IRPhE primary documentation

Ongoing

Example of Dragon data in IRPHE-DRAGON-DPR

International Reactor Physics Benchmark Experiments (IRPhE) Project

Primary documentation and other benchmarks

Recently added primary documentation archives (Last update December 2008)

IRPHE/B&W-SS-LATTICE, Spectral Shift Reactor Lattice Experiments
IRPHE-JAPAN, Reactor Physics Experiments carried out in Japan
IRPHE/JOYO MK-II, JOYO MK-II core management and characteristics database
IRPhE/RRR-SEG, Reactor Physics Experiments from Fast-Thermal Coupled Facility
IRPHE-SNEAK, KFK SNEAK Fast Reactor Experiments, Primary Documentation
IRPhE/STEK, Reactor Physics Experiments from Fast-Thermal Coupled Facility
IRPHE-ZEBRA, AEEW Fast Reactor Experiments, Primary Documentation
IRPHE-DRAGON-DPR, OECD High Temperature Reactor Dragon Project, Primary Documents
IRPHE-HTR-ARCH-01, Archive of HTR Primary Documents
IRPHE/AVR, AVR High Temperature Reactor Experience, Archival Documentation
IRPHE-KNK-II-ARCHIVE, KNK-II fast reactor documents, power history and measured parameters
IRPhE/BERENICE, effective delayed neutron fraction measurements
IRPhE-TAPIRO-ARCHIVE, fast neutron source reactor primary documents, reactor physics experiments

Other benchmarks in reactor physics (coupled neutronics/thermal-hydraulics - coupling core-plant)

ZZ 3DLWRCT, 3-D LWR Rod Ejection and Rod Withdrawal Benchmarks
ZZ BFBT, OECD/NEA-US/NRC NUPEC BWR Full-size Fine-mesh Bundle Tests Benchmark
ZZ BWRSB-FORSMARKS, Stability Benchmark Data from BWR FORSMARKS 1 and 2
ZZ BWRSB-RINGHALS1, Stability Benchmark Data from BWR RINGHALS-1
ZZ BWRTT, BWR Turbine Trip Transient Benchmark Based on Peach-Bottom 2
ZZ PBMR-400: PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark
ZZ PWR-MSLB, PWR Main Steam-Line Break Benchmarks, Coupled Neutronics Thermal-Hydraulics
ZZ V1000CT-1 VVER-1000 Main Coolant Pump (MCP) Switching On Benchmark
ZZ WPPR Pu Recycling Benchmark Results
ZZ UAM-LWR Uncertainty Analysis in Modelling, Coupled Multi-physics and Multi-scale LWR analysis

Contact

Ian Hill

Related topics

Nuclear science

Reactor physics

Multiphysics

Download files

DragonReport index

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Activities

results

Database for ICSBEP (DICE)

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments (DICE) in 2001.

See

International Criticality Safety Benchmark Evaluation Project (ICSBEP)

The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allows criticality safety analysts to easily use the data to validate calculation tools and cross-section libraries.

See

International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE)

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 various nuclear facilities around the world.

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International Reactor Physics Handbook Database and Analysis Tool (IDAT)

The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook information. Selected information from each configuration was entered into IDAT, such as the measurements performed, benchmark values, calculated values and materials specifications of the benchmark. In many cases this is supplemented with calculated data such as neutron balance data, spectra data, k-eff nuclear data sensitivities, and spatial reaction rate plots.

See

IRPhE Technical Review Group

The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental data from nuclear facilities, worldwide.

Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nuclear power systems.

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