Results 41 to 50 of about 296,182 (247)
Yuanzineng kexue jishuThe safety analysis of pebble-bed high-temperature gas-cooled reactor (PB-HTGR) relies heavily on high-fidelity system-level simulation tools. However, existing analysis codes face significant limitations in modeling the integrated transient response of ...
WU Zhao, HUA Yingjie, WU Pan, SHAN Jianqiang
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Energies, 2019 The movement and deposition of particles that occur during their natural circulation in supercritical water exercise an important impact on the safe and stable operation of a supercritical water reactor (SCWR). When supercritical water flows in pipelines,
Liangyu Zhu +4 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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DDX3X induces mesenchymal transition of endothelial cells by disrupting BMPR2 signaling
FEBS Open Bio, EarlyView.Elevated DDX3X expression led to downregulation of BMPR2, a key regulator of endothelial homeostasis and function. Our co‐immunoprecipitation assays further demonstrated a molecular interaction between DDX3X and BMPR2. Notably, DDX3X promoted lysosomal degradation of BMPR2, thereby impairing its downstream signaling and facilitating endothelial‐to ...
Yu Zhang +7 more
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Research Progress in Key Thermal-hydraulic Issue of Sodium-cooled Fast Reactor
Yuanzineng kexue jishuSodium-cooled fast reactors are considered the preferred reactor type for fourth generation nuclear energy systems due to their high thermal efficiency, high fuel utilization efficiency, inherent safety, and unique advantages of achieving a closed fuel ...
YANG Hongyi1, XUE Xiuli1, , , ZHOU Zhiwei1, LIN Chao1, LI Hongrui2, GAO Xinzhao1, YU Xintai1, MA Xiao1, XIAO Yubai1, LUO Rui2
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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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FEBS Open Bio, EarlyView.Aged human bmMSCs are seeded in the scaffold. Osteoblastic induction can slightly increase cell's bone‐forming activity to produce bone‐like tissues, shown as the sporadic xylenol orange‐stained spots (the lower left image). Notably, pioglitazone plus EGCG co‐treatment dramatically increases cell's bone‐forming activity and bone‐like tissue production (
Ching‐Yun Chen +6 more
wiley +1 more source
Design approach for mitigation of air ingress in high temperature gas-cooled reactor
Mechanical Engineering Journal, 2016 One important safety design consideration for high temperature gas-cooled reactor (HTGR) is air ingress following a rupture of the reactor pressure boundary such as primary piping.
Hiroyuki SATO +2 more
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