The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP), International Reactor Physics Experiments Evaluation Project (IRPhEP), International Assay Data of Spent Nuclear Fuel D...
Under the guidance of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performanc...
Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.
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 nu...
The International School on Simulation of Nuclear Reactor Systems (SINUS) provides hybrid, hands-on-training encompassing multiphysics modelling and simulation (M&S) and associated validation, verifi...
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 ...
The International School on Simulation of Nuclear Reactor Systems took place in Italy.
WPRS organised annual benchmarks workshop.
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...
The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...
International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.
The NEA Expert Group on the Physics of Reactor Systems (EGPRS) organised a one-day workshop to foster exchanges among radiation transport simulation developers. The workshop aimed to facilitate excha...
The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) was co-located with the BEPU 2024 conference and hosted by N.IN.E. (Nuclear...
The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.
The meetings took place in April 2024 in the United States.
The NEA organised the second International School on Simulation of Nuclear Reactor Systems (SINUS) on the topic of Reactor single- and multi-physics simulations based on Light Water Reactor (LWR) Unc...
The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiments Evaluation Project (IRPhEP) Technical Review Groups, and the Shielding Int...
Proceedings of the Second Specialists' Meeting on Shielding Aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) at CERN, Geneva, Switzerland on 12-13 October 1995.
Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, an...
Under the guidance of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance,...
