Experimental study on circulation characteristics of secondary passive heat removal system for Chinese pressurized water reactor

In this paper research has been carried out on Loss of Feed Water Accident (LOFW) scenario of the Integral Pressurized Water Reactor ( IPWR) under two circumstances by the use of thermal hydraulic system code i.e Relap5/Mod3.4. In the first one, Passive Residual Heat Removal System (PRHRS) which is designed to absorb core residual heat in case of transient conditions is included which has the function of operating under the accident vulnerabilities. Concerning with the second case i.e without the use of PRHRS rather a tank of water which has the capacity of about 8% of the total feed water supply and is operated under accident scenario is considered. Taken into account these conditions,first the nodalization diagram of the two cases have been figured out then according to the LOFW accident time event scenario use the Relap5 code to simulate the accident. Finally the graphical explanation (separately) of the two cases with graphical approach as well as the conclusion is given at the end.

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Evaluation of a SGTR Accident in the Multi-Application Integrated Pressurized Water Reactor

18th International Conference on Nuclear Engineering: Volume 4, Parts A and B ◽

10.1115/icone18-29953 ◽

2010 ◽

Author(s):

Liguo Jiang ◽

Minjun Peng ◽

Jiange Liu

Keyword(s):

Steam Generator ◽

Flow Model ◽

Heat Removal ◽

Injection System ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Heat Removal System ◽

Removal System ◽

Residual Heat

One of more frequent events in the Pressurized Water Reactor (PWR) is Steam Generator Tube Rupture (SGTR) accident, which is among the main accidents in the field of nuclear safety. This paper studies the SGTR event in the Multi-application Integrated Pressurized Water Reactor (IPWR) using the best-estimate thermal-hydraulic code RELAP5/MOD3.4. In the reactor of IPWR, several Once-Through Steam Generator (OTSG) cassettes are used and located between the core support and the pressure vessel. The tube rupture location is on the top of the tube sheet of a steam generator. Three different tube rupture modeling methods and several different subcooled discharge coefficients in the critical flow model are considered and compared. In the safety analysis, high pressure safety injection system, core makeup system and Passive Residual Heat Removal System (PRHRS) that would affect the accident consequences are considered.

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Experimental Research on Non-Condensable Gases Effects in Passive Decay Heat Removal System

Volume 3: Thermal-Hydraulics ◽

10.1115/icone24-60769 ◽

2016 ◽

Author(s):

Yang Liu ◽

Haijun Jia ◽

Li Weihua

Keyword(s):

High Pressure ◽

Heat Removal ◽

Volume Ratio ◽

Test Facility ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Decay Heat ◽

Optimizing Design ◽

Heat Removal System ◽

Removal System

Passive decay heat removal (PDHR) system is important to the safety of integral pressurized water reactor (IPWR). In small break LOCA sequence, the depressurization of the reactor pressure vessel (RPV) is achieved by the PDHR that remove the decay heat by condensing steam directly through the SGs inside the RPV at high pressure. The non-condensable gases in the RPV significantly weaken the heat transfer capability of PDHR. This paper focus on the non-condensable gas effects in passive decay heat removal system at high pressure. A series of experiments are conducted in the Institute of Nuclear and New Energy Technology test facility with various heating power and non-condensable gas volume ratio. The results are significant to the optimizing design of the PDHR and the safety operation of the IPWR.

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Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor

Science and Technology of Nuclear Installations ◽

10.1155/2009/473795 ◽

2009 ◽

Vol 2009 ◽

pp. 1-12 ◽

Cited By ~ 7

Author(s):

Junli Gou ◽

Suizheng Qiu ◽

Guanghui Su ◽

Douna Jia

Keyword(s):

Heat Exchanger ◽

Steam Generator ◽

Heat Removal ◽

Heat Transfer Area ◽

Pressurized Water Reactor ◽

Height Difference ◽

Pressurized Water ◽

Heat Removal System ◽

Removal System ◽

Residual Heat

A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary side of the steam generator, for an integral pressurized water reactor is presented in this paper. Three-interknited natural circulation loops are adopted by this PRHRS to remove the residual heat of the reactor core after a reactor trip. Based on the one-dimensional model and a simulation code (SCPRHRS), the transient behaviors of the PRHRS as well as the effects of the height difference between the steam generator and the heat exchanger and the heat transfer area of the heat exchanger are studied in detail. Through the calculation analysis, it is found that the calculated parameter variation trends are reasonable. The higher height difference between the steam generator and the residual heat exchanger and the larger heat transfer area of the residual heat exchanger are favorable to the passive residual heat removal system.

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Natural Circulation Characteristics of an Integral Pressurized Water Reactor

Volume 2: Thermal Hydraulics ◽

10.1115/icone14-89390 ◽

2006 ◽

Author(s):

Junli Gou ◽

Suizheng Qiu ◽

Guanghui Su ◽

Dounan Jia

Keyword(s):

Steady State ◽

Steam Generator ◽

Natural Circulation ◽

Heat Removal ◽

Primary Circuit ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Secondary Side ◽

Circulation Characteristics

Natural circulation potential is of great importance to the inherent safety of a nuclear reactor. This paper presents a theoretical investigation on the natural circulation characteristics of an integrated pressurized water reactor. Through numerically solved the one-dimensional model, the steady-state single phase conservative equations for the primary circuit and the steady-state two-phase drift-flux conservative equations for the secondary side of the once-through steam generator, the natural circulation characteristics are studied. Based on the preliminary calculation analysis, it is found that natural circulation mass flow rate is proportional to the exponential function of the power, and the value of the exponent is related to working conditions of the steam generator secondary side. The higher height difference between the core center and the steam generator center is favorable to the heat removal capacity of the natural circulation.

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Optimization and Analysis for Passive Residual Heat Removal System of an Integral Pressurized Water Reactor

Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition ◽

10.1115/icone17-75503 ◽

2009 ◽

Author(s):

Shoubao Dai ◽

Minjun Peng ◽

Jiange Liu

Keyword(s):

Natural Circulation ◽

Heat Removal ◽

Design Parameters ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Secondary Loop ◽

Heat Removal System ◽

Removal System ◽

Peak Value ◽

Residual Heat

The characteristics of passive safety systems for an integral pressurized water reactor (IPWR) are quite different from the general reactor because of special configuration and dangerous run environment. Passive residual heat removal system (PRHRS) for the IPWR with three-interknited natural coolant circulation loops, safely remove the core decay heat to the ultimate heat sink. Using RELAP5/MOD3.4 code to simulate this system during the reactor trip, analyses the steady-state and transient-state thermohydraulic behaviors for the IPWR and its PRHRS, and the effects of design parameters on the system. it is found that on the initial period of reactor trip, due to the establishment of the natural circulation in three loops uncompleted, the secondary loop pressure have the peak value. Through analyzing the effects of design parameters on the system, the PRHRS are optimized. The results show that the larger the residual heat exchanger (RHE) heat transfer area and the higher the height difference between the steam generator and the residual heat exchanger, the easier the establishment of the natural circulation in the third loop, but which make the peak value of the secondary loop pressure higher. According to set the compensating water tank, which is parallel connected to the RHE, can lighten the higher the peak value of the secondary loop pressure, and optimize the design of PRHRS.

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Experimental study on capability and start-up characteristic of advanced secondary passive residual heat removal system

Progress in Nuclear Energy ◽

10.1016/j.pnucene.2021.103929 ◽

2021 ◽

Vol 140 ◽

pp. 103929

Author(s):

Qianhua Su ◽

Haiyan Xu ◽

Donghua Lu ◽

Xiaohang Wu ◽

Xi Yao ◽

...

Keyword(s):

Experimental Study ◽

Heat Removal ◽

Start Up ◽

Heat Removal System ◽

Removal System ◽

Residual Heat

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Experimental study of debris head loss through a pressurized water reactor recirculation sump screen after LOCA

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2011.04.013 ◽

2011 ◽

Vol 241 (7) ◽

pp. 2462-2469 ◽

Cited By ~ 5

Author(s):

Byung Gi Park ◽

Jong Woon Park ◽

Chang Hyun Kim

Keyword(s):

Experimental Study ◽

Head Loss ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor

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An Experimental Investigation of High Level Vibration on the Residual Heat Removal Line of a Pressurized Water Reactor

Volume 4: Fluid-Structure Interaction ◽

10.1115/pvp2009-77809 ◽

2009 ◽

Author(s):

Jeffrey A. Brown ◽

Robert D. Blevins ◽

H. Joseph Fernando

Keyword(s):

Heat Removal ◽

Coupled System ◽

Acoustic Resonance ◽

Acoustic Mode ◽

Side Branch ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

High Level ◽

Residual Heat

This paper presents the results of a scaled aero acoustic test that modeled a side branch resonance observed in the residual heat removal suction line of a large pressurized water reactor. Resolution of the acoustic resonance was sought by detuning the eddy shedding frequency from the fundamental side branch acoustic mode. The specific physical modifications and their ability to detune the coupled system are presented.

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