Application of code scaling, applicability and uncertainty methodology to large break LOCA analysis of two loop PWR

Nuclear Engineering and Design

Volumn 143, Issue 1, 1993, Pages 95-109

  Mavko, Borut ^a   Stritar, Andrej ^a   Prošek, Andrej ^a  

^a JO EF STEFAN INSTITUTE   (Slovenia)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0039689538     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/0029-5493(93)90278-H     Document Type: Article

References (31)

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2. Quantifying reactor safety margins, Part 2: Characterization of important contributors to uncertainty
3. Quantifying reactor safety margins, Part 3: Assessment and ranging of parameters
4. Quantifying reactor safety margins, Part 4: Uncertainty evaluation of LB LOCA analysis based on TRAC-PF1/MOD 1
5. Quantifying reactor safety margins, Part 5: Evaluation of scale-up capabilities of best estimate codes
6. Quantifying reactor safety margins, Part 6: A physically based method of estimating PWR large break loss of coolant accident PCT
7. Quantifying reactor safety margins, application of code scaling, applicability and uncertainty evaluation methodology to a large-break loss-of-coolant accident
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14. RELAP5/MOD2 Code Manual
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16. Steam generator model for design accident calculations
17. Break modelling for RELAP5/MOD2 analyses of ISP-Bethsy
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19. Pretest calculation on third IAEA-PMK-NVH standard problem exercise
20. International standard problem 25, Achilles test experiment, Calculations by RELAP4 and RELAP5 codes
21. Analysis of 15P- 25 Achilles experiment by computer codes RELAP4/MOD6 and RELAP5/MOD2; 61. IAEA/TC
22. An overview over IAEA standard problem experiment simulations
23. An improvement in RELAP5/MOD2 heat transfer calculation during reflood
24. RELAP5/MOD2 simulation of ORNL reflood tests
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