Science and Technology of Nuclear Installations

Boiling Heat Transfer and Critical Heat Flux Enhancement Using Electrophoretic Deposition of SiO₂ Nanofluid

Investigation of the Equivalent Test Condition for the Seismic Safety Assessment of a Spent Fuel Pool with regard to Sloshing Behavior

Impact of Strontium and Krypton Release from Ghana’s MNSR following a Conjectural Accident Scenario

A Fracture Criterion for Prediction of Fracture Initiation of Metal Materials at Various Stress States for Nuclear Waste Storage

Study on Performance of Mesoscopic Impactor Filters for Aerosol Removal

Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition

Blowout Accident Impact Analysis Method for the Siting of Offshore Floating Nuclear Power Plant in Offshore Oil Fields

Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

An Integral Numerical Analysis of Impact of a Commercial Aircraft on Nuclear Containment

Applicability of Pseudoprobabilistic Method of Liquefaction Hazard Assessment for Nuclear Power Plants at Diffuse Seismicity Sites

Fretting Wear and Fatigue Life Analysis of Fuel Bundles Subjected to Turbulent Axial Flow in CEFR

Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario

Benchmarking COMSOL Multiphysics Single-Subchannel Thermal-Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2019

Boiling Heat Transfer and Critical Heat Flux Enhancement Using Electrophoretic Deposition of SiO₂ Nanofluid

Investigation of the Equivalent Test Condition for the Seismic Safety Assessment of a Spent Fuel Pool with regard to Sloshing Behavior

Impact of Strontium and Krypton Release from Ghana’s MNSR following a Conjectural Accident Scenario

A Fracture Criterion for Prediction of Fracture Initiation of Metal Materials at Various Stress States for Nuclear Waste Storage

Study on Performance of Mesoscopic Impactor Filters for Aerosol Removal

Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition

Blowout Accident Impact Analysis Method for the Siting of Offshore Floating Nuclear Power Plant in Offshore Oil Fields

Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

An Integral Numerical Analysis of Impact of a Commercial Aircraft on Nuclear Containment

Applicability of Pseudoprobabilistic Method of Liquefaction Hazard Assessment for Nuclear Power Plants at Diffuse Seismicity Sites

Fretting Wear and Fatigue Life Analysis of Fuel Bundles Subjected to Turbulent Axial Flow in CEFR

Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario

Benchmarking COMSOL Multiphysics Single-Subchannel Thermal-Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2019

Boiling Heat Transfer and Critical Heat Flux Enhancement Using Electrophoretic Deposition of SiO2 Nanofluid

Investigation of the Equivalent Test Condition for the Seismic Safety Assessment of a Spent Fuel Pool with regard to Sloshing Behavior

Impact of Strontium and Krypton Release from Ghana’s MNSR following a Conjectural Accident Scenario

A Fracture Criterion for Prediction of Fracture Initiation of Metal Materials at Various Stress States for Nuclear Waste Storage

Study on Performance of Mesoscopic Impactor Filters for Aerosol Removal

Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly

Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition

Blowout Accident Impact Analysis Method for the Siting of Offshore Floating Nuclear Power Plant in Offshore Oil Fields

Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

An Integral Numerical Analysis of Impact of a Commercial Aircraft on Nuclear Containment

Applicability of Pseudoprobabilistic Method of Liquefaction Hazard Assessment for Nuclear Power Plants at Diffuse Seismicity Sites

Fretting Wear and Fatigue Life Analysis of Fuel Bundles Subjected to Turbulent Axial Flow in CEFR

Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario

Benchmarking COMSOL Multiphysics Single-Subchannel Thermal-Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data

Boiling Heat Transfer and Critical Heat Flux Enhancement Using Electrophoretic Deposition of SiO₂ Nanofluid