Design basis accident analysis for the Ignitor experiment

2015 ◽  
Vol 98-99 ◽  
pp. 2235-2238 ◽  
Author(s):  
Massimo Zucchetti ◽  
Bruno Coppi ◽  
Maria Teresa Porfiri ◽  
Marco Riva
Keyword(s):  
Accident Analysis ◽  
Design Basis ◽  
Design Basis Accident

scholarly journals Thermal-Hydraulic Safety Analysis of Mixed Core Loads for Ukrainian NPPs with VVER-1000

2016 ◽  
pp. 9-12
Author(s):  
Yu. Vorobyov ◽  
A. Nosovsky ◽  
O. Pohonets ◽  
I. Shevchenko
Keyword(s):  
Nuclear Fuel ◽  
Computer Code ◽  
Safety Analysis ◽  
Accident Analysis ◽  
Fuel Cladding ◽  
Hydraulic Analysis ◽  
Design Basis ◽  
Hydraulic Safety ◽  
Design Basis Accident ◽  
Thermal Hydraulic Analysis

The paper presents thermal-hydraulic analysis of mixed core loads to confirm compliance with safety criteria. The objective is to verify reliability of nuclear fuel cooling in representative events of the design-basis accident analysis. RELAP5/MOD3.2 computer code was applied to show that maximum fuel cladding temperature does not exceed 1200 °C in mixed TVSA-12, TVS-WR and TVSA cores. The analysis led to the conclusion on possible safe implementation of new fuel at Ukrainian NPPs.

scholarly journals Application of RELAP5/MOD3.2 Cladding Deformation Model for VVER-1000 Fuel in Design-Basis Accident Analysis

2016 ◽  
pp. 19-22
Author(s):  
Yu. Vorobyov ◽  
O. Zhabin ◽  
M. Frankova
Keyword(s):  
Experimental Data ◽  
Limited Range ◽  
Simplified Model ◽  
Model Parameters ◽  
Accident Analysis ◽  
Deformation Model ◽  
The Core ◽  
Design Basis ◽  
Channel Blockage ◽  
Design Basis Accident

The paper presents applicability of built-in RELAP5/MOD3.2 cladding deformation model for VVER-1000 fuel with cladding of Zr+1 % Nb alloy. Experimental data and simplified model of fuel assembly channel of the core are used for this purpose. The model applicability is tested for the hot channel blockage after cladding swelling and rupture in the interval of temperatures from 600 to 1200°С and interval of pressures from 1 to 12 MPa. It is demonstrated that RELAP5/MOD3.2 builtin model of cladding deformation can be applied to VVER-1000 cladding of Zr+1%Nb alloy rupture estimation only in the certain limited range of parameters. The analysis of RELAP5/MOD3.2 cladding deformation model parameters influence on the peak cladding temperature in double-ended cold leg break was performed. The paper presents recommendations on the use of RELAP5/MOD3.2 built-in cladding deformation model in the design basis accident analysis of VVER-1000 reactors.

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