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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
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 Reactor physics Fuel studies Sodium-cooled reactor NSC Generation IV reactors Benchmark Reactor physics …
Published date: 5 November 2015
NEA Document
International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues: Results from Phase 1 on UOx Fuels
NEA/NSC/DOC(2013)1

The Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) was created in 2011 to perform specific tasks associated with reactor physics aspects of present and future nuclear power sy...

English NSC
Published date: 14 January 2013
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 NSC
Published date: 14 June 2016
NEA Document
3-D Radiation Transport Benchmarks for Simple Geometries with Void Region
NEA/NSC/DOC(2000)4

Several NEA Nuclear Science Committee (NSC) activities are concerned with the validation of computation methods and codes as applied to nuclear technology. One of the challenges has been and continue...

English Monte Carlo method Transport NSC Radiation shielding Benchmark Radiation transport and shielding …
Published date: 17 March 2000
Activity
WPMM Expert Group on Multi-scale Modelling of Fuels (EGM2F)

Under the guidance of the Nuclear Science Committee (NSC) and under the mandate of the Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems (WPMM), the objecti...

WPMM NSC Nuclear science Materials science EGM2F …
Published date: 5 March 2020
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 Modelling and simulation NSC Thermal hydraulics Benchmark Thermal hydraulics and mechanics …
Published date: 19 June 2013
NEA Document
Benchmarking the Accuracy of Solution of 3-Dimensional Transport Codes and Methods over a Range in Parameter Space
NEA/NSC/DOC(2007)1/1

Particle transport calculations in three-dimensional configurations are becoming prevalent in nuclear applications. This places a premium on determining the accuracy of numerical solutions to practic...

English Multi-physics simulations NSC Nuclear science Benchmark Multiphysics …
Published date: 23 February 2007
NEA Document
Benchmarking the Accuracy of Solution of 3-Dimensional Transport Codes and Methods over a Range in Parameter Space - Final Meeting held in conjunction with M&C-2009
NEA/NSC/DOC(2009)8

Saratoga Springs, New York, 6 May 2009 - Meeting summary

English Multi-physics simulations NSC Nuclear science Benchmark Multiphysics …
Published date: 11 May 2009
NEA Document
Summary of the Expert Group meeting on 3D Radiation Transport Benchmarks on Benchmarking the Accuracy of Solution of 3-Dimensional Transport Codes and Methods over a Range in Parameter Space
NEA/NSC/DOC(2007)8

Monterey, California, USA, 17 April 2007

English NSC
Published date: 15 May 2007