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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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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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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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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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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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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Steady-state thermal fluids analysis for the HTR-PM equilibrium core
2021
The high temperature gas-cooled reactor-pebble bed module (HTR-PM), designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, is a demonstration project of nuclear...
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Study on the thermal and geometrical parameters of helical coil once-through steam generator system
2021
Due to the special structure, helical coil once-through steam generators (HCOTSGs) can withstand greater thermal expansion stress, have a larger heat exchange area, and cause the secondary flow phenomenon...
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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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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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Experimental study on flow characteristics of rectangular narrow channel
2020
Plate fuel elements is gradually used in advanced reactor structure design because of its advantages of high fuel consumption and high safety. The flow channel of the plate fuel element is a typical...
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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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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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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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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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Development and evaluation of fuel performance analysis code FuSPAC
September 2022
The nuclear fuel rod should maintain self-sustainable nuclear fission, as the first safety barrier to prevent the leakage of radioactive products. The fuel rod performance analyses are essential to...
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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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Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code
2021
In this research, a conceptual approach is presented to obtain the neutron flux at a reactor core. A simple spherical reactor core was analyzed by a mathematical model defined by Delphi programming...
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Assessment of radiological safety and emergency response of VVER-1200 type reactor
June 2022
We studied the radiological safety and emergency response of the VVER-1200 type nuclear power plant using the RASCAL 4.3 and HOTSPOT 3.1.2 codes for INES levels 5, 6, and 7 reactor accidents due to...
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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 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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Determination of the neutron and gamma ray dose rates of the irradiating beam tubes of a pool-type research reactor by using Monte Carlo simulation and experimental detectors regarding radiation protection issues
2021
In this paper, the reactor core, irradiating beam tubes, and radiological shields of a 5 MW open pool type Material Testing Reactor (MTR) are simulated in detail by using the MCNPX 2.6 code and its...
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Experimental study on thermal-hydraulic performance of helically coiled tubes steam generator of lead-bismuth reactor
March 2024
The advantages of the helically coiled tube steam generator lie not only in its high heat transfer efficiency but also in its compact structure, which is initially used in Pb–Bi–SCO2 reactors, and its...
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Calculation of flow heat transfer characteristics of liquid gallium
2021
In order to design a more compact small nuclear reactor, liquid metal gallium can be selected as the reactor coolant. Gallium is rarely used in reactor as liquid metal coolant, however, due to its excellent...
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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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