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Event
Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 10 (LWR-UAM-10)
1 - 3 June 2016
Villigen, Switzerland
Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
Published date: 18 December 2020
Event
Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 11 (LWR-UAM-11)
10 - 12 May 2017
Erlangen, Germany
Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
Published date: 18 December 2020
Event
Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 12 (LWR-UAM-12)
16 - 17 May 2018
Lucca, Italy
Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
Published date: 18 December 2020
NEA Document
A Code to Code Benchmark for High-Temperature Gas-Cooled Reactor Fuel Element Depletion
NEA/NSC/R(2019)1

The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

English Nuclear fuel Fuel studies Generation IV reactors Reactor physics Multiphysics Reactor physics Cogeneration NSC Gas-cooled reactors Benchmark …
Published date: 18 January 2019
Event
Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 13 (LWR-UAM-13)
13 - 17 May 2019
Oak Ridge, United States
Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
Published date: 18 December 2020
News
ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

News brief Criticality safety Nuclear science Reactor physics
Published date: 18 November 2019
Subtopic
Reactor physics

Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.

Reactor physics Verification and validation Fast reactor Benchmark Advanced reactors Reactor physics …
Published date: 2 December 2019
Other
EGUAM Related Benchmarks Completed

Chart showing the benchmarks related to EGUAM that have now been completed.

Reactor physics Uncertainty analysis Benchmark Reactor physics
Published date: 13 December 2019
Other
EGUAM Current Activities

Current activities related to EGUAM.

Reactor physics Sodium-cooled reactor Light water reactors Uncertainty analysis Benchmark Reactor physics …
Published date: 13 December 2019
Activity
Expert Group on Radiation Transport and Shielding (EGRTS)

Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current ...

EGRTS State-of-the-art report Benchmark Reactor physics
Published date: 3 March 2020
News
Scientific issues of nuclear reactor systems

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

Reactor physics News brief Nuclear science Reactor physics
Published date: 4 March 2020
Activity
Expert Group on Improvement of Integral Experiments Data for Minor Actinide Management (EGIEMAM-II)

The expert group works in co-ordination with Working Party on Scientific Issues of Reactor Systems (WPRS) [including the IRPhE Project], Working Party on Scientific Issues of the Fuel Cycle (WPFC) an...

WPEC NSC Nuclear science Experiments Actinides WPRS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry Integral experiments Minor actinides …
Published date: 9 March 2020
Activity
DATabase for IFpe (DATIF)

DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...

Nuclear fuel Physics Fuel studies NSC EGRFP Databases Ancillary data Reactor physics Integral experiments …
Published date: 23 July 2020
Activity
International Fuel Performance Experiments (IFPE) database

International Fuel Performance Experiments (IFPE) is the public domain database on nuclear fuel performance experiments for the purpose of code development and validation.

Fuel studies Nuclear science Experiments EGRPF Databases Ancillary data Reactor physics …
Published date: 19 August 2020
Activity
IRPhE Handbook 2019 Edition - Contents

IRPhE Handbook 2019 Edition - Contents

Verification and validation Verification Uncertainty quantification Uncertainty analysis Reactor physics …
Published date: 30 September 2020
Subtopic
Multiphysics

Multiphysics are simulations using computer applications or software to couple multiple physical events in order to predict or validate the physical real-world outcome.

Multi-physics simulations Nuclear science Benchmark Reactor physics Multiphysics …
Published date: 16 October 2020
Activity
Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM)

The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....

Sodium-cooled reactor Verification Fast reactor Benchmark Reactor physics …
Published date: 6 November 2020
Publications and Reports
Physics of Plutonium Recycling - Volume III

The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors, requiring an increase in the total loading necessary in mixed plutonium-ura...

English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
Published date: 17 November 2020
Other
Third Information Exchange Meeting on the Nuclear Production of Hydrogen - Programme

Third Information Exchange Meeting on the Nuclear Production of Hydrogen including Second HTTR Workshop, Japan Atomic Energy Agency (JAEA), Oarai, Japan, 5 - 7 October 2005 - Programme

Nuclear science Multiphysics Reactor physics
Published date: 24 November 2020
Other
First Information Exchange Meeting on the Nuclear Production of Hydrogen - Programme and abstracts

First Information Exchange Meeting on the Nuclear Production of Hydrogen, Paris, France, 2-3 October, 2000 - Programme and abstracts

Nuclear science Multiphysics Reactor physics
Published date: 24 November 2020