NEA/CSNI/R(2003)12
Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003
Published date:
31 March 2003
An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.
Published date:
2 August 2022
The Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) is an international high-visibility benchmark for unce...
Published date:
30 September 2020
10 -
11 May 2007
Paris, France
Published date:
18 December 2020
1 -
3 June 2016
Villigen, Switzerland
Published date:
18 December 2020
10 -
12 May 2017
Erlangen, Germany
Published date:
18 December 2020
16 -
17 May 2018
Lucca, Italy
Published date:
18 December 2020
13 -
17 May 2019
Oak Ridge, United States
Published date:
18 December 2020
2 -
4 April 2008
Garching, Germany
Published date:
18 December 2020
29 April 2009 -
1 May 2009
University Park/State College, Pennsylvania, United States
Published date:
18 December 2020
13 -
15 April 2010
Pisa, Italy
Published date:
18 December 2020
13 -
15 April 2011
Stockholm, Sweden
Published date:
18 December 2020
9 -
11 May 2012
Karlsruhe, Germany
Published date:
18 December 2020
14 -
16 May 2014
Garching, Germany
Published date:
21 December 2020
20 -
22 May 2015
Madrid, Spain
Published date:
18 December 2020
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...
Published date:
25 April 2023
General view of the EREC test facility BC V-213, source: EREC
There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine...
Published date:
6 October 2023
Published date:
5 February 2001
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...
Published date:
27 October 2021
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...
Published date:
2 October 2015
Experimental facilities in nuclear energy are key to addressing safety issues. The recent loss of some critical infrastructure, from facilities to industry expertise, has therefore become a concern f...
Published date:
8 September 2021
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
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
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
Scheme of the PSB-VVER facility, EREC
The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scal...
Published date:
6 October 2023
NEA/CSNI/R(2017)6
For many years, extensive experimental investigations into the system response of pressurised water reactors (PWRs) under accident conditions have been being conducted at the large-scale Primärkreisl...
Published date:
17 January 2018
Published date:
1 January 1998
NEA/NSC/R(2022)1
There is significant international interest in the effects of temperature on criticality safety evaluations. Improved access to nuclear data, notably thermal scattering data S(α,β) for hydrogen in ic...
Published date:
2 November 2023
28 -
29 April 2006
Pisa, Italy
Published date:
18 December 2020
The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...
Published date:
2 August 2022
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...
Published date:
31 December 2003
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...
Published date:
30 June 2006
The United States and the Russian Federation have each agreed to dispose of 34 tonnes of weapons-grade plutonium that are beyond their defence needs. One effective way to dispose of this plutonium is...
Published date:
20 January 2006
NEA/CSNI/R(2021)2/ADD
PERSEO was built at SIET laboratory (Piacenza, Italy) to study a new passive decay heat removal system operating in natural circulation. The main innovation in PERSEO is the presence of two pools con...
Published date:
26 November 2024
