Investigation of thermal hydraulic behavior of SBLOCA tests in SMART-ITL facility

Kim, Yeon-Sik; Bae, Hwang; Jeon, Byong-Guk; Bang, Yoon-Gon; Yi, Sung-Jae; Park, Hyun-Sik

doi:10.1016/j.anucene.2017.11.013

Cited by 20 publications

(2 citation statements)

References 5 publications

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“…The in-vessel source terms release rate was calculated based on the relative volatility method described in IAEA TECDOC 1127. Based on Kim et al [11] the result of blowdown analysis for the SMART using the MARS-KS code, the blowdown time is 9 seconds for a double-ended guillotine break scenario. The normal operating power is 330 MWth with an average burn-up of approximately 40,000 MWd per metric ton of uranium (MTU).…”

Section: In-vessel Release Fraction Calculationmentioning

confidence: 99%

The Preliminary Study on Implementing a Simplified Source Terms Estimation Program for Early Radiological Consequences Analysis

Ryanto¹,

Pane²,

Setiawan³

et al. 2023

Tri Dasa Mega

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Indonesia possesses numerous potential sites for nuclear power plant development. A fast and comprehensive radiological consequences analysis is required to conduct a preliminary analysis of radionuclide release into the atmosphere, including source terms estimation. One simplified method for such estimation is the use of the Relative Volatility approach by Kess and Booth, published in IAEA TECDOC 1127. The objective of this study was to evaluate the use of a simple and comprehensive tool for estimating the source terms of planned nuclear power plants to facilitate the analysis of radiological consequences during site evaluation. Input parameters for the estimation include fuel burn-up, blow-down time, specific heat transfer of fuel to cladding, and coolant debit, using 100 MWe PWR as a case study. The results indicate a slight difference in the calculated release fraction compared to previous calculations, indicating a need to modify Keywords: Source terms, Relative volatility, Release fraction, PWR, SMART

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Section: In-vessel Release Fraction Calculationmentioning

confidence: 99%

The Preliminary Study on Implementing a Simplified Source Terms Estimation Program for Early Radiological Consequences Analysis

Ryanto¹,

Pane²,

Setiawan³

et al. 2023

Tri Dasa Mega

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“…Gambar 12. Hasil Pengujian Aliran Massa pada Reaktor SMART Melalui Fasilitas Eksperimental SMART-ITL oleh Y.-S Kim et al[24].…”

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

Sudarsana

Septiadi

Juarsa

2021

Jurnal Pengembangan Energi Nuklir

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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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Validation of the SPACE Code Through Simulated Accident Scenarios in SMART-ITL: A Focus on Pressurizer Safety Valve Break and Safety Injection Line Break Concurrent with TLOSHR

Al-Faifi,

Bali,

Kim

2024

Lecture Notes in Mechanical Engineering

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Investigation of thermal hydraulic behavior of SBLOCA tests in SMART-ITL facility

Cited by 20 publications

References 5 publications

The Preliminary Study on Implementing a Simplified Source Terms Estimation Program for Early Radiological Consequences Analysis

The Preliminary Study on Implementing a Simplified Source Terms Estimation Program for Early Radiological Consequences Analysis

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

Validation of the SPACE Code Through Simulated Accident Scenarios in SMART-ITL: A Focus on Pressurizer Safety Valve Break and Safety Injection Line Break Concurrent with TLOSHR

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