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Keywords: natural circulation
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Proceedings Papers

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A078, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92316
... heat transfer steam generator station blackout (SBO) advanced core-cooling mechanism experiment facility natural circulation passive safety Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92316 STUDY ON REVERSE HEAT...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89568
...Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-89568 THE INVESTIGATION ON GEYSERING IN SCALING ANALYSES OF NATURAL CIRCULATION Xiangfei MENG China Nuclear Power Technology Research Institute Shenzhen, China ABSTRACT...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93169
... sodium-cooled fast reactor, the decay heat of the core is discharged through natural circulation. The Plant Dynamics Test Loop (PLANDTL-DHX), an experimental device built in Japan, can simulate core coolant flow process and decay heat transfer phenomenon under decay heat discharged accident condition...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A057, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91869
... pool type fast reactor natural circulation Abstract It is essential to understand the thermal hydraulics of natural circulation in a pool type fast reactor which uses the passive direct heat exchanger (DHX) for decay heat removal. A transparent slab water model has been developed...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92794
... wall heat transfer model sytem code DRACS natural circulation Abstract Passive Direct Reactor Axiliary Cooling System (DRACS) of China Experimental Fast Reactor (CEFR) can effectively remove decay heat generated by core to protect the reactor safety under accident conditions...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93119
... Abstract The natural circulation process with a thermal hydraulic interaction between the core and the plenum in a reactor vessel is a significant issue for the evaluation of the feasibility of a decay heat removal system using dipped-type direct heat exchangers (D-DHXs) in the upper plenum...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A043, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93303
... Abstract Nuclear power in a water-cooled reactor changes with reactivity under the influence of temperature and void fraction. Effects of power oscillations on natural circulation are experimentally investigated with a neutronic-thermo-hydraulic loop to better understand neutronic-thermo...
Proceedings Papers

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A042, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93292
... Abstract Using deionized water as the working fluid, an experimental study on the resistance characteristics of single-phase and two-phase flow under natural circulation conditions is carried out in a 3 × 3 rod bundle channel. For the single-phase flow, the flow regime transition of rod bundle...
Proceedings Papers

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A061, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93526
... Xi'an pulsed reactor passive system natural circulation MLOCA functional reliability probability safety assessment Abstract Due to the epistemic uncertainties involved in the numerical values of its parameters and its modeling, the system may not accomplish its function as required...
Proceedings Papers

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A048, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92779
... inherent safety passive residual heat removal system natural circulation Abstract With the development of nuclear energy and the need for environmental protection, some advanced small reactors have gradually entered the public’s field of vision. The passive natural circulation...
Topics: Heat, Safety, Water
Proceedings Papers

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A034, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66338
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-66338 EXPERIMENTAL SIMULATION OF TRANSITIONS BETWEEN FORCED CIRCULATION AND NATURAL CIRCULATION WITH NUCLEAR REACTIVITY FEEDBACK Hanying Chen1, Linzhong Xia1*, Puzhen Gao2...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A014, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64367
... Abstract Natural circulation refers to the phenomenon of fluid circulation driven by the driving force formed by the density difference and height difference. Natural circulation is very common in nuclear power system, which has an important impact on reactor safety. Therefore, accurate...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63380
... Abstract In order to enhance the safety of sodium-cooled fast reactors, a direct reactor auxiliary cooling system (DRACS) under natural circulation conditions with a dipped-type direct heat exchanger (D-DHX) in an upper plenum of the reactor vessel has been investigated. During the DRACS...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A077, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65682
... Abstract The load distribution and coupling feedback between parallel loops is one of the issues in the multi-loop nuclear reactor system. In the present study, a dual-loop reactor natural circulation experimental system with typical structural features was designed and built based...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A055, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64553
... VHTR GTHTR300C natural circulation molecular diffusion Abstract A depressurization accident involving the rupture of the primary cooling pipe of the Gas Turbine High Temperature Reactor 300 cogeneration (GTHTR300C), which is a very-high-temperature reactor, is a design-based accident...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A054, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64552
... natural circulation vessel cooling system VHTR vertical rectangular channel porous material Abstract A very high-temperature reactor (VHTR) is a next-generation nuclear reactor systems. A gas cooling system with natural circulation is considered as a candidate for the pressure vessel...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64515
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64515 THREE-DIMENSIONAL NUMERICAL SIMULATION ON TRANSIENT NATURAL CIRCULATION CHARACTERISTICS OF DRACS IN PLANDTL-DHX EXPERIMENTAL DEVICE Zijia Chen1,2, Daogang Lu1,2...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A017, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63561
... liquid metal natural circulation grey correlation heat transfer coefficient temperture Abstract Liquid metals have excellent thermal, nuclear physics, and high-density power properties that allow them to efficiently take heat out of the reactor. Based on the data of Natrium, Natrium...