Methodology of probabilistic safety assessment for transportation of radioactive material

2024-8-19

A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event

2024-8-16

Frontmatter

2024-8-1

Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction

2024-8-1

Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation

2024-7-30

Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE

2024-7-29

Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor

2024-7-26

Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants

2024-7-25

Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies

2024-7-25

Comparison of modeling methods for the effective diffusivities of IO₃ ⁻ estimated in compacted bentonite using through-diffusion tests under aerobic conditions

2024-7-25

Study on comprehensive evaluation method of mental workload level

2024-7-24

Fuzzy reliability algorithm for the shutdown system of research reactor

2024-7-24

Reliability analysis of digital reactor protection systems in floating nuclear power plants

2024-7-24

System theory safety analysis of network malfunction in nuclear power plant distributed control systems

2024-7-24

A detection and defense security system design for nuclear waste storage against stealth terrorists attack

2024-7-23

Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)

2024-7-22

Calendar of events

2024-7-22

Frontmatter

2024-5-29

Investigating advection–dispersion behavior for simulation of HTO and ²³⁸Pu transport in argillaceous shale with different varying degrees of weathering

2024-5-20

Calendar of events

2024-5-1

Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger

2024-4-30

Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method

2024-4-26

Study on spent fuel heatup during spent fuel pool complete loss of coolant accident

2024-4-26

Study on advection–dispersion behavior for simulation of ³H, ⁹⁹Tc, and ⁹⁰Sr transport in crushed sandstone of column experiments

2024-4-24

Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production

2024-4-19

Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators

2024-4-19

Frontmatter

2024-4-1

Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment

2024-3-29

Overview on GRS CFD activities related to containment applications

2024-3-29

Numerical simulation analysis of high-temperature bent sodium heat pipes

2024-3-26

Large-scale PANDA facility – radiation experiments and CFD calculations

2024-3-22

Calendar of events

2024-3-21

Analyses of the unavailability dynamics of emergency core cooling system

2024-3-20

CTAB modification bentonite for enhanced Re adsorption and diffusion suppression

2024-3-19

CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges

2024-3-19

The European GO-VIKING project on flow-induced vibrations: overview and current status

2024-3-15

Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant

2024-3-15

The 34th German CFD network of competence meeting: numerical 3D simulation of reactor primary cooling circuit and containment flows

2024-3-12

CFD simulation on droplet behaviour in post-dryout region

2024-3-8

Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor

2024-2-29

A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis

2024-2-28

Implementation of the preCICE coupling interface for AC²/ATHLET

2024-2-26

Coupled AC²-CFD simulations for a high-pressure core melt accident scenario

2024-2-23

Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code

2024-2-20

Generic flame extension model development based on machine learning for NPPs fire hazard analysis (FHA)

2024-2-19

Scaling factors for CANDU reactor waste: how reliable are they?

2024-2-16

Comparison of thermal hydraulic performance between horizontal and vertical steam generators in nuclear power plants

2024-2-1

Frontmatter

2024-2-1

Calendar of events

2024-2-1

The RADTRAD analysis methodology for the Fuel Handling Accident during the long-term shutdown period of Chinshan Nuclear Power Plant

2024-1-30