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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 Nuclear science WPRS Reactor physics Multiphysics EGMUP Reactor physics Cogeneration NSC Gas-cooled reactors EGPRS Nuclear science Benchmark …
Published date: 18 January 2019
NEA Document
Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
Published date: 12 October 2020
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
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
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
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
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
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
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
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