20 -
22 June 2023
NEA, Paris, France
Date: 20-22 June 2023
Place: OECD/NEA Headquarters
46, Quai Alphonse Le Gallo
92100 Boulogne-Billancourt (Paris) - FRANCE
Minimum enrollment: 8 participants
Maximum enrollment: 16 participan...
Published date:
10 March 2023
22 -
26 May 2023
NEA, Paris (France)
Place: OECD/NEA Headquarters in Paris, France
Minimum enrollment required: 12 participants
Course fee: 2300 EUR
Registration deadline: 7 April 2023
The training course will be taught in Engli...
Published date:
8 March 2023
3 -
7 April 2023
OECD Headquarters, Paris
Dates: 3-7 April, 2023
Place: OECD Headquarters in Paris, France
Minimum enrollment required: 12 participants
Course fee: 1000 EUR
This 4.5-day interactive course is intended to give students a thorough...
Published date:
27 January 2023
The 9th edition of the Computational Fluid Dynamics for Nuclear Reactor Safety workshop was hosted by Texas A&M University on 20-22 February 2023.
Published date:
23 March 2023
6 -
10 March 2023
Paris, France
This advanced course is designed for people who have experience in running MCNP Monte Carlo calculations, but who would like to advance their skills and develop greater depth of understanding of theo...
Published date:
13 January 2023
27 February 2023 -
3 March 2023
Paris, France
***The course is full***
This intermediate course is designed for people who have some experience in running MCNP Monte Carlo calculations, but who would like to refresh or advance their skills. Prov...
Published date:
13 January 2023
The 2021 edition can be downloaded online.
Published date:
22 November 2022
21 -
25 November 2022
NEA, Paris (France)
PHITS (Particle and Heavy Ion Transport code System) is a general purpose Monte Carlo particle transport simulation code developed under a collaboration between Japan Atomic Energy Agency (JAEA) and ...
Published date:
6 September 2022
14 -
18 November 2022
NEA, Paris (France)
This training course provides instruction on the use of the KENO-VI Monte Carlo code for criticality safety calculations and the MAVRIC (Monaco with Automated Variance Reduction using Importance Calc...
Published date:
13 September 2022
The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental dat...
Published date:
10 November 2022
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...
Published date:
10 November 2022
The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...
Published date:
9 November 2022
24 -
27 October 2022
Online training course
OpenMC is a community-developed Monte Carlo neutron and photon transport simulation code. It is capable of performing fixed source, k-eigenvalue and subcritical multiplication calculations on models ...
Published date:
23 September 2022
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
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:
5 July 2022
21 -
23 June 2022
NEA, Paris, France
FISPACT-II (currently at release version 5.0) is an enhanced multi-physics platform providing a wide variety of advanced simulation methods and employing the most up to date (TENDL-2019, ENDF/B-VIII....
Published date:
30 March 2022
Collected sources of primary documentation for reactor physics benchmarks.
Published date:
14 April 2022
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
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
Nuclear materials science investigates how corrosion, irradiation, thermal ageing and mechanical load may affect materials properties and potentially degrade their performance.
Published date:
10 March 2020
13 -
17 May 2019
Oak Ridge, United States
Published date:
18 December 2020
16 -
17 May 2018
Lucca, Italy
Published date:
18 December 2020
10 -
12 May 2017
Erlangen, Germany
Published date:
18 December 2020
1 -
3 June 2016
Villigen, Switzerland
Published date:
18 December 2020
20 -
22 May 2015
Madrid, Spain
Published date:
18 December 2020
14 -
16 May 2014
Garching, Germany
Published date:
21 December 2020
NEA/CSNI/R(2014)4
Following the CFD4NRS workshops held in Garching, Germany (September 2006), Grenoble, France (September 2008) and Washington D.C., USA (September 2010), this workshop, held in Daejeon, Korea on 10-12...
Published date:
14 February 2014
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
NEA/CSNI/R(2013)1
The OECD/NEA ROSA Project was performed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety by using the ROSA/LSTF of JAEA for 4 years from April 2005. In pa...
Published date:
30 April 2013
9 -
11 May 2012
Karlsruhe, Germany
Published date:
18 December 2020
13 -
15 April 2011
Stockholm, Sweden
Published date:
18 December 2020
11 -
12 April 2011
Royal Institute of Technology, Stockholm, Sweden
Published date:
9 November 2020
13 -
15 April 2010
Pisa, Italy
Published date:
18 December 2020
12 -
13 April 2010
University of Pisa, Italy
Published date:
9 November 2020
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
29 April 2009 -
1 May 2009
University Park/State College, Pennsylvania, United States
Published date:
18 December 2020
27 -
28 April 2009
Pennsylvania State University (PSU), United States
Published date:
9 November 2020
NEA/CSNI/R(2008)6/VOL3
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2008)6/VOL2
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2008)6/VOL1
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
2 -
4 April 2008
Garching, Germany
Published date:
18 December 2020
10 -
11 May 2007
Paris, France
Published date:
18 December 2020
In the deep disposal of radioactive waste, the presence of several barriers serving complementary safety functions enhances confidence that the waste will be isolated and contained to protect human h...
Published date:
16 February 2007
28 -
29 April 2006
Pisa, Italy
Published date:
18 December 2020
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
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 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
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
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 Probabilistic System Assessment Group (PSAG) (formerly the Probabilistic System Assessment Code (PSAC) User Group was established in 1985 by the Nuclear Energy Agency (NEA) of the Organisation fo...
Published date:
1 January 1987
