Science and Technology of Nuclear Installations

Improved Modelling and Assessment of the Performance of Firefighting Means in the Frame of a Fire PSA

A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit

Scenario Grouping and Classification Methodology for Postprocessing of Data Generated by Integrated Deterministic-Probabilistic Safety Analysis

An Enhanced Preventive Maintenance Optimization Model Based on a Three-Stage Failure Process

Safety Assessment of Nuclear Power Plants for Liquefaction Consequences

Probabilistic Dynamics for Integrated Analysis of Accident Sequences considering Uncertain Events

Demonstration of Emulator-Based Bayesian Calibration of Safety Analysis Codes: Theory and Formulation

Delayed Station Blackout Event and Nuclear Safety

Risk-Based Clustering for Near Misses Identification in Integrated Deterministic and Probabilistic Safety Analysis

Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

Properties of Neutron Noise Induced by Localized Perturbations in an SFR

Full Scope Modeling and Analysis on the Secondary Circuit of Chinese Large-Capacity Advanced PWR Based on RELAP5 Code

Analysis of Wetting Characteristics on Microstructured Hydrophobic Surfaces for the Passive Containment Cooling System

Multilayered Pipe Cutting Test for Remote Handling Maintenance

Science and Technology of Nuclear Installations

Table of Contents

Table of Contents: 2015

Improved Modelling and Assessment of the Performance of Firefighting Means in the Frame of a Fire PSA

A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit

Scenario Grouping and Classification Methodology for Postprocessing of Data Generated by Integrated Deterministic-Probabilistic Safety Analysis

An Enhanced Preventive Maintenance Optimization Model Based on a Three-Stage Failure Process

Safety Assessment of Nuclear Power Plants for Liquefaction Consequences

Probabilistic Dynamics for Integrated Analysis of Accident Sequences considering Uncertain Events

Demonstration of Emulator-Based Bayesian Calibration of Safety Analysis Codes: Theory and Formulation

Delayed Station Blackout Event and Nuclear Safety

Risk-Based Clustering for Near Misses Identification in Integrated Deterministic and Probabilistic Safety Analysis

Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

Properties of Neutron Noise Induced by Localized Perturbations in an SFR

Full Scope Modeling and Analysis on the Secondary Circuit of Chinese Large-Capacity Advanced PWR Based on RELAP5 Code

Analysis of Wetting Characteristics on Microstructured Hydrophobic Surfaces for the Passive Containment Cooling System

Multilayered Pipe Cutting Test for Remote Handling Maintenance