Benchmark set
Introduction
A number of benchmark examples are included in the OSCAR-5 package. These benchmarks serve as an excellent validation platform as well as practical examples of how to construct reactor models and create applications for various target codes with the OSCAR-5 reactor analysis platform. This document briefly outlines each benchmark model and describes the notable features illustrated in each model with regard to OSCAR-5 functionality as well as reactor modelling in general.
The benchmark set includes models for:
ETRR-2, Egypt Test and Research Reactor
IRR1, Israeli Research Reactor
MNR, McMaster Nuclear Reactor
OPAL, Open-Pool Australian Lightwater reactor
SAFARI-1, South Africa Fundamental Atomic Research Installation reactor
ETRR-2
The Egypt Test and Research Reactor, number 2, at the Nuclear Research Centre in Egypt.
ETRR-2 benchmark source
Part of the IAEA CRP 1496: Innovative Methods in Research Reactor Analysis – Benchmarking Against Experimental Data.
Also part of the followup IAEA CRP T12029: Benchmark of Computational Tools against Experimental Data on Fuel Burnup and Material Activation for Utilization, Operation and Safety Analysis of Research Reactors.
ETRR-2 facility overview
ETRR-2 is a 22 MW, open pool research reactor with light water as coolant and moderator and with beryllium as reflector. This reactor is an array of fuel assemblies, inter-assembly absorber plates inside guide-boxes, a double walled chimney and irradiation boxes. The grid pithc is 8.1cm x 8.1cm and the ex-core grid pitch is 7.87cm x 7.87cm.
There is a total of 29 fuel assemblies with plate type fuel of 19.7% enriched \(U_3O_8\). The 6 control blades are intra-assembly type with Ag-In-Cd absorber material.
ETRR-2 experimental description
Two categories of experimental data is available in this benchmark.
Control rod calibrations
Rod calibrations done on several commissioning cores with fresh fuel
Fuel burnup
Burnup over four cycles (with limited plant data available)
Discharge burnup of three fuel assemblies measured using gamma spectroscopy
ETRR-2 model description
“Provide a summary of the OSCAR-5 model description and link to the auto doc for ETRR-2.”
Notable features of ETRR-2 benchmark
There are several notable features for the ETRR-2 benchmark. These can be split into notable features of the ETRR-2 reactor, notable features of the benchmark and notable features used in OSCAR-5 to model this reactor and benchmark calculations.
Reactor features
Intra-assembly control rods
Customizable core and ex-core configuration
Benchmark features
Experiments done on commissioning cores with fresh fuel
Burnup measurements of three fuel assemblies
OSCAR-5 features
Customizing core and pool configurations for different cycles
Using the application drivers for rod calibration
IRR1
The Israeli Research Reactor, number 1, at the Soreq Nuclear Research Centre in Israel.
“This part of the documentation is still under construction.”
MNR
The McMaster Nuclear Reactor, at the McMaster University in Canada.
MNR benchmark source
Part of the IAEA CRP 1496: Innovative Methods in Research Reactor Analysis – Benchmarking Against Experimental Data.
MNR facitily overview
The MNR reactor is an open pool MTR type research reactor operating at 3 MW thermal power. The configurable grid consists of 9 x 6 positions and is loaded with 28 fuel assemblies, 6 intra-assembly control rods and graphite, lead and beryllium reflectors with in-core irradiation positions. There are 6 ex-core beam tubes as well as further ex-core irradiation facilities. The reactor is light water moderated and graphite reflected.
Fuel assemblies consist of LEU (19.75% enriched) \(U_3Si_2-Al\) material as well as one burnt HEU assembly. The 6 shim control rods have Ag-In-Cd absorber and the 1 regulating rod is made of stainless steel.
MNR experimental description
Four categories of experimental data is available in this benchmark.
Core change measurements
Rod worth measurements.
Reactivity change measurements (fuel movements and additions, irradiation vessel and capsule loading).
Radial flux wire mapping (in all fuel assemblies).
Burnup (21.9 MWd).
Axial flux wire experiment
Low power flux wire measurements in sample irradiation positions.
Simulated void experiment
Critical rod measurements during aluminium plate insertion into coolant channels of fuel assemblies.
Pool temperature experiment
Critical rod measurements during heating of primary system.
MNR model description
“Provide a summary of the OSCAR-5 model description and link to the auto doc for MNR.”
Notable features of MNR benchmark
There are several notable features for the MNR benchmark. These can be split into notable features of the MNR reactor, notable features of the benchmark and notable features used in OSCAR-5 to model this reactor and benchmark calculations.
Reactor features
Intra-assembly control rods
Large amounts of graphite and lead
High neutron leakage at two core sides
Curved fuel, graphite and beryllium assemblies
Benchmark features
Extensive set of neutronic experimental data
OSCAR-5 features
Modelling intra-assembly control rods
Modelling curved fuel and other assemblies
Importing an inventory from a previous OSCAR-4 model
Using advanced cOMPoSe features for albedo boundary conditions and lattice coloursets
OPAL
The Open-Pool Australian Lightwater reactor, at the Australian Nuclear Science and Technology Organisation (ANSTO) in Australia.
OPAL benchmark source
Part of the IAEA CRP 1496: Innovative Methods in Research Reactor Analysis – Benchmarking Against Experimental Data.
Also part of the followup IAEA CRP T12029: Benchmark of Computational Tools against Experimental Data on Fuel Burnup and Material Activation for Utilization, Operation and Safety Analysis of Research Reactors.
OPAL facitily overview
The OPAL reactor is a 20 MW open-pool type research reactor. The reactor is cooled and moderated with light water and reflected with heavy water. The compact core consists of 16 plate-type fuel assemblies arranged in a 4x4 grid, with four control blades and a central cruciform control blade inserted in between the assemblies. The heavy water reflector vessel surrounding the core is populated with beam tubes, irradiation facilities and a cold neutron source.
The fuel assemblies have 19.8% enriched \(U_3Si_2-Al\) material with burnable cadmium wires in the side plates of two of the three fuel types (three types with different uranium loading). The control blades have hafnium absorber material.
OPAL experimental description
Two categories of experimental data is available for this benchmark.
Control rod calibration experiments
Commissioning experiments on all rods
Operational data
Core-follow data for seven cycles, from commissioning core
Material activation experiment
Gold foil experiments
OPAL model description
“Provide a summary of the OSCAR-5 model and link to the auto doc for MNR.”
Notable features of OPAL benchmark
There are several notable features for the OPAL benchmark. These can be split into notable features of the OPAL reactor, notable features of the benchmark and notable features used in OSCAR-5 to model this reactor and benchmark calculations.
Reactor features
Compact core with high leakage
Heavy water reflector
Cold neutron source
Benchmark features
Control rod calibration data for a commissioning core
Core-follow plant data over an extensive burnup period
OSCAR-5 features
Modelling intra-assembly control blades
Modelling integrated burnable absorbers in fuel assemblies
Using the application drivers for rod calibration and core-follow calculations
Using advanced cOMPoSe features for fuel assembly segmentation and albedo boundary conditions
Modelling multi-cycle operation
SAFARI-1
The South Africa Fundamental Atomic Research Installation reactor, number 1, at the South African Nuclear Energy Corporation (Necsa) in South Africa.
SAFARI-1 benchmark source
Part of the IAEA CRP T12029: Benchmark of Computational Tools against Experimental Data on Fuel Burnup and Material Activation for Utilization, Operation and Safety Analysis of Research Reactors.
SAFARI-1 facitily overview
The SAFARI-1 reactor is a tank-in-pool type MTR reactor operating at 20 MW thermal. The configurable grid consists of 9 x 8 positions, hosting 26 fuel assemblies and 6 fuel follower-type control assemblies. Other in-core positions house beryllium, lead and aluminium reflectors and irradiation positions. Ex-core there are irradiation facilities and 7 beam tubes.
Fuel assemblies are LEU (19.75% enriched) with U 3 Si 2 -Al material. The control assemblies are follower-type with fuel assemblies attached to the bottom of each absorber section. The absorber sections consist of a cadmium box inside an aluminium frame.
SAFARI-1 experimental description
Two categories of experimental data is available for this benchmark.
Multi-cycle operational data
Operational history for 1 year, plant data in fine scale and averaged
Low power flux wire experiments at start of each (in all fuel and fuel follower assemblies)
Control rod calibration experiments for five cycles
Beryllium poison concentration estimates
Approximate fluence and spectra history over the lifetime of beryllium elements
Beryllium poison related spectral measurements at start of operational data
SAFARI-1 model description
“Provide a summary of the OSCAR-5 model and link to the auto doc for SAFARI.”
Notable features of SAFARI-1 benchmark
There are several notable features for the SAFARI-1 benchmark. These can be split into notable features of the SAFARI-1 reactor, notable features of the benchmark and notable features used in OSCAR-5 to model this reactor and benchmark calculations.
Reactor features
Follower control rods
High leakage at pool side of core
Highly heterogeneous core configuration
Benchmark features
Core-follow plant data over an extensive burnup period
Flux wire and control rod data over multiple cycles
Fresh beryllium loaded at start of operational time for benchmark
OSCAR-5 features
Modelling follower-type control rods
Importing an inventory for burnable materials
Importing a reactor model from MCNP
Using the application drivers for rod calibration, flux wire mapping and core-follow calculations
Modeling complicated rig movements
Modelling beryllium poison
Modelling multi-cycle operation
Calculating thermal-hydraulic feedback