ICONE11-36446 ASSESSMENT OF THE RELAP5-3D CODE Against An IIST 0.5% COLD LEG SBLOCA EXPERIMENT WITH PASSIVE SAFETY INJECTION

• Chang Chin Jang

  Nuclear Engineering Division Institute of Nuclear Energy Research

• Young Hua Jiun

  Gengood Engineering Corporation

• Lee Chien Hsiung

  Nuclear Engineering Division Institute of Nuclear Energy Research

• Wang Lance L. C.

  Power Research Institute, Taiwan Power Company

抄録

The code RELAP5-3D is used for the analysis of a 0.5% cold-leg Small-Break Loss-of-Coolant Accident (SBLOCA) experiment PL-12 conducted at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility with the passive core cooling injection. The code predictions include the analysis for primary system pressure, loop flow rate, loop and CMT temperatures, coolant inventory distribution in pressurizer, Accumulator (ACC), and Core Makeup Tank (CMT), mass flow rate in Passive Residual Heat Removal (PRHR) system, and other core thermal-hydraulics. A comparison between the calculated results and the experiment data shows (a) a good match with the prediction of the primary system pressure, CMT-1 upper portion temperature, and loop-3 hot-leg fluid temperature, (b) underprediction of the loop-3 mass flow rate and CMT-1 lower portion temperature, (c) overprediction of the pressurizer liquid level, CMTs liquid level and PRHR system mass flow rate.

収録刊行物

• Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE

  Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2003 (0), 306-, 2003

  一般社団法人 日本機械学会

キーワード

• Small-Break Loss-of-Coolant Accident
• Passive Safety
• Thermal-Hydraulics Code
• Passive Safety Injection

詳細情報

• CRID: 1390001205878376064
• NII論文ID: 110002479037
• DOI: 10.1299/jsmeicone.2003.306
• ISSN: 24242934
• Web Site: https://www.jstage.jst.go.jp/article/jsmeicone/2003/0/2003_306/_pdf
• 本文言語コード: en
• データソース種別:
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