Established to help fulfil the objectives of the Agency and the Nuclear Science Committee (NSC), the NSC Programme Review Group (PRG) formulates recommendations based on best practices to optimise ac...
Published date:
19 March 2024
Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...
Published date:
7 July 2006
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...
Published date:
1 January 2010
NEA/NSC/R(2020)6
In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...
Published date:
1 June 2021
NEA/NSC/R(2020)7
In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...
Published date:
2 December 2021
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark
Published date:
2 August 2022
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...
Published date:
4 January 2012
NEA/NSC/DOC(2003)1
21-22 January 2003, Barcelona, Spain
Published date:
1 May 2003
Published date:
10 December 2000
NEA/NSC/DOC(2002)15
6 October 2002, Seoul, Korea
Published date:
1 November 2002
NEA/NSC/DOC(2001)20
Paul Scherrer Institute, Villigen, Switzerland, 15-16 October 2001
Published date:
1 October 2001
NEA/NSC/DOC(2002)11
Rossendorf (Dresden), Germany, 28-30 May 2002
Published date:
29 July 2002
NEA/NEACRP/L(1991)333
A summary of the Sixth Symposium on Reactor Noise (SMORN VI), Gatlinburg, United States, 19-24 May 1991
Published date:
1 January 1991
Kick-off meeting preparation for the Framework for Irradiation Experiments (FIDES) Joint Experimental Programmes (JEEPs) - List of participants
Published date:
27 February 2020
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 ...
Published date:
19 June 2013
The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.
Published date:
26 July 2021
Published date:
20 July 2005
The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...
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23 March 2022
Published date:
11 January 2002
Published date:
20 October 2003
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26 June 2006
Published date:
20 February 2009
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18 December 2006
Published date:
10 September 2015
Published date:
1 January 1999
Published date:
7 February 2006
For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.
Published date:
8 September 2021
Attitudes towards plutonium management vary from country to country and from utility to utility: some regard plutonium as a liability and others as a valuable source of energy.
The purpose of this st...
Published date:
1 November 1995
The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors. There are in addition incentives to better utilise fuel by increasing the b...
Published date:
19 July 1995
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...
Published date:
17 November 2020
Studies on fast reactors have historically concentrated on their capability of using plutonium produced in thermal reactors as initial fuel, and subsequently their capacity to produce electricity whi...
Published date:
1 November 1995
The NEA has studied multiple recycling issues associated with various reactor systems fuelled with mixed-oxide (MOX) and published a series of computational physics benchmarks. This has led to improv...
Published date:
21 June 2007
Studies on fast reactors have historically concentrated on their capability to use plutonium produced in thermal reactors as initial fuel, and subsequently their capacity to produce electricity while...
Published date:
1 November 1996
Although the recycling of plutonium as thermal mixed-oxide (MOX) fuel in pressurised water reactors (PWRs) is now well-established on a commercial scale, many physics questions remain. The main quest...
Published date:
23 October 2002
The commercial recycling of plutonium as PUO2/UO2 mixed-oxide (MOX) fuel is an established practice in pressurised water reactors (PWRs) in several countries, the main motivation being the consumptio...
Published date:
10 March 2003
The NEA has studied multiple recycling issues associated with various reactor systems fuelled with mixed-oxide (MOX) and published a series of computational physics benchmarks. This has led to improv...
Published date:
21 June 2007
The decision to re-use plutonium generated in thermal reactors is a strategic one for a utility, and is closely tied to the spent fuel management strategy. One option is to reprocess the spent fuel i...
Published date:
3 November 2003
Published date:
29 September 2011
The OECD/NEA Task Force on Computing Radiation Dose and Modelling of Radiation-Induced Degradation of Reactor Components (TFRDD) launched two international blind intercomparison exercises to examine ...
Published date:
1 January 2000
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 ...
Published date:
1 January 1999
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....
Published date:
22 December 2000
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...
Published date:
22 November 2002
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...
Published date:
19 November 2003
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 ...
Published date:
2 August 2022
PWR MOX/UO2 Core Transient Benchmark
Published date:
7 December 2022
Published date:
29 December 2006
NEA/NSC/DOC(2015)9
Primary Radiation Damage in Materials – Review of Current Understanding and Proposed New Standard Displacement Damage Model to Incorporate in Cascade Defect Production Efficiency and Mixing Effects
Published date:
26 February 2015
NEA/NSC/DOC(2013)9
Workshop Proceedings, 10-12 December 2012
Published date:
25 February 2020
Proceedings of the Second Specialists' Meeting on Shielding Aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) at CERN, Geneva, Switzerland on 12-13 October 1995.
Published date:
4 March 2024
NEA/NSC/R(2020)3
The following report is issued by WPEC Subgroup 28, which builds upon the work of the previous Subgroup 20 for developing new methods for cross-section covariance evaluation. Subgroup 28 was tasked w...
Published date:
28 September 2020