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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
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...
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
Paper No: ICONE28-60964
...]. the latest patch version of the integral code ASTEC V2.1.1 Patch 6, developed by IRSN. ASTEC is able to perform FIGURE 2: SCHEMATIC LAYOUT OF THE DEBRIS TEST simulations of the most relevant thermal hydraulic processes SECTION CF.  during an incident with core degradation in LWR. For the simulations...
Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-pueng, Yanin Sukjai, Koroush Shirvan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A075, August 4–6, 2021
Paper No: ICONE28-65609
... (PCHE) holds 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...
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A009, August 4–5, 2020
Paper No: ICONE2020-16164
...EFFECTS OF ROLLING ON CHARACTERISTICS OF SYSTEM UNDER FORCED CIRCULATION AND NATURAL CIRCULATION Rong Cai Science and Technology on Reactor System Design Technology Laboratory, Chengdu, China Nina Yue CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Chengdu, China Hongyu Fang...
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A008, July 29–August 2, 2013
Paper No: ICONE21-15106
... Coupled Neutron Dynamic and Thermal Hydraulic Models of the HTR Simulator Sui Zhe, Sun Jun, Wei Chunlin, Ma Yuanle. Shan Wenzhi Institute of Nuclear and New Energy Technology of Tsinghua University, the key laboratory of advanced reactor engineering and safety, Ministry of Education, Beijing...
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
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...
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
Paper No: ICONE16-48944
...° angles. The theoretical 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...
Gerhard Poss, Teja Kanzleiter, Friedhelm Funke, Gert Langrock, Hans-Josef Allelein, Holger Nowack, Gunter Weber
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 721-726, May 11–15, 2008
Paper No: ICONE16-48692
... PAR (metal iodide interaction) to the iodine source term together with the restricted knowledge from both THAI and RECI tests, means that further investigations are required. severe accident containment thermal hydraulics THAI test facility iodine volatility CsI passive autocatalytic...
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 139-146, April 14–18, 2002
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...
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 745-749, April 25–29, 2004
Paper No: ICONE12-49460
... w −T CHF )/(T MHF −T CHF ). The prediction by the present model was in agreement with the present experimental data for water. Thermal Hydraulics Heat Transfer Transition Boiling Correlation Model Proceedings of ICONE12 12th International Conference on Nuclear Engineering Keywords...
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 643-649, July 17–20, 2006
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...