Radiation shielding is a protective shield that is inserted betweeen a source of ionising radiation and the object to protect to reduce the amount of damage that can happen to delicate or biological materials, particularly during transport. The wall design of the protective shield must have adequate thickness and meet safety criteria.
Nuclear, accelerator and fusion systems require complex calculations of shielding and dosimetry. Often these problems are sufficiently complex to require advanced analytical techniques to supplement Monte Carlo methods. The calculations impact key aspects of facilities, from the dose recieved by workers to the fluence load on the pressure vessel and internals.
A community of experts has been formed within the Expert Group on Physics of Reactor Systems (EGPRS) to advance a wide range of steady-state and transient radiation transport, accelerator, shielding and fusion predictions. The predictions are underpinned by experimental data contained in the SINBAD database, overseen by the EGPRS in close collaboration with Radiation Safety Information Computational Center (RSICC). The group provides a state-of-the-art best estimate and uncertainty analysis for many types of reactor systems.
Under the EGPRS, NEA activities represent the state-of-the-art in international radiation transport activities, some of which can be found below.
Additionally, the group publishes expert guidance in the domain of radiation transport and shielding. The work conducted within EGPRS has led to numerous conference and journal publications, in addition to the NEA technical reports published.
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) will perform specific tasks associated with reactor physics aspects of present and future nuclear power systems.
Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current and future nuclear systems and accelerator-based irradiation facilities.
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 Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) deals with the various aspects of the modelling and design of accelerator shield systems and radiation facilities.
Under the guidance of the Nuclear Science Committee (NSC) the Working Party on Scientific Issues of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nuclear power systems. The Working Party also studies the uncertainties associated with modelling of these phenomena, particularly the modelling of reactor transient events.
WPEC Subgroup 47 (SG47) works in close coordination with other NEA activities such as WPRS Expert Group on Radiation Transport and Shielding (EGRTS), WPEC SG45, SG46, Collaborative International Evaluated Library Organisation (CIELO) Pilot Project and the JEFF project, where the work could be used to guide the evaluations. Feedback from these groups on the specific needs and the use of Shielding Integral Benchmark Archive and Database (SINBAD) data is expected. SINBAD evaluation work shall be tightly coordinated with the interest of SG46 on Efficient and Effective Use of Integral Experiments for Nuclear Data Validation. Past experience in integral benchmark evaluations from the International Criticality Safety Benchmark Evaluation Project (ICSBEP), the International Reactor Physics Experiment Evaluation (IRPhE) Project and SINBAD will be valuable.