Development of Evaluation Model for Wastage Environment under Tube Failure Accident in Steam Generator of Sodium-Cooled Fast Reactor

スポンサーリンク

概要

• 論文の詳細を見る

• In order to establish a safety evaluation method of a steam generator in sodium-cooled fast reactors, a computer program called SERAPHIM to calculate compressible multicomponent multiphase flow with sodium-water chemical reaction under tube failure accident has been developed. In this study, a numerical model for liquid droplet entrainment from an interface of the gaseous jet and its transport was newly constructed to evaluate the environment of the liquid droplet impingement erosion. Applicability of the SERAPHIM program which incorporates the droplet entrainment / transport model was investigated through the analysis of vertical discharging of water vapor in the liquid sodium pool. The numerical analysis reproduced the underexpansion of the vapor jet, which appears under the actual condition of the tube failure accident. The calculated peak temperature agreed with the experimental results well. Also, appearance of the dispersed phase of droplets in the reacting jet and movement with the supersonic gaseous flow were calculated successfully.

著者

• 大島 宏之

  （独）日本原子力研究開発機構

• 内堀 昭寛

  （独）日本原子力研究開発機構

関連論文

• 高速炉蒸気発生器における伝熱管ウェステージに関する高温NaOH衝突実験
• ナトリウム―水反応および圧縮性混相流数値解析コードSERAPHIMの高度化（化学反応を伴う液体中気体噴流に対する再現性検証）
• T字合流部における渦構造と温度変動に関する数値解析
• T字合流部における非定常枝噴流挙動に着目した流体－構造熱連成問題の研究
• ナトリウム－水化学反応場の素反応解析
• The Effect of Flow-Accelerated Corrosion with High-Temperature Sodium Hydroxide on Tube Target-Wastage Caused in Steam Generator of Sodium-Cooled Fast Reactor
• Development of Evaluation Model for Wastage Environment under Tube Failure Accident in Steam Generator of Sodium-Cooled Fast Reactor
• Experimental Study and Kinetic Analysis of Sodium-Water Chemical Reaction Mechanism in Steam Generator of Sodium-Cooled Fast Reactor
• 高速炉蒸気発生器の伝熱管破損時事象に対する解析評価手法の開発
• 高速炉蒸気発生器伝熱管周りに形成されるナトリウム－水反応ジェットの熱伝達特性

スポンサーリンク