Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...
The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....
This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...
This report defines the “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark of the PBMR-400 Core Design”. This chapter gives more information on the day-to-day management of ...
The main objective of the first phase of the Hydro...
Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...
The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.
Within the context of the Nuclear Energy Agency (NEA) Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) project, a series of tests were performed to resolve key thermal-hydraulic s...
The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialists’ meeting on transient thermal-hydraulics in water cooled nuclear reactors on 22-23 March 2022.
The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...
Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...
The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) 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 ...
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.
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 ...
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...
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...
The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...
The objective of the NEA THAI-3 project was to address open questions concerning the behaviour of hydrogen, iodine and aerosols under severe accident conditions in the containment of water cooled rea...
PANDA vessel assembly (construction phase, 1993), PSI.
The PANDA project is a follow-up of the HYMERES-2 project, and its general objective is to advance the knowledge on the containment of thermal...
The scope of the proposed project is therefore to perform practical exercises of demonstration of the SAPIUM approach.
View looking down onto the LOFT reactor
The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened int...
Multi-compartment THAI+ test facility, Becker Technologies GmbH.
In the wake of the OECD/NEA THAI project, conducted in three phases from 2007 until 2019, a new project, THAI Experiments on Mitigat...
Scheme of the PKL facility, Framatome GmbH.
The SESAR Thermal-hydraulics (SETH) Project began in 2001 and consisted of thermal-hydraulic experiments in support of accident management, which were ca...
Scheme of the THAI+ facility, Becker Technologies.
The experimental investigations carried out in the frame of the THAI (2007-2009), THAI-2 (2011-2014) and THAI-3 (2016-2019) projects contributed s...
Scheme of the ROSA LSTF facility, JAEA
The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...
View of the ATLAS experimental loop. KAERI, KoreaThe Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...
The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...
Scheme of the PSB-VVER facility, EREC
The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scal...
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...
The NEA ATLAS3 and NEA ETHARINUS projects organised a workshop on 7-9 November 2023.
Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...
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...
Under the guidance of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance,...