ICONE11-36446 ASSESSMENT OF THE RELAP5-3D CODE Against An IIST 0.5% COLD LEG SBLOCA EXPERIMENT WITH PASSIVE SAFETY INJECTION
スポンサーリンク
概要
- 論文の詳細を見る
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.
- 一般社団法人日本機械学会の論文
著者
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Chang Chin
Nuclear Engineering Division Institute Of Nuclear Energy Research
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Young Hua
Gengood Engineering Corporation
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Lee Chien
Nuclear Engineering Division Institute of Nuclear Energy Research
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Wang Lance
Power Research Institute, Taiwan Power Company
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Wang Lance
Power Research Institute Taiwan Power Company