Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis

Kerntechnik ◽  
2017 ◽  
Vol 82 (5) ◽  
pp. 517-526
Author(s):  
I. Panka ◽  
Gy. Hegyi ◽  
Cs. Maráczy ◽  
E. Temesvári
Keyword(s):  
Safety Analysis ◽  
Code System ◽  
Statistical Version

Comprehensive Safety Analysis Code System for Nuclear Fusion Reactors IV: Preliminary Estimation of Dust Production Due to Plasma Disruptions

1996 ◽  
Vol 30 (1) ◽  
pp. 95-103 ◽  
Author(s):  
Takuro Honda ◽  
Takashi Okazaki ◽  
Yasushi Seki ◽  
Isao Aoki ◽  
Tomoaki Kunugi
Keyword(s):  
Nuclear Fusion ◽  
Safety Analysis ◽  
Fusion Reactors ◽  
Code System ◽  
Dust Production ◽  
Preliminary Estimation

scholarly journals The SAS4A/SASSYS-1 Safety Analysis Code System, Version 5

2017 ◽  
Author(s):  
T. H. Fanning ◽  
A. J. Brunett ◽  
T. Sumner
Keyword(s):  
Safety Analysis ◽  
Code System

Application of the integrated safety analysis code system (ISAS) for ITER

2001 ◽  
Vol 58-59 ◽  
pp. 1047-1051 ◽  
Author(s):  
E. Kajlert ◽  
T. Boubee de Gramont ◽  
W. Gulden ◽  
M.-T. Porfiri
Keyword(s):  
Safety Analysis ◽  
Code System

Development of New MHI LOCA Analysis Code: MCOBRA/RELAP5-GOTHIC

2016 ◽  
Author(s):  
Masaaki Katayama ◽  
Tetsuya Teramae ◽  
Masatsugu Mizokami ◽  
Shinya Kosaka
Keyword(s):  
Heat Transfer ◽  
Current Flow ◽  
Safety Analysis ◽  
Code System ◽  
Steam Generators ◽  
Code Model ◽  
Integral Effect ◽  
Counter Current ◽  
Relap5 Code ◽  
Containment Integrity

Mitsubishi Heavy Industries, Ltd. (MHI) has developed the safety analysis code system, MCOBRA/RELAP5-GOTHIC, for large break LOCA, small break LOCA and containment integrity analyses of PWR. The code system contains three codes, MCOBRA code, M-RELAP5 code and GOTHIC code. MHI implemented some models and correlations to MCOBRA and M-RELAP5 code to improve prediction of important phenomena of LOCA event. MHI conducted a lot of analyses for separate effect tests and integral effect tests to confirm the applicability of the MHI’s safety analysis code to LOCA key phenomena, like core heat transfer, DNB, entrainment, break flow, counter-current flow limitation (CCFL), core froth level, and so on. The code model uncertainties are quantified to calculate core heat transfer break flow rate, loop seal phenomena; heat transfer in steam generators, and so on. The results show that the code system can predict the key phenomena well and can calculate LOCA event scenario. Consequently, it is confirmed that the new code system is applicable to the LOCA licensing analysis.

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