Development status of small modular fast reactors
June 2026
Small modular reactors (SMRs) offer significant prospects for widespread application due to their compact size, modularity, low cost and short construction period, rapid deployment capability, ease...
Distribution-free fault-tree analysis for probabilistic risk assessment under uncertainty
September 2026
This paper proposes a Bayesian framework for a distribution-free fault-tree analysis using a probability-boxes and confidence-boxes to estimate the reliability of a complex coherent system. The approach...
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)...
Preliminary thermodynamic design and optimization of a steam Rankine cycle for CFEDR
December 2026
The China Fusion Engineering Demo Reactor (CFEDR) serves as a vital bridge toward commercial fusion energy, necessitating a highly efficient Power Conversion System (PCS) to manage its multi-grade heat...
Pipe-Diameter Effects on Horizontal Gas-Liquid Flow Regimes and Pressure Drop: A Nuclear Thermal-Hydraulic Review
Available online 24 September 2026
This review systematically examines the influence of pipe diameter on horizontal gas-liquid two-phase flow, focusing on flow regimes, regime transitions, frictional pressure drop, and predictive modeling...
Research progress on irradiation damage of Molybdenum-Rhenium alloys
June 2026
Renowned for their outstanding creep resistance and high-temperature performance, Molybdenum–Rhenium (Mo–Re) alloys are now prime candidates for structural applications in nuclear reactors and first-wall...
Enhancing the efficiency of Mo-99 production in an IAEA 10 MW research reactor through OpenMC-based neutron transport modeling
September 2026
Molybdenum-99 (Mo-99) is a crucial radioisotope widely used in nuclear medicine as the precursor of technetium-99 m (Tc-99 m), which plays a significant role in medical imaging and diagnosis. This study...
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...
Analysis of explosion incidents in nuclear fuel reprocessing facilities and recommendations for their prevention
June 2024
Human society endeavors to harness nuclear energy for peaceful utilization, intertwining it with global strategies to address pressing issues such as energy demand, environmental preservation, and energy...
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...
Simulation and analysis of typical operational conditions in a PWR based on Modelica
September 2026
With advantages such as rapid and simplified modeling and better compatibility with emerging technologies, Modelica is one of the key technical pathways driving the digitalization of future nuclear...
Opportunities and challenges in the application of high-temperature resistant yttrium hydride neutron moderators in microreactors
December 2026
Metal hydrides possess excellent neutron moderating power and favorable thermal conductivity, making them ideal high-temperature neutron moderator materials for micro-nuclear reactors. Zirconium hydride...
Theoretical and experimental study on heat transfer characteristics of water heat pipe
June 2026
The heat pipe is an efficient heat transfer element based on two-phase natural circulation. It offers the advantages of a simple structure, strong heat transfer capability, and excellent isothermal...
Review of spatial scale dispersion models (ATDMs) to simulate environmental dispersion and deposition of radionuclides and the overview of GIS coupling with dispersion models
December 2024
Estimation of the radiological consequences including the calculation of radiation doses to the exposed population requires numerical evaluation of atmospheric radioactive releases from nuclear facilities...
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...
Numerical investigation on the thermal-hydraulic performance of LFR fuel assemblies with multi-parameter wire wrap geometries
December 2026
Lead-cooled fast reactors (LFRs) represent a highly promising fourth-generation nuclear technology, characterized by low operating pressures, inherent safety, and compact core configurations. Within...
Thermal hydraulic study of NuScale iPWR passive containment cooling behaviour during loss-of-coolant accident
June 2025
Operation of the NuScale emergency core cooling system (ECCS) was studied, with an emphasis on the crucial role of the containment vessel (CNV). Design parameters such as vessel volume were varied to...
Research on verification benchmarks for reactor thermal-hydraulic system analysis software
September 2026
Verification serves as the prerequisite for the engineering application of independently developed nuclear safety analysis software. Verification methods for reactor thermal-hydraulic system analysis...
Study on the flow and mechanical properties of the control rod guide tube assembly
September 2026
To investigate the impact of coolant flow within a 2×2 control rod guide tube (CRGT) assembly on the deformation and wear of control rods, this study employed a synergistic approach utilizing both experimental...
A real-time digital twin simulation platform for the AHPR1000 safety system test facility
September 2026
To address the high risk of high-temperature and high-pressure physical testing, the long testing cycle, and the low efficiency of control logic integration in integrated safety system tests for advanced...
Preliminary analysis on oxidation and embrittlement behavior at the burst region of zirconium alloy cladding
December 2026
In the event of a LOCA scenario, the fuel rod cladding experiences a progressive sequence of ballooning, burst and double-side oxidation. Ballooning and burst alter the geometric dimensions of the cladding,...
Research on the natural circulation capability and heat transfer capacity of the new separated water tank for the passive containment cooling system and secondary passive residual heat removal system
September 2026
Passive Containment Cooling System (PCS) and the Secondary Passive Residual Heat Removal System (PRS) are two major passive systems that ensure the safety of nuclear power plants under accident conditions....
Reactivity safety analysis of an air-cooled nuclear thermal propulsion reactor
March 2026
As the most promising alternative to chemical propulsion, nuclear thermal propulsion technology has been extensively studied in recent years. However, most existing research lacks comprehensive safety...
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...
Thermal mechanical response analysis of the first wall in laser initial confinement fusion reactors
June 2025
This paper investigates the thermo-mechanical response characteristics of the first wall of a laser initial confinement fusion reactor under periodic transient heat flux loads. The first wall of the...