電力中央研究所 報告書(電力中央研究所報告)
報告書データベース 詳細情報
報告書番号
ET88001
タイトル(和文)
DEVELOPMENT OF THE TWO-DIMENSIONAL THERMAL HYDRAULIC ANALYSIS COMPUTER CODE BY FINITE ELEMENT METHOD
タイトル(英文)
DEVELOPMENT OF THE TWO-DIMENSIONAL THERMAL HYDRAULIC ANALYSIS COMPUTER CODE BY FINITE ELEMENT METHOD
概要 (図表や脚注は「報告書全文」に掲載しております)
*
概要 (英文)
THERMAL HYDRAULIC ANALYSIS IS ONE OF THE IMPORTANT PROCEDURES TO ASSESS COMPONENTS DESIGN AND SAFETY IN NUCLEAR ENGINEERING. THE DETAILS OF THE TWO-DIMENSIONAL THERMAL HYDRAULIC ANALYIS COMPUTER CODE NEWLY DEVELOPED WITH THE AIM OF APPLICATION ESPECIALLY TOLMFBR COMPONENTS ARE DESCRIBED IN THIS REPORT. THE FEATURES OF THIS CODE ARE: (1)STREAMLINE-UPWIND/PETROV-GALERKIN FINITE ELEMENT METHOD IS USED FOR ANALYZING A REGION WITH COMPLICATED CONFIGRATION AND FOR DEALING WITH HIGH-REYNOLDS(PECLET)NUMBER FLOW. (2)A PROBLEM OF SPURIOUSLY OSCILLATING PRESSURE FIELD,WHICH HAS BEEN TROUBLESOME IN FINITE ELEMENT FLOW ANALYSIS WITH NON-STAGGERED MESH,IS REMOVED BY INTRODUCING NEW NUMERICAL SCHEMES IN THE MOMENTUM CONSERVATION EQUATION AND THE PRESSURE EQUATION. (3)A NEW AND REASONABLE AVERAGING OF SPATIALLY NONUNIFORM DIFFUSIVITIES ARE IMPLEMENTED. (4)FREE IN-FLOW/OUT-FLOW BOUNDARY CONDITIONS AND QUASI THREE-DIMENSIONAL ANALYSIS CAN BE DEALT WITH. SOME NUMERICAL RESULTS ARE SHOWN TO PRESENT THE ABILITY OF THIS COMPUTER CODE.
報告書年度
1988
発行年月
1988/08/01
報告者
担当 | 氏名 | 所属 |
---|---|---|
主 |
荒関 英夫 |
狛江研究所発電プラント部機械研究室 |
共 |
魚谷 正樹 |
狛江研究所発電プラント部機械研究室 |
キーワード
和文 | 英文 |
---|---|
* | FINITE ELEMENT METHOD |
THERMAL HYDRAULIC ANALYSIS | |
FAST BREEDER REACTOR |