Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on Uncertainty Analysis in Modelling (EGUAM). The CANDU Owners Group (COG) provided full-scale experimental data for a 28-element CANDU fuel assembly including pressure drop and detailed pin temperatures for single-phase and boiling conditions.
The purpose of the benchmark is to:
A unique aspect of these data is the traversing thermocouples which provide axial and azimuthal sheath temperatures along every fuel element for both pre= and post-CHF conditions. A wide range of test conditions (inlet pressure, mass flows and inlet temperatures) will be provided to participants along with the temperature scans, CHF location and power, and post-dryout sheath temperatures. Similar to the NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Tests (BFBT) and NUPEC Pressurised Water Reactor (PWR) Subchannel and Bundle Tests (PSBT) benchmarks, the complete set of data will be made available to participants after completion of the benchmark.
NEA: O. Buss
McMaster University Co-ordinator: D.R. Novog
Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of present and future nuclear power systems.
The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests and of numerical predictions of the Thermal Hydraulic Out of Reactor Safety (THORS) integral effect tests and comparison to experimental results.
The Working Group on the Analysis and Management of Accidents (WGAMA) focuses on the NEA activities related to potential design-basis and beyond design-basis accidents in nuclear reactors and related technologies. The accident progression includes in-vessel and ex-vessel phenomena involving system thermal-hydraulics, core damage and relocation, release and transport of radioactive materials and their physical-chemical behaviour, combustible gas generation, distribution and combustion, and molten core-concrete/structure interactions. The WGAMA also works on the safety aspects of existing nuclear reactors and related technologies as well as emerging challenges of evolutionary and innovative reactor designs and nuclear technologies, including small modular reactors. Group's priorities are based on established criteria of the Committee on the Safety of Nuclear Installations (CSNI) and in particular on safety significance and risk and uncertainty considerations.
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.