| タイトル | Study of thermohydraulic behavior within the fuel bundle under a loss of flow condition |
| その他のタイトル | None |
| DOI | |
| 本文（外部サイト） | http://jolissrch-inter.tokai-sc.jaea.go.jp/pdfdata/PNC-TN9410-92-018.pdf |
| 参考URL | http://jolissrch-inter.tokai-sc.jaea.go.jp/search/servlet/search?4034359 |
| 著者（日） | 早船 浩樹 |
| 著者（英） | M.E.Kab |
| 発行日 | 1992-01 |
| 発行機関など | JAEA |
| 刊行物名 | PNC-TN9410 92-018 |
| 開始ページ | 1 |
| 終了ページ | 58 |
| 刊行年月日 | 1992-01 |
| 言語 | en |
| 内容記述 | This report describes the result of the analysis of unprotected Loss of Flow (LOF) ansient experiment conducted at the PLANt Dynamics Test Loop (PLANDTL) experimentalfility by Super System Code (SSC) and SubAssembly Boiling EvolutioN Analysis (SABENA)ode. This report also describes the effect of the modification we made in SSC with t recent void fraction and two-phase friction multiplier models during the analysis othe experiment. After the analysis, it was found that the two-fluid two-phase flow mel of SABENA 1-D is better than the homogeneous model of SSC in predictiong the therhydraulic behavior within the simulated fuel bundle test section of thePLANDTL facily in case of high quality sodium boiling experiment. Moreover, it wasalso revealed tt the two-fluid one dimensional model is not accurate enough in predicting the onsetf boiling and axial evolution of boiling region inside the heatedchannel.
著者所属: 日本原子力研究開発機構(JAEA) |
| 資料種別 | Technical Report |
| URI | https://repository.exst.jaxa.jp/dspace/handle/a-is/618397 |
