... Abstract The sodium-cooled fast reactor (SFR) experimental device PLANDTL-DHX adopts a loop-type arrangement. In the event of station blackout, a natural circulation is required to remove the decay heat of core. There are two main ways to remove the decay heat from the reactor core, one...

... Abstract To study the natural circulation capabilities of Liquid Lead Bismuth (LBE), natural circulation loops have been designed and constructed in several countries for natural circulation characterization of LBE. These loops aim to characterize LBE’ natural circulation properties. Seeking...

...Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-135738 INVESTIGATION OF THE HEAT TRANSFER PROPERTIES OF NATURAL CIRCULATION FLOW IN THE IRRADIATION CHANNEL OF THE HFETR Jin Shuai Nuclear Power Institute of China...

... are proposed. The first method involves reducing the length of the ring header, while the second method focuses on increasing the buoyancy force of the natural circulation system. The effectiveness of these methods is calculated and discussed. This paper highlights the NHR-200II reactor PRHR system, discusses...

... 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...

... 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...

... 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...

... 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 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 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 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...

... of the reactor pressure vessel of GTHTR300C ruptures, molecular diffusion and local natural convection facilitate gas mixing, in addition to air ingress by counter flow. Furthermore, it is expected that a natural circulation flow around the furnace will suddenly occur. To improve the safety of GTHTR300C...

... 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 cooling system (VCS) of the VHTR. The Japan Atomic Energy Agency is pursuing the design...

... Abstract For a nuclear power reactor operating under forced circulation (FC) and natural circulation (NC) conditions, during transitions between these two types of circulation condition, nuclear reactivity fluctuation will occur due to sudden coolant flowrate change, and the reactivity...