The Best Estimate Plus Uncertainty (BEPU) method is applied to analysis of the “intentional depressurization of steam generator secondary side” which is an accident management procedure in a small break loss-of-coolant accident with high pressure injection system failure. In the present study, experimental analyses using the RELAP5/MOD3.2 code were carried out for the ROSA/Large Scale Test Facility (LSTF) secondary-side depressurization tests. The two test cases were selected with different break sizes and different depressurization conditions to ensure the reliability for the accident scenario analyses. The input parameter uncertainty propagation analyses were performed to get 95%/95% tolerance limit values of the output parameters. It was confirmed that the code predicted well the major event progressions of the accident for both test cases and the 95%/95% uncertainty bounds of the peak cladding temperatures included the measured values. On the other hand, the same ranges of some input uncertainty parameters could lead to different influences on the output uncertainties between the test cases. The dominating input uncertainty parameters could be different depending on the break sizes and depressurization conditions of the accident scenario.
Skip Nav Destination
2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5003-9
PROCEEDINGS PAPER
RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure
Ikuo Kinoshita,
Ikuo Kinoshita
Institute of Nuclear Safety System, Inc. (INSS), Fukui, Japan
Search for other works by this author on:
Toshihide Torige
Toshihide Torige
Institute of Nuclear Safety System, Inc. (INSS), Fukui, Japan
Search for other works by this author on:
Ikuo Kinoshita
Institute of Nuclear Safety System, Inc. (INSS), Fukui, Japan
Toshihide Torige
Institute of Nuclear Safety System, Inc. (INSS), Fukui, Japan
Paper No:
ICONE24-60525, V003T09A035; 10 pages
Published Online:
October 25, 2016
Citation
Kinoshita, I, & Torige, T. "RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 3: Thermal-Hydraulics. Charlotte, North Carolina, USA. June 26–30, 2016. V003T09A035. ASME. https://doi.org/10.1115/ICONE24-60525
Download citation file:
23
Views
Related Proceedings Papers
Related Articles
Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model
ASME J of Nuclear Rad Sci (April,2016)
Turbine Efficiency
Measurement System for the QinetiQ Turbine Test
Facility
J. Turbomach (January,2010)
A Multistage Compressor Test Facility: Uncertainty Analysis and Preliminary Test Results
J. Eng. Gas Turbines Power (January,2005)
Related Chapters
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Application of Probabilistic Methods for the Evaluation of Deterministic Deviations from Technical Specifications (PSAM-0277)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)