Article
Energy & Fuels
Shibao Wang, Dalin Zhang, Suizheng Qiu, Guanghui Su, Wenxi Tian
Summary: The study focused on simulation of the hot plenum in a sodium-cooled fast reactor, proposing a 2-dimensional method to address the thermal stratification phenomena. Special techniques were implemented to restore the geometry reality, resulting in an optimal model with an 8-block partition scheme. Experimental validation demonstrated the effectiveness of the model in tackling spatial layout in pool-type SFRs.
INTERNATIONAL JOURNAL OF ENERGY RESEARCH
(2021)
Article
Nuclear Science & Technology
Yongping Wang, Liang Qiao, Xianan Du, Youqi Zheng
Summary: This paper focuses on the application of the nuclear data adjustment method in the physics calculation of sodium cooled fast reactors. The study derives a multi-parameter nuclear data adjustment method based on Bayesian theory, and provides experimental screening rules. Verification is conducted using 47 candidate experiments from zero-power experimental facilities. The results show that adjusting based only on k(eff) has limitations, while the multi-parameter method effectively reduces uncertainties and errors for various physical parameters.
PROGRESS IN NUCLEAR ENERGY
(2023)
Article
Nuclear Science & Technology
Omur Akbayir
Summary: The study aims to predict the peak fuel temperature under different temperature conditions in a depressurized cooldown accident, and determine the impact of flow bypass gap size. The results show that all peak fuel temperatures remain below the TRISO design limits of 1600 degrees C.
NUCLEAR ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
D. Guenadou, P. Aubert, J-P Descamps
Summary: The CEA has been involved in the development of fourth generation sodium-cooled reactors for decades. Due to the complexity of sodium experiments, water is mostly used as a simulant fluid. The MICAS mock-up, representing the upper plenum, aims to study the behavior of the jet emitted from the core. Understanding the operating conditions for a steady jet is crucial for designing the hot plenum.
NUCLEAR ENGINEERING AND DESIGN
(2022)
Article
Energy & Fuels
Rongshuan Xu, Ping Song, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui H. Su
Summary: This study developed a numerical analysis code called COSFIAS to investigate the flow instability of parallel channels in a sodium heated OTSG, validated experimental data, and drew conclusions: decreasing water pressure increases heat transfer power and destabilizes the system; sodium heated condition is more stable compared to uniform heating condition; inlet subcooling in different regions affects the stability of the parallel channels system.
INTERNATIONAL JOURNAL OF ENERGY RESEARCH
(2021)
Article
Nuclear Science & Technology
Xi Bai, Peiwei Sun, Gang Luo, Huasong Cao, Xinyu Wei
Summary: In modern sodium-cooled fast reactor (SFR) designs, paralleling steam generators (SGs) are used to improve the economy. A detailed pressure wave propagation model based on conversion equations was derived and verified with experimental data, which simulated a large leakage sodium-water reaction (SWR) accident in the SFR with four parallel SGs. Sensitivity analysis of critical parameters on large leakages was also conducted. The findings of this study are valuable for SG designs and protection from large leakage SWR accidents.
PROGRESS IN NUCLEAR ENERGY
(2023)
Article
Nuclear Science & Technology
Yang Yu, Dong Liu, Xiaoming Song, Zhongchun Li, Fengchen Guo, Yafeng Wang, Bo Pang
Summary: In this study, a transient thermal-hydraulic code THCSA was developed to analyze the primary coolant system of a pool-type sodium cooled fast reactor, showing a benign response to transient conditions and proving the effectiveness of the models and numerical method.
ANNALS OF NUCLEAR ENERGY
(2021)
Article
Energy & Fuels
Shibao Wang, Dalin Zhang, Yapeng Liu, Chenglong Wang, Suizheng Qiu, Guanghui Su, Wenxi Tian
Summary: This experiment validated a modular code THACS focusing on safety analysis of SFR and carried out necessary development and verification for physical property, frictional loss, and heat transfer of water. Simulation of an unprotected loss-of-flow scenario predicted natural circulation paths and the transition of heat exchanger operation mode.
INTERNATIONAL JOURNAL OF ENERGY RESEARCH
(2021)
Article
Nuclear Science & Technology
Yang Yu, Fengchen Guo, Wei Lu, Xueqiang Wang, Zhuo Sun
Summary: The paper presents the development of a real-time simulation code for analyzing the primary coolant system of a pool-type sodium cooled fast reactor. Different numerical methods are utilized to solve the equations sets, and the results are in good agreement with the final safety analysis report. The newly developed code can be used in the real-time simulation of similar reactor systems and has been adopted in the development of a full scope simulator for the CEFR.
ANNALS OF NUCLEAR ENERGY
(2022)
Article
Nuclear Science & Technology
Junghyun Bae, Robert S. Bean
Summary: In this paper, the thermohydraulic limits on the maximum power of the Purdue University research reactor (PUR-1) are investigated using computational fluid dynamics (CFD) simulations coupled with Monte Carlo neutron transport simulations. The results show that the thermohydraulic limit for the PUR-1 core power is 350 kW without changing the coolant system, but with a conservative safety margin, the estimated maximum power level is decreased to 170 kW. Additional cooling systems, such as guide pipes and lowered coolant temperature, are also presented to demonstrate the potential of advanced cooling capacity.
NUCLEAR SCIENCE AND ENGINEERING
(2022)
Article
Nuclear Science & Technology
G. M. S. K. Chaitanya, Anish Kumar
Summary: A new ultrasonic imaging method is introduced in this paper for assessing the bowing of subassembly (SA) heads. Specific signatures in the ultrasonic signals can be used to detect the bowing of SA heads, and images from two orientations are superimposed for better visualization of the arrangement of SAs.
ANNALS OF NUCLEAR ENERGY
(2021)
Article
Nuclear Science & Technology
Seongmin Lee, Yonghee Kim, Yonadan Choi, Yong Hoon Jeong
Summary: Negative reactivity feedback is an important safety characteristic of reactors, and the floating absorber system (FAST) can improve the coolant temperature coefficient and stabilize the system by introducing damping. This study explains the variables affecting the FAST behavior and proposes a damping FAST to passively remove oscillations. The performance evaluation in an innovative sodium-cooled fast reactor shows that the damping FAST significantly lowers the core power and keeps the coolant temperature stable, improving the inherent safety of SFRs.
ANNALS OF NUCLEAR ENERGY
(2022)
Article
Nuclear Science & Technology
Zeng-Yao Li, Guang-Lei Yu
Summary: This study investigates the thermal hydraulic characteristics of the intermediate heat exchanger (IHX) and analyzes the influence of coaxial bends on its performance. Utilizing both 3-D detail simulation method and the distributed parameter method, it was found that the shell-side main flow direction is generally consistent with the tube direction, and that the bending section plays a crucial role in controlling the non-uniformity of temperature field.
NUCLEAR ENGINEERING AND DESIGN
(2021)
Article
Energy & Fuels
Liwen Huang, Jia Wang, Wen-Feng Lin, Yan Wu
Summary: A ceria electrolyte-based solid ceramic fuel cell (SCFC) with a layer-structured Li1-xNaxNi0.8Co0.15Al0.05O2 (LNNCA) anode was developed. The use of LNNCA anode significantly improved the power density of the fuel cell at high temperatures, while still maintaining operability at low temperatures. The anchoring effect of doped Na+ and the in-situ grown NaOH played crucial roles in enhancing the catalytic activity, electrical contact, and bonding between the anode and electrolyte, as well as providing transport channels for ions.
Article
Engineering, Environmental
S. Abbasi, A. A. Zinatizadeh, M. Mirghorayshi, S. Zinadini, T. McKay
Summary: The study evaluated a novel laboratory scale continuous electrocoagulation (EC) reactor using iron rod electrodes for treating licorice processing wastewater. Results showed that the EC system with iron rod electrodes performed better in turbidity removal compared to iron plate electrodes.
JOURNAL OF ENVIRONMENTAL CHEMICAL ENGINEERING
(2022)
Article
Nuclear Science & Technology
S. Balaguru, Vela Murali, P. Chellapandi
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS
(2016)
Article
Chemistry, Multidisciplinary
Gnanaselvan Gnanasekaran, Sasikumar Balaguru, Gangasalam Arthanareeswaran, Diganta B. Das
SEPARATION SCIENCE AND TECHNOLOGY
(2019)
Article
Nuclear Science & Technology
S. Balaguru, Vela Murali, P. Chellapandi, Manoj Gupta
NUCLEAR ENGINEERING AND TECHNOLOGY
(2020)
Article
Materials Science, Multidisciplinary
S. Balaguru, Mohammad Abid, M. Gupta
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
(2020)
Article
Energy & Fuels
Rajvikram Madurai Elavarasan, G. M. Shafiullah, Kannadasan Raju, Vijay Mudgal, M. T. Arif, Taskin Jamal, Senthilkumar Subramanian, V. S. Sriraja Balaguru, K. S. Reddy, Umashankar Subramaniam
Review
Materials Science, Multidisciplinary
S. Balaguru, M. Gupta
Summary: Hardfacing is commonly used to increase the service life of structural components, with Ni-base, Co-base, and Fe-base alloys being widely utilized. Ni-base alloys are preferred for their ability to retain hardness at elevated temperatures. Various research works on Ni alloy hardfacings using different processes on different substrates can benefit researchers and industries in the field of hardfacing.
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
(2021)
Article
Engineering, Mechanical
Amruta Pasarkar, S. Balaguru
Summary: This paper discusses the need for hardfacing of components in a Sodium Cooled Fast Reactor (SFR) and explores the importance of studying fatigue characteristics. Selecting coating materials with good creep and fatigue life is essential for achieving high breeding ratio and high fuel burn up.
ENGINEERING FAILURE ANALYSIS
(2022)
Article
Engineering, Multidisciplinary
Makendran Chandrakasu, Karunanidhi Suthandhiram, Shiferaw Garoma, Bekesha Merea, Balaguru Sethuraman
Summary: The self-curing process is considered a better alternative for concrete structures in Ethiopia due to the scarcity of water. Polyethylene Glycol (PEG) 600 was studied as a substitute, and its significant results for self-curing concrete were confirmed through testing.
Article
Engineering, Biomedical
Pravin R. Lokhande, S. Balaguru
JOURNAL OF BIOMIMETICS BIOMATERIALS AND BIOMEDICAL ENGINEERING
(2019)
Proceedings Paper
Materials Science, Multidisciplinary
S. Balaguru, Elango Natarajan, S. Ramesh, B. Muthuvijayan
MATERIALS TODAY-PROCEEDINGS
(2019)
Proceedings Paper
Engineering, Electrical & Electronic
N. Kalaiselvi, K. R. Aravind, S. Balaguru, V. Vijayaragul
2017 FOURTH INTERNATIONAL CONFERENCE ON SIGNAL PROCESSING, COMMUNICATION AND NETWORKING (ICSCN)
(2017)
Article
Public, Environmental & Occupational Health
Matthew J. Mimiaga, Beena Thomas, Katie Biello, Blake E. Johnson, Soumya Swaminathan, Pandiyaraja Navakodi, S. Balaguru, A. Dhanalakshmi, Elizabeth F. Closson, Sunil Menon, Conall O'Cleirigh, Kenneth H. Mayer, Steven A. Safren
Proceedings Paper
Computer Science, Hardware & Architecture
Saranya Balaguru, Rachel Nallathamby, C. R. Rene Robin
INTERNATIONAL CONFERENCE ON COMPUTER, COMMUNICATION AND CONVERGENCE (ICCC 2015)
(2015)
Proceedings Paper
Engineering, Mechanical
S. Balaguru, K. Saranraj, Murali Vela, P. Chellapandi
ADVANCED MANUFACTURING RESEARCH AND INTELLIGENT APPLICATIONS
(2014)
