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耐衝撃試験後の変形燃料束の圧力損失特性

Pressure loss characteristics of deformed fuel assembly

阿部 定好*; 大坪 章*; 井口 達郎*

Abe, Sadayoshi*; not registered; Iguchi, Tatsuro*

仮想事故時の炉心冷却材流量を評価する際に,ラッパー管が不規則に変形した燃料束の圧力損失特性を知ることが必要である。従来,これに関する知見が乏しいため本試験を実施した。本試験では,「もんじゅ」ブランケット燃料集合体の燃料束部を模擬した供試体を用いた。「ラッパー管耐衝撃性評価試験」でラッパー管等に不規則な変形を与えた供試体3体と,変形のない供試体1体について,圧力損失特性を測定した。本試験で得られた主な結論は次の通りである。燃料束部で定義したイノルズ数Re=10$$times$$3$$sim$$3$$times$$10$$times$$4で,変形による平均流路断面の減少が正常燃料束の17%以下で,正常燃料束に対する変形燃料束の圧力損失$$Delta$$Pは,平均流路断面積Aを用いて,近似的に次式で表わされる。上記の関係を用いて正常燃料束より求めた変形燃料束の圧力損失予測誤差は,Re=l0$$times$$3$$sim$$8$$times$$10$$times$$3で+-8%以下であり,Re=8$$times$$10$$times$$3$$sim$$3.5$$times$$10$$times$$4では+-3%以下であった。

The objective of this experimental study is to obtain the data on pressure loss characteristics of the fuel assembly which must be deformed during hypothetical core disruptive accident (HCDA). Three of deformed bundle and one of normal shaped bundle were used in the experiment. These bundles had the same geometry as the fuel bundle part of "Monju" blanket assembly. The main conclusions are as follows: The pressure loss ($$Delta$$P) of deformed bundle at the same Reynolds numbers as normal bundle can approximately predicted by using the ratio of cross sectional flow area(A), as shown below. ($$Delta$$P(deformed))/($$Delta$$(normal)) = (A(normal)/A(deformed))$$^{2}$$. This equation is applicable with the following limitations. (1)Reynolds numbers defined at bundle area is 10$$^{3}$$ to 3$$times$$10$$^{4}$$. (2)Reduction of flow area is within 17% of flow area of normal bundle. Prediction area of the equation is less than 8% and 3% for the range of Reynolds number of 10$$^{3}$$ to 8$$times$$10$$^{3}$$ and 8$$times$$10$$^{3}$$ to 3$$times$$10$$^{4}$$, respectively.

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