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Activity
Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

Nuclear fuel Reactor physics Multi-physics simulations Fuel studies Light water reactors Thermal hydraulics WPRS Pressurised heavy water reactors Reactor physics Multiphysics …
Published date: 7 February 2023
Joint project
Primary Coolant Loop Test Facility (PKL) Project

PKL facility. Photo: FRAMATOME, Germany

The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...

Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
Published date: 20 December 2022
Joint project
Rod Bundle Heat Transfer (RBHT) Project

Photo: RBHT Test Facility. US NRC.

Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...

Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
Published date: 13 December 2022
Joint project
Experimental Thermal Hydraulics for Analysis, Research and Innovations in NUclear Safety (ETHARINUS) Project

PKL facility. Photo: FRAMATOME, Germany

The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenome...

Accident analysis and management Thermal hydraulics Nuclear safety research Accident management
Published date: 9 December 2022
Joint project
Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) Project

Units 1 and 2 End of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (4th October, 2011). Photo: Tokyo Electric Power Company Holdings

The Benchmark Study of the Acci...

Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
Published date: 25 November 2022
Joint project
Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project

View of the ATLAS experimental loop. KAERI, Korea

The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...

Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
Published date: 25 November 2022
NEA Document
Summary and Conclusions of the Joint PKL-ATLAS Workshop on Analytical Activities Related to the NEA PKL-4 and ATLAS-2 Projects
NEA/CSNI/R(2020)13

Since 2001, the NEA has supported the Senior Expert Group on Safety Research Thermal-hydraulics (SETH), the Primärkreislauf-Versuchsanlage - Primary Coolant Loop Test Facility (PKL), PKL-2 and PKL-3 ...

Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Accident management …
Published date: 23 November 2022
Activity
Thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)

High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists consists in a multi-staged code-to-code-to-data thermal hydraulics code validation...

Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 9 November 2022
Activity
Benchmark Based on NUPEC Pressurised Water Reactor (PWR) Subchannel and Bundle Tests (PSBT)

An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.

Reactor physics Nuclear science Thermal hydraulics Multiphysics Benchmark Reactor physics Pressurised water reactors Multiphysics …
Published date: 2 August 2022
Activity
Pressurised Water Reactor Main Steam-Line Break (MSLB) Benchmark

This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

Modelling and simulation Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics …
Published date: 2 August 2022