Advancements in the research of high-temperature gas-cooled reactor fuel via additive manufacturing techniques
March 2024
Recent advances in high-temperature gas-cooled reactor fuel research have captured the global spotlight, as modern operating contexts demand innovative responses to unprecedented challenges. This article...
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Validation of transient SYSTEM analysis code GINKGO based on a SLB TEST
March 2024
Transient System analysis code is an important tool for reactor thermal hydraulic analysis. GINKGO is a transient system analysis in-house code developed by China General Nuclear Power Corporation (CGN)....
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Investigation on crack propagation of SiCf/SiC composite via PF-CZM method
March 2024
SiCf/SiC composite materials had become a research hotspot in the fields of aerospace materials and nuclear materials in recent years. This materials have high strength, radiation resistance, high temperature...
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Multi-objective optimization research of open and closed air brayton cycle
March 2024
Air Brayton cycle obtains the significant advantages of high efficiency, compact structure, easy medium requirement and so on, which is one of the most suitable choices for the mobile nuclear power...
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Research on thermal stratification of surge line in the marine reactor based on fluid-solid thermal coupling model
December 2023
Due to the requirements of ship movement, the power of the marine reactor is constantly changing, and the expansion and contraction of the primary coolant make the fluid flow in and out through the...
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Research on characteristic of flow instability in a two-phase natural circulation loop with parallel once-through steam generators
December 2023
When there are two sets of parallel once through-steam generators(OTSG) in the natural circulation loop, the thermal-hydraulic characteristics are complicated. Flow instability often occurs in such...
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Conceptual design of a novel megawatt portable nuclear power system by supercritical carbon dioxide brayton cycle coupled with heat pipe cooled reactor
December 2023
In order to meet realistic requirements for flexible and reliable power supply in special scenarios such as remote areas and deep ocean exploration, a novel megawatt portable nuclear power system called...
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Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling
December 2023
External Reactor Vessel Cooling (ERVC) is a key measure to realize molten corium In-Vessel Retention (IVR). The uncertainty of severe accident in core leads to the uncertainty of molten pool parameters...
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Research of aerosol removal by passive containment cooling system
December 2023
Passive containment cooling system (PCCS) can effectively remove the heat from the containment and maintain the pressure and temperature in case of accident, thus ensuring the containment integrity....
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Experimental study of the interaction between molten corium and new sacrificial material for ex-vessel melt retention
December 2023
Ex-vessel melt Retention (EVR) is one of the important countermeasures to address the issue of basement melt penetration in the course of a hypothetical severe accident in a nuclear power plant. Specifically...
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Numerical simulation and structural optimization of spiral finned tube thermal energy storage
September 2023
Thermal energy storage (TES) has emerged as a promising solution to enhance nuclear safety by passively removing decay heat during reactor shutdown and accidents, thus preventing overheating of the...
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Advanced manufacturing technologies for enhancing security in nuclear and radiological materials transport
September 2023
Advanced manufacturing technologies have transformed various industries, including nuclear security areas such as nuclear and radiological transport. This review manuscript describes the intersection...
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Excitation function of neutron induced reaction on isotopes of cadmium (106Cd, 108Cd &110Cd) in the energy range of 13–15 MeV
September 2023
This study focuses on the theoretical calculations of neutron-induced reaction cross-sections on several stable isotopes of cadmium within the energy range of 13–15 MeV. The nuclei produced in this...
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Analysis of thermal hydraulic system code LOCUST V1.2 with ECC thermal mixing test facility
September 2023
The safety injection (SI) system might be put into use, and the coolant at high temperature will mix with the supcooled water under Loss Of Coolant Accident (LOCA). The thermo-hydraulic phenomena associated...
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Research on bubble generation method based on flow control mechanism
Available online 28 August 2023
The method of bubble generation is the key to the application of bubbles, of which the flow control method is widely used because of its low energy consumption and high efficiency, and the flow mechanism...
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Advanced nuclear power engine: A brief overview of gas core reactor for space exploration
June 2023
Space travel requires propulsion with high specific impulse. Gas core reactors using plasma nuclear fuel operate at high temperature (104-105K) and theoretically produce higher specific impulses (2500-7000s)...
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Analysis of containment pressure control strategy in HPR1000 NPP under severe accidents
June 2023
Containment is the last barrier of preventing the release of radioactive fission products in a nuclear power plant (NPP). It has the top priority of its strategy in a severe accident (SA) to ensure...
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Study on iterative algorithm of full plate cross-flow and counter-flow printed circuit heat exchanger for fluoride-salt-cooled high-temperature advanced reactor
June 2023
In the concept of Fluoride-Salt-cooled high-Temperature Advanced Reactor (FuSTAR), the Printed Circuit Heat Exchanger (PCHE) is mainly considered in its supercritical carbon dioxide (S–CO2) Brayton...
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Phenomena identification Ranking Table (PIRT) study for suppression containment of small modular reactor using new methodology
June 2023
The Phenomena Identification and Ranking Table (PIRT) is a significant method for analyzing the safety of nuclear reactors. It helps researchers identify important phenomena within the reactor, enabling...
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Prediction of heat transfer coefficients for steam condensation in the presence of air based on ANN method
June 2023
Artificial neural network (ANN) methods have been gradually used in the field of nuclear reactor thermal-hydraulics as new methods to improve accuracy or fast prediction. This study establishes a back...
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The modeling of passive containment cooling system and sensitivity analysis using the SPRUCE code
June 2023
Passive Containment Cooling Systems (PCCSs) have attracted wide attention to improve the inherent safety of nuclear power plants. This study summarizes a system analysis method of a closed-loop natural...
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The evaporation of nanoscale sodium liquid film on the non-ideal nanostructure surface: A molecular dynamics study
March 2023
The nanoscale liquid sodium film inside the microporous wick structure is of great importance to understanding the evaporation mechanism of the sodium heat pipe. The novel optimized wick structure is...
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Numerical investigation on transverse flow of helical cruciform fuel rod assembly in a lead-bismuth cooled fast reactor
March 2023
The helical cruciform fuel (HCF) rod assembly is a new type of fuel for the lead-bismuth (LBE) fast reactor. It can be self-positioned and realize a coolant mixing without wrapped wire or grid spacer....
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A criticality assessment through user's routines in FLUKA
March 2023
In the present paper, a method to obtain the keff value using the FLUKA code is described. It took advantage of the chance to write user defined routines in the standard code. A new algorithm was implemented...
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Analysis of radiation shielding effectiveness of hydride and borohydride metals for nuclear industry
March 2023
Hydrogenous materials are of great interest in nuclear industry because of the ability of hydrogen to slow-down neutrons. In comparison with common hydrogenous materials, metal hydrides highly enriched...
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