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Keywords: thermal hydraulics
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Proceedings Papers

Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133151
... Technology, Tsinghua University, Beijing 100084, China 2. Institute of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China ABSTRACT The RELAP5 code was employed to study the natural circulation characteristics and core thermal-hydraulic parameters of THFR (Tsinghua...
Topics: Heat
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A051, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93442
... and ranked to ensure the scaling can reproduce them in the test facility as the same as the prototype does. The height ratio is 1:4 and the diameter ratio is 1:6 for the test facility. Totally 177 simulators were used to simulate the thermal hydraulics of the fuel assemblies in the practical reactor core...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92795
... used in compact reactors such as research reactors, integrated reactors, and high-flux reactors. at present, most thermal-hydraulic analysis programs, such as RELAP, RETRAN, THEATRE, are mostly developed for large-scale pressurized water reactors using rod-shaped fuels. It is suitable for narrow...
Proceedings Papers

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91901
... and the prediction of the hot spot of the sodium-cooled fast reactor wire-wrapped fuel bundle. sodium-cooled fast reactor wire-wrapped fuel bundle turbulent Prandtl number thermal hydraulics CFD Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A075, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65609
... promise to fulfil these requirements. The chemical etching and diffusion bonding technology expands PCHE application for several different nuclear technologies. This work presents the thermal-hydraulic and structural analysis of PCHE for molten salt application with thermal energy storage. In this study...
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, V003T08A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61351
... the analytical approach to calculate the pipe deformation effects the overestimation of the pressure peak reduces to 8%. beyond design basis events computational fluid dynamics (CFD) thermal hydraulics nuclear safety and security Proceedings of the 2021 28th International Conference on Nuclear...
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, V003T12A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-60964
... with the experimental results. This is also reflected by the evolution of the quench front and also applies to the conducted COCOMO simulations. The released amount of steam is overestimated by both codes and leaves room for improvement. beyond design basis events thermal hydraulics nuclear safety and security...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A009, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16164
... Abstract The marine nuclear power plant operating in the marine environment has complicated motion under the influence of wind and waves. The movement of marine nuclear power plant will affect the thermal-hydraulic characteristics of its nuclear reactor system. Compared with other typical...
Proceedings Papers

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A008, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15106
... HTR simulator neutron dynamics thermal hydraulics coupling Along with the design and construction of the high temperature reactor pebble bed module (HTR-PM), the engineering simulator system (ESS) has been accomplished to deal with the key techniques of the HTR simulator. In our...
Proceedings Papers

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 865-872, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75454
... 23 02 2010 This study presents a predictive thermal-hydraulic analysis with packed spheres in a nuclear gas-cooled reactor core. The predictive analysis considering the effects of high power density and the some porosity value were applied as a design condition for an Ultra High...
Proceedings Papers

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 721-726, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48692
... interaction) to the iodine source term together with the restricted knowledge from both THAI and RECI tests, means that further investigations are required. 09 07 2009 severe accident containment thermal hydraulics THAI test facility iodine volatility CsI passive autocatalytic recombiner...
Proceedings Papers

Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 515-520, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48944
... models of the thermal hydraulics under steady condition are conducted in one-twelfth of the core and calculated by the numerical method. The DRAGON code is adopted to calculate the axial and radial power factors. The flow and heat transfer models in the fuel salt and graphite are founded basing...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 139-146, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22120
... thermal hydraulics Proceedings of ICONE10 10TH International Conference on Nuclear Engineering Arlington, VA, USA, April 14-18, 2002 AB L E mi tru nd 1 K , F ing theoretical tool. Keywords: severe accidents, thermal hydraulics 1. INTRO To e environme generation melt with requireme the corium reactor...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 745-749, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49460
... Proceedings of ICONE12 12th International Conference on Nuclear Engineering Keywords: Thermal Hydraulics, Heat Transfer, Transition Boiling, Correlation, Model INTRO Th import for ex Emerg Coolan and a magne investi transit throug combin boiling a heati were obtained. Correlations...
Proceedings Papers

Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 643-649, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89620
... 17 09 2008 The THAI experimental programme includes combined-effect investigations on thermal hydraulics, hydrogen, and fission product (iodine and aerosols) behaviour in LWR containments under severe accident conditions. An overview on the experiments performed up to now...