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Burn-up credit and nuclear criticality safety

Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.

Criticality safety NSC Nuclear science Criticality WPNCS …
Published date: 11 September 2023
Activity
Working Party on International Nuclear Data Evaluation Co-operation (WPEC)

The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countrie...

NSC Nuclear science Nuclear data
Published date: 28 August 2023
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 of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...

Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
Published date: 19 July 2023
Activity
Lead-cooled Fast Reactor Benchmark (LFR)

Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

Generation IV reactors Verification and validation Verification Validation Liquid metal reactors Benchmark Reactor physics …
Published date: 9 June 2023
Activity
Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM)

Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM) addresses materials science aspects of nuclea...

Nuclear fuel Material science Structural materials NSC Nuclear science Materials science WPFM Nuclear science Accident tolerant fuels …
Published date: 1 June 2023
Activity
Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM)

The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...

Modelling and simulation Reactor physics Light water reactors Verification and validation Validation Uncertainty quantification Uncertainty analysis Benchmark Reactor physics Pressurised water reactors …
Published date: 25 April 2023
Activity
DATabase for IFpe (DATIF)

Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...

Nuclear fuel Physics Fuel studies NSC EGRFP Databases Ancillary data Reactor physics Integral experiments …
Published date: 12 April 2023
Activity
Expert Group on Reactor Fuel Performance (EGRFP)

Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...

Nuclear fuel Reactor physics EGRFP Reactor physics
Published date: 8 March 2023
Activity
Burst Fission Gas Release (FGR) Benchmark of the Expert Group on Reactor Fuel Performance (EGRFP)

This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).

Nuclear science Validation EGRPF WPRS Benchmark Reactor fuel performance …
Published date: 7 March 2023
Activity
Expert Group on Fuel Materials (EGFM)

Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Fuel Materials (EGFM) focuses on materials science aspects of...

Nuclear fuel Material science NSC Nuclear science Materials science WPFM Nuclear science Accident tolerant fuels …
Published date: 3 March 2023