Benchmark Calculations of a Radiation Heat Transfer for a CANDU Fuel Channel Analysis using the CFD Code
スポンサーリンク
概要
- 論文の詳細を見る
To justify the use of a commercial Computational Fluid Dynamics (CFD) code for a CANDU fuel channel analysis, especially for the radiation heat transfer dominant conditions, the CFX-10 code is tested against three benchmark problems which were used for the validation of a radiation heat transfer in the CANDU analysis code, a CATHENA. These three benchmark problems are representative of the CANDU fuel channel configurations from a simple geometry to a whole fuel channel geometry. For the solutions of the benchmark problems, the temperature or the net radiation heat flux boundary conditions are prescribed for each radiating surface to determine the radiation heat transfer rate or the surface temperature, respectively by using the network method.The Discrete Transfer Model (DTM) is used for the CFX-10 radiation model and its calculation results are compared with the solutions of the benchmark problems. The CFX-10 results for the three benchmark problems are in close agreement with these solutions, so it is concluded that the CFX-10 with a DTM radiation model can be applied to the CANDU fuel channel analysis where a surface radiation heat transfer is a dominant mode of the heat transfer.
- 社団法人 日本原子力学会の論文
著者
-
Park Joo
Korea Kumho Petrochemical Co. Ltd. Chungnam Kor
-
KIM Hyoung
Korea Research Institute of Chemical Technology
-
Park Joo
Korea Atomic Energy Research Institute
-
RHEE Bo
Korea Atomic Energy Research Institute
-
Kim Hyoung
Korea Atomic Energy Research Institute
関連論文
- (R)-[1-(1-Naphthyl)ethyl] Isothiocyanate and (S)-1-Phenylethyl Isothiocyanate.New Chirality Recognizing Reagents for the Determination of Enantiomeric Purity of Chiral Amines by NMR
- Application of a Zircaloy/Steam Oxidation Model to a CFD Code and its Validation against a CANDU Fuel Channel Experiment : CS28-2
- Moderator Analysis of Wolsong Units 2/3/4 for the 35% Reactor Inlet Header Break with a Loss of Emergency Core Cooling Injection
- Benchmark Calculations of a Radiation Heat Transfer for a CANDU Fuel Channel Analysis using the CFD Code
- I16 VIDEO-ASSISTED THORACOSCOPIC SURGERY : KOREA UNIVERSITY EXPERIENCE(International Invertigator Awards)
- A301 EFFECT OF TRANSVERSE CONVEX CURVATURE ON THE ONSET OF NUCLEATE BOILING IN CONCENTRIC ANNULI : EXPERIMENTS(Subcooled boiling)
- Ontogenetic and diel changes in diets of two sympatric mudskippers Periophthalmus modestus and Periophthalmus magnuspinnatus on the tidal flats of Suncheon Bay, Korea