Experimental evaluation of safety performance of emergency passive residual heat removal system in HPR1000

Sun, D.C.; Li, Y.; Xi, Z.; Yuanfeng, Zan; Li, P.Z.; Zhuo, Wenbin

doi:10.1016/j.nucengdes.2017.04.003

Cited by 29 publications

(3 citation statements)

References 13 publications

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“…The passive cooling system works without requiring electrical energy, so this system can operate when a Station Blackout (SBO) occurs. The Passive System Simulation Facility (FASSIP) test loop is a passive cooling system experimental test facility for recovering residual heat from decay produced by the reactor core during accident conditions [1], [2], [3], [4]. Several simulation test facilities have been created by the Nuclear Reactor Technology Research Center to be used as a means of experimental-based research on passive cooling.…”

Section: Introductionmentioning

confidence: 99%

Investigation of Heat Exchanger Performance in The Heating Tank Section of Loop FASSIP 03 NT

Haryanto,

Budiman,

Putra

et al. 2024

JurTek: Jurnal Teknologi FT UMJ

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The Passive System Simulation Facility (FASSIP) loop is an experimental test facility for a passive cooling system to recover the residual heat from decay produced by the reactor core during accident conditions. The Heating Tank Section (HTS) is one of the components of the FASSIP 03 NT facility. This component is equipped with a heat exchanger, 3 types of heat exchangers can be applied to HTS. Namely heat exchangers of the Straight Pipe Heat Exchanger (SPHE) type, the Straight Pipe Fins Heat Exchanger (SPFHE) type, and the Helical Pipe Heat Exchanger (HPHE) type. A modification was made to increase the efficiency of HTS, namely replacing the electric heater on the HTS from a ceramic band heater type to an immersion heater type. With this modification, it is necessary to know the performance of the heat exchanger on HTS and its speed in reaching operational temperature. The HPHE-type heat exchanger is more efficient than the SPHE-type and SPFHE-type heat exchangers. The HPHE-type heat exchanger has a much larger length of 5.5 m, so the thermal resistance (Rth) is very small, namely 0.003926 ℃/W. To reach the working fluid temperature in the range of 50 – 90 ℃, the HPHE-type heat exchanger requires 35 – 86 minutes.

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Section: Introductionmentioning

confidence: 99%

Investigation of Heat Exchanger Performance in The Heating Tank Section of Loop FASSIP 03 NT

Haryanto,

Budiman,

Putra

et al. 2024

JurTek: Jurnal Teknologi FT UMJ

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show abstract

“…It adopts the concept of combining active and passive safety systems in its design, and China has fully independent intellectual property rights. Cheng et al [18], Sun et al [19], and Lu et al [20] researched the emergency passive residual heat removal system and steam generator secondary pH under the SGTR condition of HPR1000.…”

Section: Introductionmentioning

confidence: 99%

Pressure Transient Analysis on the Condenser of the HPR1000 Nuclear Power Unit

Lu,

Yang,

Zhang

2024

Energies

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The transient characteristics of pressure in the condenser under fault conditions have a crucial impact on the safe operation of the entire nuclear power plant. In order to ascertain whether the condenser pressure of a HPR1000 nuclear power unit meets the requirements of the steam generator, this paper establishes a mathematical model of the condenser, along with the connected steam turbine bypass steam system and circulating water system, based on Apros. The accuracy of the simulation model is verified by comparing the coasting curve of the circulating water pump with the flow change curve under the pump-tripping condition in Apros. Under the initial CCR condition and the half-side operating condition of the condenser, simulation analyses were conducted for two transient sequences involving the loss of normal external power and the simultaneous tripping of two circulating water pumps. The corresponding changes of pressure in the condenser under the transient sequence were obtained. The study reveals that, under different initial conditions and transient sequences, the condenser pressure of the unit can meet the requirements of a 12 s steam discharge to the condenser before the internal pressure of the condenser reaches the “unavailable” set value when the turbine bypass system is under the fault condition. The research findings of this paper can provide reference data for the design, commissioning, and operation of subsequent HPR1000 nuclear power plants.

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“…3.6334 from removing heat generation during station blackout (SBO) event. In the design concept of next-generation NPP, the PCS is implemented [1][2][3][4].…”

Section: Introductionmentioning

confidence: 99%

Study on Thermal Characteristics of U-Shaped Heat Pipe

et al. 2021

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The latest accident in Japan's nuclear power station became a valuable experience to start engaging passive cooling systems (PCS) more aggressively to improve safety aspects in nuclear power reactors being studied in Indonesia. This investigation is related to the U-shaped heat pipe (UHP) research as PCS of water in the cooling tank (CT). The objective of this research is to study the thermal characteristics of UHP as PCS in the CT. The experiment on small-scale UHP and simulation with RELAP5 code has been conducted to understand the performance of UHP. The experiment results of the small-scale UHP model will be used as a basic understanding of simulating and designing a UHP with big scaling. The study result showed the highest thermal performance of UHP was obtained when it operated on the higher temperature of heat load and higher air cooling velocity. The more UHPs inserted into the cooling pool, the more heat that can be discharged into the environment. This result also shows promising use of UHP for CT PCS. The use of UHP as PCS can enhance the safety aspect of the nuclear reactor, especially in station blackout event.

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Experimental evaluation of safety performance of emergency passive residual heat removal system in HPR1000

Cited by 29 publications

References 13 publications

Investigation of Heat Exchanger Performance in The Heating Tank Section of Loop FASSIP 03 NT

Investigation of Heat Exchanger Performance in The Heating Tank Section of Loop FASSIP 03 NT

Pressure Transient Analysis on the Condenser of the HPR1000 Nuclear Power Unit

Study on Thermal Characteristics of U-Shaped Heat Pipe

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