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ISSN: 2468-6050

Advanced nuclear power engine: A brief overview of gas core reactor for space exploration

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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Advanced manufacturing technologies for enhancing security in nuclear and radiological materials transport

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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Study on the thermal and geometrical parameters of helical coil once-through steam generator system

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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Steady-state thermal fluids analysis for the HTR-PM equilibrium core

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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Experimental study on flow characteristics of rectangular narrow channel

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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Numerical simulation and structural optimization of spiral finned tube thermal energy storage

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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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

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

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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Phenomena identification Ranking Table (PIRT) study for suppression containment of small modular reactor using new methodology

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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Study on startup characteristics of prototype once-through steam generator for China fast reactor

Once-through steam generator (OTSG) is a vital heat transfer equipment of China Fast Reactor-600 (CFR-600), and its startup characteristics are of great importance to the safe operation of nuclear power...

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Research on bubble generation method based on flow control mechanism

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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Numerical investigation on transverse flow of helical cruciform fuel rod assembly in a lead-bismuth cooled fast reactor

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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Study on iterative algorithm of full plate cross-flow and counter-flow printed circuit heat exchanger for fluoride-salt-cooled high-temperature advanced reactor

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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Analysis of radiation shielding effectiveness of hydride and borohydride metals for nuclear industry

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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Prediction of heat transfer coefficients for steam condensation in the presence of air based on ANN method

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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Improvement and evaluation of ATWS Protective Signal and mitigation system for ACPR1000 nuclear power plant

At the event of Loss of Normal Feed Water-An Anticipated Transient without Scram (LOFW-ATWS) in ACPR1000 unit, there exists the primary overpressure risk probability when the regulation function of...

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Development and evaluation of fuel performance analysis code FuSPAC

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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Development of an edge-cloud collaboration framework for fission battery management system

As a “plug-and-play” nuclear system, the technology of fission battery enables nuclear reactor systems to function as batteries. Undoubtedly, advanced intelligent technologies have to be adopted to...

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Studies on post-dryout heat transfer in R-134a vertical flow

An experimental study of post-dryout heat transfer with the coolant R-134a was performed in a vertical round tube with upward flow. The experiments were conducted in an uniformly heated tube with an...

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Influence of zinc injection on deposition of corrosion products on inner wall of heat transfer tube

The zinc injection process has been widely used in the primary coolant of PWR nuclear power plants. This study explored its effect in the water coolant of fusion reactors. The research uses the International...

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Heat transfer performance of high temperature and high velocity hydrogen flow and analysis of blockage characteristics

In the current situation of increasing demand for nuclear heat propulsion in various countries, the heat transfer characteristics of high temperature and high velocity fluid in the flow channel are...

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Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core

The random distribution of TRISO fuel particles in the fuel elements may form local hotspots, thereby increasing the thermal stress on TRISO particle layers that may cause particle failures. Optimization...

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Analysis of thermal hydraulic system code LOCUST V1.2 with ECC thermal mixing test facility

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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IVR design and review of advanced NPPs in China: Issues and perspectives

The In-Vessel Retention (IVR) is an attractive strategy which could avoid the failure of Reactor Pressure Vessel (RPV) and consequent phenomenon in severe accident of nuclear power plants (NPPs). Most...

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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

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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