Analyzing the Loss of Coolant Accident in PWR Nuclear Reactors with Elevation Change in Cold Leg by RELAP5/MOD3.2 System Code

Kheshtpaz, H; Alison, C

Analyzing the Loss of Coolant Accident in PWR Nuclear Reactors with Elevation Change in Cold Leg by RELAP5/MOD3.2 System Code

Document Type : Research Paper

Authors

H Kheshtpaz

C Alison

Abstract

As, the Russian designed VVER-1000 reactor of the Bushehr Nuclear Power Plant (BNPP) by taking into account the change from German technology to that of Russian technology, and with the design of elevation change in the cold legs has been developed; therefore safety assessment of these systems for loss of coolant accident (LOCA) in elevation change in the cold legs and comparison results for non change elevation in the cold legs for a typical reactor (normal design of nuclear reactors) is the main important factor to be considered for the safe operation. In this article, the main objective is the simulation of the loss of coolant accident scenario by the RELAP5/MOD3.2 code in two different cases; first, the elevation change in the cold legs, and the second, non change in it. After comparing and analyzing these two code calculations the results have been generalized for a new design feature of Bushehr reactor. The design and simulation of the elevation change in the cold legs process with RELAP5/MOD3.2 code for PWR reactor is performed for the first time in the country, where it is introducing several important results in this respect.

Highlights

AEP “Preliminary safety analysis report,” PSAR, Chapter 5, Rev 1, (2000).
C.D. Fletcher, “Loss of offsite power scenarios for the Westinghouse Zion-1 Pressurizes Water reactor,” EGG-CAAP-5156, (1980).
C.D. Fletcher and M.A. Bolander, “Analysis of instrument tube ruptures in Westinghouse 4-loop PWRs,” UREG/CR-4672, EGG-2461, (1986).
C.D Fletcher and R.R. Schults, “RELAP5/MOD3.3 Code Manual,” NUREG/CR-5535, Volume III, (2001).

Keywords

RELAP5/MOD3.2 Code

Bushehr VVER-1000 Reactor

Loss of Coolant Accident (LOCA)

Model Nodalization in RELAP5 Code

Computerized Simulation

Reactor Safety

AEP “Preliminary safety analysis report,” PSAR, Chapter 5, Rev 1, (2000).
C.D. Fletcher, “Loss of offsite power scenarios for the Westinghouse Zion-1 Pressurizes Water reactor,” EGG-CAAP-5156, (1980).
C.D. Fletcher and M.A. Bolander, “Analysis of instrument tube ruptures in Westinghouse 4-loop PWRs,” UREG/CR-4672, EGG-2461, (1986).
C.D Fletcher and R.R. Schults, “RELAP5/MOD3.3 Code Manual,” NUREG/CR-5535, Volume III, (2001).