Investigation of break orientation effect during cold leg small-break LOCA at ROSA-IV LSTF.

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概要

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• The Large Scale Test Facility (LSTF) of the Rig-of-Safety Assessment No. 4 (ROSA-N) Program is a volumetrically scaled (1/48) pressurized water reactor (PWR) system with an electrically heated core used for integral simulation of small break loss-of-coolant accidents (SBLOCAs) and operational transients. Three 2.5% cold-leg SBLOCA experiments were conducted at LSTF. In the experiments, the break was oriented at the side, bottom and top of the horizontal cold leg, respectively. The loop seal clearing in the bottom break case was later than in the side break case since a larger amount of liquid had to be discharged until the loop seal clearing. The loop seal clearing in the top break case was later than in the side break case because of the smaller discharge flow rate. The core liquid level drop due to boiloff after the loop seal clearing in the bottom break case was earliest among three cases because of the largest mass loss before the loop seal clearing and in the top break case latest because of the latest occurrence of the loop seal clearing. However, the effect on the system transients such as the pressure and core liquid level transients was small since the transient time was quite long. Analyses to the experimental results were performed with the RELAP5/MOD2 code. Shortcomings in the RELAP5 code calculation results were resolved by reducing the interfacial drag in the hot leg and the core. The inclusion of Shrock's model for the side, bottom and top break of a large horizontal pipe was also tested in the analyses. However, consistent results with data were not obtained since the void fraction in the broken cold leg was not calculated properly.

• 一般社団法人 日本原子力学会の論文

著者

• ASAKA Hideaki

  Japan Atomic Energy Research Institute

• KUMAMARU Hiroshige

  Japan Atomic Energy Research Institute

• TASAKA Kanji

  Japan Atomic Energy Research Institute

• KOIZUMI Yasuo

  Japan Atomic Energy Research Institute

• OSAKABE Masahiro

  Japan Atomic Energy Research Institute

• MIMURA Yuichi

  I. S. L. Inc.

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