... can be used to couple with FLUENT to calculate the emergency response of CEFR between circuits under an accident. The SAC-DRACS-II in this work can be used for the safety analysis of pool-type fast reactor DRACS. wall heat transfer model sytem code DRACS natural circulation Proceedings...

... Abstract In the floating nuclear power plant, Core Make-up Tank (CMT) is one of the passive safety facilities, has been widely used in nuclear engineering. Under emergency conditions, natural circulation occurs and consequent thermal stratification appears in CMT system. However, rolling motion...

... 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...

... Abstract The passive decay heat removal system based on natural circulation can passively remove the heat from the core, which greatly improves the safety of the nuclear reactor. The Plant Dynamics Test Loop (PLANDTL-DHX) experimental facility can simulate the flow and heat transfer...

... 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...

... 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...

... 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. Functional failure becomes an important factors in the natural circulation system operation failure, which needs...

... 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 is an important part of the inherent safety feature for advanced small reactors. Based...

... 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...

... Abstract Natural circulation as a mode of heat removal is being considered as a prominent passive feature in the innovative nuclear reactor designs, particularly in boiling-water-reactors, due to its simplicity and economy. However, boiling natural circulation system poses many challenges...

... Abstract If the plant blackout accident occurs in the pool-type 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...

... 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 at China Institute of Atomic Energy, which allows...

... 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 of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64367 APPLICATION OF HIGH ACCURACY NUMERICAL METHODS FOR THE NATURAL CIRCULATION PROBLEM Fei Chao Longze Li Wen Yang Wuhan Second Ship Design and Wuhan Second Ship Design...

... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-63380 CORE THERMAL-HYDRAULIC ANALYSIS DURING DIPPED-TYPE DIRECT HEAT EXCHANGER OPERATION IN NATURAL CIRCULATION CONDITIONS Erina Hamase, Norihiro Doda, Ayako Ono, Masaaki...

... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-65682 STUDY ON FLOW CHARACTERISTICS OF DOUBLE LOOP NATURAL CIRCULATION SYSTEM UNDER ASYMMETRIC CONDITIONS Shuang Wang1,2, Xin Li1,2, Yongchao Liu1,2, Shouxu Qiao1,2...

... facilitate gas mixing, in addition to He air ingress by counter flow. Furthermore, it is expected that a natural circulation flow around the furnace will suddenly occur. m To improve the safety of GTHTR300C, an experiment was conducted using an experimental apparatus simulating the flow 1. INTRODUCTION path...

... with Metal wire length natural circulation is considered as a candidate for the pressure Local Nusselt number vessel cooling system (VCS) of the VHTR. The Japan Atomic Energy Agency is pursuing the design and development of defined by Eqs. (4), (5) and (9) commercial systems such as the 300 MWe gas turbine...

...Abstract Abstract The pool-type sodium-cooled fast reactor adopts a new type of decay heat removal method to discharge the core heat to ensure the safety and cool of the nuclear power plant in a long time under the station blackout accident. The natural circulation and forced circulation...

...-6, 2021, Virtual, Online ICONE28-63561 GREY CORRELATION STUDY ON NATURAL CIRCULATION HEAT TRANSFER COEFFICIENT OF LIQUID METAL Chen Ning Zhou Tao* Zhou Lanyu School of Nuclear Science and Southeast University School of China Nuclear Power Engineering, North China Electric Energy and Enviroment, Nan...