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NEA Document
Overview of SMORN-VI: Summary of the Sixth Symposium on Reactor Noise (SMORN VI)
NEA/NEACRP/L(1991)333

A summary of the Sixth Symposium on Reactor Noise (SMORN VI), Gatlinburg, United States, 19-24 May 1991

English Reactor physics NSC Nuclear science Nuclear science …
Published date: 1 January 1991
Publications and Reports
Very High Burn-ups in Light Water Reactors

Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

English Nuclear fuel Reactor physics Fuel studies Nuclear science Light water reactors Nuclear science Reactor physics …
Published date: 22 August 2006
Publications and Reports
VVER-1000 MOX Core Computational Benchmark

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...

English Modelling and simulation Reactor physics Nuclear science Nuclear science Benchmark Pressurised water reactors …
Published date: 20 January 2006
Publications and Reports
NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark

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...

English Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Reactor physics Multiphysics …
Published date: 7 July 2006
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
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
NEA Document
English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
Published date: 8 December 2021
NEA Document
Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-14)
NEA/NSC/R(2021)2

Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

English Nuclear science Radiation shielding WPRS Proceedings Reactor physics Reactor physics NSC EGPRS Nuclear science …
Published date: 16 December 2021
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
NEA Document
English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
Published date: 16 May 2013
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
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
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
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
NEA Document
NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume IV: Results of Phase II on Pressure Drop and Critical Power
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...

English Boiling water reactors Nuclear science Nuclear safety WPRS EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
Published date: 2 December 2021
NEA Document
NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume III: Results of Phase I on Void Distribution
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...

English Boiling water reactors Nuclear science Nuclear safety WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
Published date: 1 June 2021
NEA Document
Benchmark Specifications for the Fluoride-salt High-temperature Reactor (FHR) Reactor Physics Calculations
NEA/NSC/R(2020)5

This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...

Reactor physics Nuclear science EGPRS Verification WPRS Nuclear science Reactor physics …
Published date: 4 June 2021
NEA Document
Coupled Neutronic/Thermal-Fluid Benchmark of the MHTGR-350 MW Core Design: Results for the Lattice Physics Exercises
NEA/NSC/R(2019)6

The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...

English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics EGMUP Reactor physics NSC EGPRS Nuclear science …
Published date: 18 November 2021
NEA Document
Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
Published date: 12 October 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