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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
News
Scientific issues and uncertainty analysis of nuclear reactor systems

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.

Reactor physics News brief Nuclear science EGPRS SINBAD WPRS Reactor physics …
Published date: 24 February 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
NEA Document
Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
Published date: 12 October 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
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 Nuclear science WPRS Reactor physics Multiphysics EGMUP Reactor physics Cogeneration NSC Gas-cooled reactors EGPRS Nuclear science Benchmark …
Published date: 18 January 2019
NEA Document
English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
Published date: 6 December 2017
NEA Document
MOx Depletion Calculation Benchmark
NEA/NSC/R(2016)3

In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...

English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
Published date: 14 June 2016
NEA Document
English Nuclear science Criticality WPNCS WPRS Multiphysics Reactor physics Multiphysics EGMUP Reactor physics Criticality safety NSC Nuclear science …
Published date: 23 February 2016
NEA Document
Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes
NEA/NSC/R(2015)9

Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Reactor physics Sodium-cooled reactor NSC EGPRS Nuclear science Benchmark …
Published date: 5 November 2015
NEA Document
International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume III: Departure from nucleate boiling
NEA/NSC/R(2015)7

The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
Published date: 2 October 2015
NEA Document
International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume II: Benchmark results of phase I Void distribution
NEA/NSC/R(2015)4

The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark …
Published date: 24 June 2015
NEA Document
Shielding Aspects of Accelerators, Target and Irradiation Facilities (SATIF-12)
NEA/NSC/R(2015)3

Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014

English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
Published date: 2 June 2015
Publications and Reports
Review of Integral Experiments for Minor Actinide Management

Spent nuclear fuel contains minor actinides (MAs) such as neptunium, americium and curium, which require careful management. This becomes even more important when mixed oxide (MOX) fuel is being used...

English Reactor physics Nuclear science EGPRS WPRS Nuclear science …
Published date: 17 February 2015
NEA Document
PBMR Coupled Neutronics/Thermal-Hydraulics Transient Benchmark: The PBMR-400 Core Design - Volume 1: The Benchmark Definition
NEA/NSC/DOC(2013)10

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 ...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics Reactor physics Multiphysics EGMUP Modelling and simulation Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
Published date: 19 June 2013
NEA Document
English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
Published date: 16 May 2013
NEA Document
Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Volume II: Specification and Support Data for the Core Cases (Phase II)
NEA/NSC/DOC(2012)11

The objective of the OECD LWR UAM activity is to establish an internationally accepted benchmark framework to compare, assess and further develop different uncertainty analysis methods associated wit...

English NSC EGRRS WPRS Uncertainty analysis Benchmark …
Published date: 24 May 2012
NEA Document
OECD/NRC Benchmark Based on NUPEC Pressurised Water Reactor Sub-channel and Bundle Tests (PSBT) - Volume I: Experimental database and final problem specifications
NEA/NSC/DOC(2012)1

Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...

English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
Published date: 4 January 2012
Publications and Reports
VVER-1000 Coolant Transient Benchmark - Phase 2 (V1000CT-2): Summary Results of Exercise 1 on Vessel Mixing Simulation

Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...

English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
Published date: 5 October 2010
Publications and Reports
NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark - Volume II: Uncertainty and Sensitivity Analyses of Void Distribution and Critical Power - Specification

This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...

English Nuclear science Light water reactors WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Modelling and simulation Reactor physics Verification and validation Validation Uncertainty analysis Nuclear science Benchmark …
Published date: 1 January 2010
Publications and Reports
VVER-1000 Coolant Transient Benchmark - Phase 1 Phase I (V1000CT-1), Volume 3: Summary Results of Exercise 2 on Coupled 3-D Kinetics/Core Thermal-hydraulics

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
Published date: 16 November 2007