Development of Non-LOCA Safety Analysis Methodology with RETRAN-3D and VIPRE-01/K

2004 ◽  
Vol 148 (1) ◽  
pp. 56-67
Author(s):  
Yo-Han Kim ◽  
Ae-Ju Cheong ◽  
Chang-Keun Yang
Keyword(s):  
Safety Analysis ◽  
Analysis Methodology

scholarly journals SAFETY ANALYSIS METHODOLOGY FOR AGED CANDU® 6 NUCLEAR REACTORS

2013 ◽  
Vol 45 (5) ◽  
pp. 581-588 ◽  
Author(s):  
WOLFGANG HARTMANN ◽  
JONG YEOB JUNG
Keyword(s):  
Nuclear Reactors ◽  
Safety Analysis ◽  
Analysis Methodology

Reliability and Safety Analysis Methodology in the Nuclear Programs of ERDA

1976 ◽  
Vol R-25 (3) ◽  
pp. 140-146 ◽  
Author(s):  
W.H. Hannum ◽  
F.X. Gavigan ◽  
D.E. Emon
Keyword(s):  
Safety Analysis ◽  
Analysis Methodology

Development of the Methodology of the Safety Analysis Performed by the Coupled KIKO3D/ATHLET Code System in VVER-440 Type NPP

2004 ◽  
Author(s):  
Gy. Hegyi ◽  
G. Hordo´sy ◽  
A. Keresztu´ri ◽  
Cs. Mara´czy ◽  
I. Panka ◽  
...  
Keyword(s):  
Safety Analysis ◽  
Emergency Control ◽  
Transient Behaviour ◽  
Analysis Methodology ◽  
Whole Plant ◽  
Wide Range ◽  
Coolant Loop ◽  
Computer Codes ◽  
High Degree ◽  
Physical Phenomena

In the deterministic safety analysis codes are required in order to provide evaluations of potential nuclear plant accidents. In the fields of the core transient behaviour, the computer codes have achieved a high degree of realistic modelling. Nevertheless, some further tools for the investigations of the wide range of physical phenomena in the whole plant transient, such as modeling the ex-core detector signals and the malfunctioning of the emergency control system are unavoidable, too. The programs and methods used in KFKI-AEKI for safety analysis of VVER-440 NPP are presented. The accident analysis methodology for a boron dilution scenario, in which an inactive coolant loop is started, is shown.

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