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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A068, August 8–12, 2022
Paper No: ICONE29-92887
... analysis of the U 3 Si 2 with accident tolerant cladding (FeCrAl, SiC) in mPower using SEPRENT and DAKOTA. Sensitivity analysis performed the relative importance of each input parameters for different ATF combination. Uncertainty analysis gave the tolerance range and uncertainty for different ATF...
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022
Paper No: ICONE29-89017
... Abstract The uncertainty analysis and sensitivity analysis are two important parts in the safety analysis of nuclear reactor accidents, and the main purpose of the sensitivity analysis is to quantify the importance of the input on the target output. In typical sensitivity analysis...
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A006, August 8–12, 2022
Paper No: ICONE29-90732
... of coupling MAAP5 software with FSS are described. Then taking the MSLB+SBO as the initial hypothetical condition to simulate the whole process of the severe accident emergency drill scenario in 3rd-generation NPP and make a preliminary sensitivity analysis on the mitigation effect of the mitigation measure...
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A009, August 8–12, 2022
Paper No: ICONE29-91730
... Abstract The complicated severe accident phenomena in typical Pressurized Water Reactor (PWR) Generation III may have a strong influence on source term release into environment and radiological consequence. The study on sensitivity analysis is beneficial to the identification of important...
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A034, August 8–12, 2022
Paper No: ICONE29-92164
... contributes to uncertainty quantification in condensation phenomena for PCCS. The purpose is to create a surrogate model instead of a deterministic model for sensitivity analysis on the account of saving computational time. The case used is an experiment carried out in 1998 for which the data is publicly...
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A027, August 8–12, 2022
Paper No: ICONE29-90347
... Abstract In order to study the loss-of-flow accident for the small integrated pressurized water reactor, the transient thermal-hydraulic model of this nuclear power plant was established using the RELAP5/MOD3.2 program. The uncertainty and sensitivity analysis of complete loss of coolant flow...
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A006, August 4–6, 2021
Paper No: ICONE28-64430
... power and core temperature. A local sensitivity analysis was utilized to analyze the power related parameters. And a wide variety of values were selected for each parameter as the assuming initial conditions of the analysis. Multiple thermal-hydraulic simulation runs through a modified RELAP5 code were...
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A022, August 4–6, 2021
Paper No: ICONE28-64415
... nonlinear dynamic analysis software ANSYS/LS-DYNA to conduct a series of parameter sensitivity analysis on the impact of blast resistance of the steel concrete structure wall based on the CONWEP method. These parameters include: the explosive scaled distance, thickness of the steel plate, thickness...
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A006, August 4–6, 2021
Paper No: ICONE28-64749
... 300kg∼520kg, indicating that there is no cliff effect in PISAA. In the future, the researchers plan to do some works to improve the accuracy and functions of PISAA. severe accident verification calculation sensitivity analysis Proceedings of the 2021 28th International Conference on Nuclear...
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A048, August 4–6, 2021
Paper No: ICONE28-64490
... can be somewhat difficult because of its danger, inconvenience, and high cost, it is quite essential to conduct a sensitivity analysis through the program for the purpose of facilitating the design of an SFR. Since most sodium-cooled fast reactor designs are multimodules, a parallel channel structure...
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A002, August 4–5, 2020
Paper No: ICONE2020-16485
... Abstract The sensitivity analysis of the dynamical response of reactor coolant system to the input parameters is an important precondition for the design optimization. In this paper, the sensitivity of the dynamical loads at the nozzles of the equipment under seismic conditions is analyzed...
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 393-399, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54613
...), sensitivity analysis, two-layer configuration, three-layer configuration As is known to all that, pressure vessel is the second barrier for nuclide leakage and it is very important for nuclear safety and will influence the safety of public. It is necessary to study in-vessel retention (IVR) when severe...
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 617-624, May 17–21, 2010
Paper No: ICONE18-29930
... Investigations on Optimal Design of a U-tube Steam Generator QIN Hui-min,YAN Chang-qi, WANG Meng,HE Shi-jing College of Nuclear science and technology, Harbin Engineering University, 150001, China Key words Steam Generator, Optimal Design; Sensitivity Analysis Abstract Steam generator is one...
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 205-212, July 12–16, 2009
Paper No: ICONE17-75661
... Temperature (PCT) with CATHARE-2 V2.5 code during a Large Break (LB) LOCA event for ZION, a 4-loop PWR of Westinghouse design. As a general rule the Global Sensitivity Analysis (GSA) is done with linear correlation coefficients. This paper presents a new approach to perform a more accurate GSA to determine...