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Keywords: CHF
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Proceedings Papers
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A056, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91840
... Abstract The accurate prediction of critical heat flux (CHF) is of great significance to the safe operation of the reactor. At present, most of the traditional methods for predicting CHF are based on relational fitting in mathematical form, which are not accurate enough and may can not taking...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A057, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93623
... pressure vessel lower head is in the pool boiling state. In this research a one-dimensional full-height experimental facility was established to research the heat transfer limit (CHF) of ERVC under the pool boiling condition with a one-dimensional heating block, which is used to simulate the lower head...
Proceedings Papers
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89378
... Abstract Safety is the biggest concern of nuclear power plant and research reactors.As one of the three primary thermal design criteria for rectors, the critical heat flux (CHF) guarantee the reactor’s safety and economics. The bubble dynamics in narrow rectangular channel is didderent from...
Topics:
Critical heat flux
Proceedings Papers
Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66591
... boiling (DNB) occurs, the prohibited. Other names may be trademarks of their respective owners. critical heat flux (CHF) must be accurately determined for In this paper, the new methodology is described for local different conditions in order to maintain reasonable margin to resistivity measurement...
Proceedings Papers
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, V003T12A014, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64130
... Abstract In-Vessel Retention (IVR) strategy is one of the most important severe accidents mitigation strategies. The Critical Heat Flux (CHF) is an important key element in the assessment of IVR efficiency. How to increase the CHF is a significant method to make sure the IVR success. Heating...
Proceedings Papers
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A032, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16632
... Abstract Heat transfer between cladding and coolant during transient scenarios remains a critical area of uncertainty in understanding nuclear reactor safety. To advance the understanding of transient and accident scenarios involving critical heat flux (CHF), an in-pile experiment...
Proceedings Papers
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 729-738, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48289
... are calculated. 09 07 2009 Narrow channel Separated flow Numerical simulation CHF Proceedings of the 16th International Conference on Nuclear Engineering ICONE16 May 11-15, 2008, Orlando, Florida, USA coolant channels between the plate fuels are narrow channels. As to the investigation...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 23-32, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22031
... 05 03 2009 An experimental study of the critical heat flux (CHF) and the associated limiting critical quality phenomenon has been conducted recently for horizontal and vertical tubes cooled with water and the refrigerant R-134a. The objective of this study is to compare the CHF...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 147-154, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22128
... 05 03 2009 For the purpose of predicting CHF for a wide range in quality, we developed the analytical CHF prediction method. Two-phase flow analysis code based on multi-fluid model was developed and, by using typical dryout model and DNB model, CHF predictions for a wide range...