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Analysis of natural circulation types' effect on source term during PWR severe accident [PDF]
مجله علوم و فنون هستهای, 2023 Creep rupture as a failure mechanism during a severe accident in a PWR is of particular importance as it can lead to releasing radioactive materials into the environment.
A. Zarnousheh Farahani +3 more
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Frontiers in Energy Research, 2021 SNCLFR-100 is a small modular natural circulation lead-cooled fast reactor, developed by University of Science and Technology of China, aiming at taking full advantage of the good economics and inherent safety of lead-cooled fast reactors to develop ...
Chao Guo +5 more
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Frontiers in Energy Research, 2022 A steady state model of the NuScale reactor has been built using the thermal hydraulic module CESAR of the severe accident code ASTEC. Construction of the model was achieved through iterations based on convergence towards data provided by NuScale ...
Zhexi Guo, Sicong Xiao, Keng Yeow Chung
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Assessment of Modified RELAP5 MOD3.2 Against LBE Natural Circulation Test Loops
Frontiers in Energy Research, 2021 Motivated by the significant natural circulation capability of lead–bismuth eutectic (LBE)–cooled systems, the RELAP5 MOD3.2 code was modified for the analysis of LBE-cooled reactors and non-nuclear systems.
Yufeng Lv +4 more
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The effect of code user and boundary conditions on RELAP calculations of MTR research reactor transient scenarios [PDF]
Nuclear Technology and Radiation Protection, 2005 The safety evaluation of nuclear power and re search reactors is a very important step before their construction and during their operation. This evaluation based on the best estimate calculations requires qualified codes qualified users, and qualified ...
Khedr Ahmed +2 more
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Determination of the maximum core power of natural circulation lead–bismuth reactors
He jishu, 2023 BackgroundBecause of the excellent properties of lead-based materials as reactor coolants, lead-based fast reactors have become a key type of fourth-generation advanced nuclear energy systems.
XIAO Yingjie +5 more
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Nodalization effects on RELAP5 results related to MTR research reactor transient scenarios [PDF]
Nuclear Technology and Radiation Protection, 2005 The present work deals with the anal y sis of RELAP5 results obtained from the evaluation study of the total loss of flow transient with the deficiency of the heat removal system in a research reactor using two different nodalizations.
Khedr Ahmed, d’Auria Francesco
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1D modelling and preliminary analysis of the coupled DYNASTY–eDYNASTY natural circulation loop
Frontiers in Energy Research, 2023 In the continuous strive to improve the safety of current-generation and next-generation nuclear power plants, natural circulation can be used to design passive safety systems to remove the decay heat during the shutdown.
Gabriele Benzoni +4 more
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Mechanical Engineering Journal, 2020 Fully natural circulation decay heat removal systems (DHRSs) are adopted for sodium fast reactors, which is a passive safety feature without any electrical pumps.
Ayako ONO +4 more
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Investigation on natural circulation phenomena of LOCA with PRHR pipeline break in ACME facility
He jishu, 2023 BackgroundThe passive residual heat removal (PRHR) system is an important innovative design of the advanced pressurized water reactor technology. Under accident conditions, PRHR system can transport decay heat in the form of natural circulation to ensure
LIU Yusheng +5 more
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