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Expert Group on Uncertainty Analysis in Modelling (EGUAM)

The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...

EGUAM Boiling water reactors Nuclear science Light water reactors WPRS Reactor physics Modelling and simulation Reactor physics Uncertainty quantification Uncertainty analysis Benchmark Pressurised water reactors …
Published date: 27 October 2021
Activity
Benchmark of the Modular High-Temperature Gas-Cooled Reactor-350 MW Core Design

Helium-cooled very high-temperature gas reactors are highlighted as a key technology with the potential to improve the competitiveness of nuclear energy within the Generation IV International Forum (...

Gas-cooled reactors Reactor physics
Published date: 20 September 2021
Activity
Physics of plutonium recycling

For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.

Reactor physics Plutonium Nuclear fuel cycle Reactor physics
Published date: 8 September 2021
Activity
Neutron noise analysis

Neutron noise analysis can be defined as the direct measurement of the kinetics of a nuclear core. This page describes some of the NEA's previous activities on neutron noise analysis in nuclear power...

Nuclear science Fast reactor Benchmark Reactor physics
Published date: 26 July 2021
Activity
Pebble Bed Modular Reactor (PBMR) Coupled Neutronics/Thermal-hydraulics Transients Benchmark - PBMR-400 Core Design

The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.

SMR Gas-cooled reactors Thermal hydraulics Verification Multiphysics Benchmark Reactor physics Multiphysics …
Published date: 26 July 2021
Activity
Technical Review Group for the International Assay Data of Spent Nuclear Fuel Database (TRG SFCOMPO)

The Technical Review Group (TRG) for the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO) lies under the direction of the Working Party on Nuclear Criticality Safety (WPNCS).

Criticality safety
Published date: 13 April 2021
Activity
Expert Group on Integral Experiments for Minor Actinide Management (EGIEMAM)

The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...

WPFC WPEC Nuclear science Experiments Actinides WPRS Reactor physics Integral experiments Minor actinides NSC Nuclear fuel cycle Fuel cycle physics and chemistry …
Published date: 5 March 2021
Activity
Sodium-cooled Fast Reactor (SFR) Benchmark Task Force

A sodium-cooled fast reactor (SFR) is a fast neutron reactor that uses molten sodium metal as a coolant. Sodium-cooled Fast Reactors (SFRs) are the most promising type of reactors to achieve Generati...

Reactor physics EGRPANS Fast reactor WPRS Reactor physics …
Published date: 4 February 2021
Activity
Expert Group on Reactor-based Plutonium Disposition (TFRPD)

The Expert Group on Reactor-based Plutonium Disposition (TFRPD) dealt with the status and trends of reactor physics, fuel performance and fuel cycle issues related to the disposition of weapons-grade...

Reactor physics Fuel studies Nuclear science Plutonium Reactor physics …
Published date: 16 December 2020
Activity
MeshTal Viewer

MeshTal Viewer is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.

Nuclear science Verification
Published date: 2 October 2020