OKB "GIDROPRESS" for FA steady-state operation assessment.
This paper presents the results of reconstruction of the pin-by-pin power distribution for the FA with use of developed pin-by-pin model. The neutron-physics model was cross-validated with the code SAPFIR_95&RC_VVER which is used for obtaining steady state pin-by-pin power distribution and power distribution of the fuel assemblies in the core.
The investigation of pin radial peaking factor change during transient was performed. This investigation was performed for “Control rod ejection” and “Main steam line break”.

Keywords
pin-by-pin model of FA, KORSAR/GP, pin-by-pin power distribution, pin radial peaking factor, control rod ejection, main steam line break

Article Text (PDF, in Russian)

References

UDC 621.039.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2017, issue 4, 4:12