2010Unpublished venueRequires access

Preliminary Safety Analysis for Total Loss of Feedwater of the Multi-application Integrated Pressurized Water Reactor

Liguo Jiang, Minjun Peng, Jiange Liu

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Abstract

The purpose of this study is to perform loss of normal feedwater reference calculations for Multi-application Integrated Light Pressurized Reactor (IPWR) using the best-estimate code SCADP/RELAPSIM/MOD3.4. In addition, the thermalhydraulic responses of the reactor coolant system (RCS) and passive residual heat removal system (PRHRS) are studied in detail. Total loss of feedwater can cause the greatly decrease of the heat transfer capacity from the steam generator secondary, which will result in the increase of primary coolant temperature and pressure. The results of the study show that the safety system of the IPWR functions properly and thus secures the reactor to a safe condition. The most important function that should effectively take action in a short period of the accident occurrence is proper opening of the pressurizer safety relief valve and the PRHRS.

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What this paper is about

The purpose of this study is to perform loss of normal feedwater reference calculations for Multi-application Integrated Light Pressurized Reactor (IPWR) using the best-estimate code SCADP/RELAPSIM/MOD3.4. In addition, the thermalhydraulic responses of the reactor coolant system (RCS) and passive residual heat removal system (PRHRS) are studied in detail. Total loss of feedwater can cause the greatly decrease of the heat transfer capacity from the steam generator secondary, which will result in the increase of primary coolant temperature and pressure. The results of the study show that the safety system of the IPWR functions properly and thus secures the reactor to a safe condition. The most important function that should effectively take action in a short period of the accident occurrence is proper opening of the pressurizer safety relief valve and the PRHRS.

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Available abstract

The purpose of this study is to perform loss of normal feedwater reference calculations for Multi-application Integrated Light Pressurized Reactor (IPWR) using the best-estimate code SCADP/RELAPSIM/MOD3.4. In addition, the thermalhydraulic responses of the reactor coolant system (RCS) and passive residual heat removal system (PRHRS) are studied in detail. Total loss of feedwater can cause the greatly decrease of the heat transfer capacity from the steam generator secondary, which will result in the increase of primary coolant temperature and pressure. The results of the study show that the safety system of the IPWR functions properly and thus secures the reactor to a safe condition. The most important function that should effectively take action in a short period of the accident occurrence is proper opening of the pressurizer safety relief valve and the PRHRS.

Key concepts: Boiler feedwater, Pressurizer, Nuclear engineering, Safety valve, Coolant, Feedwater heater, Pressurized water reactor, Boiler (water heating)

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