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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
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
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
NEA Document
English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
Published date: 6 December 2017
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 Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
Published date: 14 June 2016