Kajian Performa Passive Residual Heat Removal System (PRHRS) pada System-Integrated Advanced Modular Reactor (SMART)

SMART (System-Integrated Advanced Modular Reactor) merupakan desain reaktor multifungsi Generasi III+ tipe SMR (Small Modular Reactor) yang dikembangkan oleh KAERI (Korean Atomic Energy Research Institute) dengan kapabilitas produksi listrik 107 MWe dan energi termal 365 MWt. Sistem SMART meliputi berbagai fitur keselamatan untuk mengatasi LOCA (Loss of Coolant Accident) dan skenario kecelakaan lainnya. Salah satu dari fitur tersebut adalah Passive Residual Heat Removal System (PRHRS) atau sistem pembuang sisa panas pasif yang bekerja tanpa membutuhkan sumber daya elektrik. Sistem ini bekerja sesuai dengan prinsip sirkulasi alam sehingga bergantung pada aspek termal, tekanan, dan pengaruhnya terhadap aliran massa. Ketiga aspek tersebut dapat mempengaruhi kapabilitas pembuangan panas pada sistem. Data performa PRHRS reaktor SMART pada beberapa kondisi kecelakaan yang diperoleh melalui studi eksperimental maupun simulasi termohidrolika dianalisis pada kajian ini. Hasil analisis menunjukkan unjuk kerja pembuangan sisa panas yang baik oleh PRHRS SMART dengan waktu aktuasi yang tepat dan pendinginan yang stabil. Dengan kapabilitas multifungsi dan kemampuan pendinginan yang baik pada berbagai skenario kecelakaan, SMART memiliki potensi tinggi untuk kelak diterapkan di Indonesia.

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Thermal Hydraulic Characteristics of the Integral Type Reactor, SMART-P for Validation of the Heat Removal Capability

Volume 2: Thermal Hydraulics ◽

10.1115/icone14-89438 ◽

2006 ◽

Author(s):

K. Y. Choi ◽

S. Cho ◽

S. J. Yi ◽

H. S. Park ◽

N. H. Choi ◽

...

Keyword(s):

System Design ◽

Heat Removal ◽

Test Facility ◽

Integral Type ◽

Control Rod ◽

Type Reactor ◽

Loss Of Coolant ◽

Heat Removal System ◽

Removal System ◽

Residual Heat

The SMART is an integral type reactor with new innovative design features aimed at achieving a highly enhanced safety and improved economics. This paper focuses on the thermal hydraulic experimental program for the development of SMART. Thermal hydraulic responses for the transient operations of the SMART-P are experimentally investigated by using an integral effect test facility. The test facility (VISTA) has been constructed to simulate the SMART-P, which is a pilot plant of the SMART. The VISTA facility is a full height and 1/96 volume scaled test facility with respect to the SMART-P with a power of 65MWt. In the present study, the VISTA facility was subjected to various transient conditions in order to understand the thermal-hydraulic responses following transients and finally to verify the system design of the SMART-P. Several experiments, including a heatup, a main coolant pump (MCP) speed change, and a power change, have been performed to investigate the heat transfer characteristics and the natural circulation performance of the primary system and the Passive Residual Heat Removal System (PRHRS) of the SMART-P by using the VISTA facility. Performance tests of a passive residual heat removal system (PRHRS) have also been carried out for its design optimization. Besides, several design basis accidents, such as an increase or a decrease of the feedwater flow, a loss of coolant flow, a control rod withdrawal, and a limited case of a loss of coolant accident (LOCA) on the line to the gas cylinder are under investigation in order to understand the thermal-hydraulic responses and finally to verify the system design of the SMART-P. Especially, the details of the experimental results for a loss of feedwater accident and a power increase accident due to a control rod withdrawal are explored in the present study.

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

Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues ◽

10.1115/icone25-66181 ◽

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.

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Indefinite sustainability of passive residual heat removal system of small modular reactor using dry air cooling tower

Nuclear Engineering and Technology ◽

10.1016/j.net.2019.11.003 ◽

2020 ◽

Vol 52 (5) ◽

pp. 964-974 ◽

Cited By ~ 1

Author(s):

Min Wook Na ◽

Doyoung Shin ◽

Jae Hyung Park ◽

Jeong Ik Lee ◽

Sung Joong Kim

Keyword(s):

Cooling Tower ◽

Heat Removal ◽

Air Cooling ◽

Dry Air ◽

Small Modular Reactor ◽

Heat Removal System ◽

Removal System ◽

Residual Heat

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Approach for the Analysis of a Shutdown Scenario in the Framework of the Validation of Severe Accident Management Guidelines in Belgium

Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications ◽

10.1115/icone17-75457 ◽

2009 ◽

Author(s):

Antonio Cipollaro ◽

Laurent Sallus

Keyword(s):

Heat Removal ◽

The United States ◽

Severe Accident ◽

Management Guidelines ◽

Accident Management ◽

Loss Of Coolant ◽

Full Power ◽

Heat Removal System ◽

Removal System ◽

Residual Heat

During last four years, in the framework of the periodic safety review of the Belgian Nuclear Power Plants, the Severe Accident Management Guidelines implemented in Belgium have been involved in a series of detailed validation exercises as suggested by the Westinghouse Owner Group SAMG Scenario Templates. The purpose of this task is essentially to evaluate the severe accident management capabilities of the units and to ensure that personnel in the utility’s emergency response organization (crisis team and eventually the control room staff for certain type of accidents) are trained with the use of the above mentioned guidelines. The supporting calculations to the validation exercises have been performed by Tractebel Engineering by means of the MELCOR 1.8.5 code, which is developed under the sponsorship of the United States Nuclear Regulatory Commission (USNRC). Most of the implemented scenarios and related validation exercises account for full power operating states and are based on previous PSA studies. These included Station Black-Out accidents (SBO), Small Break Loss of Coolant Accidents (SBLOCA), Large Break Loss of Coolant Accidents (LBLOCA), and Interface System Loss of Coolant Accidents (ISLOCA), possibly including additional losses of available emergency safeguards features (ECCS, containment sprays, fan coolers, chemical and volumetric control system). In order to cover the entire spectrum of possible scenarios, it has been judged necessary to consider also a type of accident not originated at nominal power but initiated while the plant is in shutdown conditions. The specific Plant Operating State characterizing this scenario has been defined by a mid-loop operation with the reactor pressure vessel head still in place, and including the opening of the pressurizer manhole, the installation of the nozzle dams in all steam generators, the isolation of the reactor building, and the operation of the Residual Heat Removal system. The initiating event of this accident is the loss of the Residual Heat Removal system one day after the normal reactor shutdown. A point demanding a special attention is the fact the entry criterion to redirect towards the opening of the SAMG (based on core exit temperature measurement in full power states) does not straightforward apply in this case and an alternative criterion is necessary. In particular this paper presents the approach and results obtained accounting for the proposed criterion based on the launch of the internal emergency plan and on the timing for the crisis team to be operational and take the decision.

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