Analysis of Passive Residual Heat Removal System at Primary Side when Station Blackout Occurs

2014 ◽  
Vol 986-987 ◽  
pp. 231-234
Author(s):  
Jun Teng Liu ◽  
Qi Cai ◽  
Xia Xin Cao
Keyword(s):  
Nuclear Reactor ◽  
Natural Circulation ◽  
Reactor Core ◽  
Saturation Temperature ◽  
Heat Removal ◽  
Primary Circuit ◽  
Station Blackout ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

This paper regarded CNP1000 power plant system as the research object, which is the second-generation half Nuclear Reactor System in our country, and tried to set Westinghouse AP1000 passive residual heat removal system to the primary circuit of CNP1000. Then set up a simulation model based on RELAP5/MOD3.2 program to calculate and analyze the response and operating characteristic of passive residual heat removal system on assumption that Station Blackout occurs. The calculation has the following conclusions: natural circulation was quickly established after accident, which removes core residual heat effectively and keep the core safe. The residual heat can be quickly removed, and during this process the actual temperature was lower than saturation temperature in reactor core.

scholarly journals Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

2021 ◽  
Vol 2021 ◽  
pp. 1-6
Author(s):  
Feng Li ◽  
Yazhe Lu ◽  
Xiao Chu ◽  
Qiang Zheng ◽  
Guanghao Wu
Keyword(s):  
Nuclear Power ◽  
Natural Circulation ◽  
Heat Removal ◽  
Two Phase ◽  
Safe State ◽  
Station Blackout ◽  
Run Test ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two-phase natural circulation principle, the system is designed to bring out long-term core residual heat after an accident to ensure that the reactor is in a safe state. The steady-state characteristic test and transient start and run test of the PRS were carried out on the integrated experiment bench named ESPRIT. The experiment results show that the PRS can establish natural circulation and discharge residual heat of the first loop. China’s Fuqing no. 5 nuclear power plant completed the installation of the PRS in September 2019 and carried out commissioning work in October. This debugging is the first real-world debugging of the new design. This paper introduces the design process of the PRS debugging scheme.

Simulation of Heat Flux Effect in Straight Heat Pipe as Passive Residual Heat Removal System in Light Water Reactor Using RELAP5 Mod 3.2

2016 ◽  
Vol 819 ◽  
pp. 122-126 ◽  
Author(s):  
M. Hadi Kusuma ◽  
Nandy Putra ◽  
Surip Widodo ◽  
Anhar Riza Antariksawan
Keyword(s):  
Heat Flux ◽  
Heat Pipe ◽  
Saturation Temperature ◽  
Heat Removal ◽  
Working Fluid ◽  
Steady State Condition ◽  
Set Up ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Heat pipe is considered being used as a passive system to remove residual heat that generated from reactor core when incident occur or from spent fuel pool. The present research is aimed to studying the characteristics of straight heat pipe as passive residual heat removal system. As an initial step, a numerical simulation was conducted to simulate the best experimental design set up being prepared for the next step of the research. The objective is to get the thermal hydraulic characteristic due to variation of heat flux of heat source. The thermal hydraulic RELAP5 MOD 3.2 code is used to simulate and analyze the straight heat pipe characteristics. Variations of heat flux are 1567 Watt/m2, 3134 Watt/m2, 4701 Watt/m2, 6269 Watt/m2, and 7837 Watt/m2. Water as working fluid is heated on evaporation section with filling ratio 60%. Environmental air with variation 5 m/s and 10 m/s of velocity are used as external cooler. Straight heat pipe used in the simulation is wickless with 0.1 m of diameter and 6 m of length. The results show that higher heat flux given to the evaporator section will lead to more rapid heat transfer and achievement of steady state condition. The increasing of heat flux leads to an increase of evaporation of the working fluid and of pressure built in the heat pipe affecting higher saturation temperature of working fluid. Heat flux loading must consider the velocity of air as heat removal in the condenser to prevent dry out phenomenon in the evaporator. Based on the results, given the experimental set-up, the optimum range of experimental parameters could be determined.

Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000

2012 ◽  
Vol 45 ◽  
pp. 86-93 ◽  
Author(s):  
Mingjun Wang ◽  
Hao Zhao ◽  
Yapei Zhang ◽  
Guanghui Su ◽  
Wenxi Tian ◽  
...  
Keyword(s):  
Heat Removal ◽  
Station Blackout ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Comparison and Analysis on Two Kinds of Passive Residual Heat Removal System Designs Under Station Blackout Accident for Integral Small Modular Reactor

2017 ◽  
Author(s):  
Fei Li ◽  
Feng Shen ◽  
Ning Bai ◽  
Zhaocan Meng
Keyword(s):  
Heat Removal ◽  
Simulation Models ◽  
Small Modular Reactor ◽  
Calculation Results ◽  
Station Blackout ◽  
Safety Features ◽  
Heat Removal System ◽  
System Designs ◽  
Removal System ◽  
Residual Heat

Small Modular Reactor has gained much attention in recent years. The passive residual heat removal system (PRHRS) is designed to increase the inherent safety features of the Integral Small Modular Reactor. There are many differences on the design of PRHRS. To get a comprehensive understanding of the PRHRS design in ISMRs, two simplified simulation models of ISMRs with different PRHRS design are built by the use of thermal hydraulic system code Relap5/Mod3.2 in this paper. A blackout accident is introduced to study the different performance between two PRHRS design models. The calculation results show that both two cases can successfully remove decay heat from the core. But there are still some differences between two cases in aspects of primary and PRHRS coolant parameters. Comparisons of the results from two cases are conducted in this paper, and the differences are carefully analyzed too.

Experimental and Computational Studies of LNPP-2 Passive System for Severe Accident Management

2010 ◽  
Author(s):  
Valery G. Sidorov ◽  
Vladimir Bezlepkin ◽  
Sergej Alekseev ◽  
Sergey Semashko ◽  
Igor Ivkov ◽  
...  
Keyword(s):  
Heat Removal ◽  
Severe Accident ◽  
Primary Circuit ◽  
Steam Generators ◽  
Final Heat ◽  
Spray System ◽  
Heat Absorber ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

The project of nuclear station LNPP-2 with a reactor power plant VVER type by electrical power 1200 MVt involves a number of new design solutions to increase of parameters of safety. The passive containment heat removal system and heat removal system via steam generators is including of number of such solutions. Passive heat removal system via steam generators (PHRS/SG) is assigned for remove of residual heat of reactors core to final heat absorber (atmosphere) through a secondary circuit at DEC accident. The system PHRS/SG duplicates cooling-down system via SG to final heat absorber in case of impossibility of realization of its design functions. Containment heat removal system (PHRS/C) is assigned for remove of residual heat from containment in accidents with heat-transfer emissions from primary circuit. PHRS/C duplicates functions of a spray system to reduce of pressure under containment in case of spray system failure. In the substantiation of passive security systems the complex in SPbAEP of computational and experimental analysis was executed, the main results of which are shown in the present report.

Experimental Research on Characteristics of Passive Residual Heat Removal System for Small Modular Reactors Under the Station Blackout Accident

2016 ◽  
Author(s):  
Xiaodong Lu ◽  
Chuanxin Peng ◽  
Yan Zhang ◽  
Xuesong Bai ◽  
Yuanfeng Zan ◽  
...  
Keyword(s):  
Experimental Research ◽  
Heat Removal ◽  
Injection System ◽  
Primary System ◽  
Water Tank ◽  
The Core ◽  
Station Blackout ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

An experimental research on performance characteristics of passive residual heat removal system (PRHRS) for the small modular reactor designed by Nuclear Power Institute of China (NPIC) under the station blackout accident was performed in the CREAS facility, which consists of the primary system, the secondary system, the passive safety injection system, the passive residual heat removal system, the overpressure protection system and the auxiliary system. The experimental results show that, after the station blackout accident, a stable two-phase natural circulation between the steam generators and the heat exchanger in the PRHRS was established with a mass flow of 0.4T/h, thus the heat from the primary system was removed to the water in the containment water tank (CWT). During this period, the core decay residual heat and the sensible heat were removed from the primary system by the PRHRS effectively. The cold water from the core makeup tanks was injected into the reactor pressure vessel for core cooling. The peaked primary pressure was 16.3MPa and less than relief valve opening pressure 16.9MPa. In addition, the average coolant temperature of the reactor core reduced below 483 K, and the reactor operated safely.

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