Modelling the atmospheric dispersion of radiotracers in small-scale, controlled detonations: validation of dispersion models using field test data.

A series of modelling exercises, based on field tests conducted in the Czech Republic, were carried out by the 'Urban' Working Groups as part of the International Atomic Energy Agency's Environmental Modelling for Radiation Safety II, Modelling and Data for Radiological Impact Assessment (MODARIA) I and MODARIA II international data compilation and model validation programmes. In the first two of these programmes, data from a series of field tests involving dispersion of a radiotracer,99mTc, from small-scale, controlled detonations were used in a comparison of model predictions with field measurements of deposition. In the third programme, data from a similar field test, involving dispersion of140La instead of99mTc, were used. Use of longer-lived140La as a radiotracer allowed a greater number of measurements to be made over a greater distance from the dispersion point and in more directions than was possible for the earlier tests involving shorter-lived99mTc. The modelling exercises included both intercomparison of model predictions from several participants and comparison of model predictions with the measured data. Several models (HotSpot, LASAIR, ADDAM/CSA-ERM, plus some research models) were used in the comparisons, which demonstrated the challenges of modelling dispersion of radionuclides from detonations and the need for appropriate meteorological measurements.

An updated strategic research agenda for the integration of radioecology in the european radiation protection research.

The ALLIANCE Strategic Research Agenda (SRA) for radioecology is a living document that defines a long-term vision (20 years) of the needs for, and implementation of, research in radioecology in Europe. The initial SRA, published in 2012, included consultation with a wide range of stakeholders (Hinton et al., 2013). This revised version is an update of the research strategy for identified research challenges, and includes a strategy to maintain and develop the associated required capacities for workforce (education and training) and research infrastructures and capabilities. Beyond radioecology, this SRA update constitutes a contribution to the implementation of a Joint Roadmap for radiation protection research in Europe (CONCERT, 2019a). This roadmap, established under the H2020 European Joint Programme CONCERT, provides a common and shared vision for radiation protection research, priority areas and strategic objectives for collaboration within a European radiation protection research programme to 2030 and beyond. Considering the advances made since the first SRA, this updated version presents research challenges and priorities including identified scientific issues that, when successfully resolved, have the potential to impact substantially and strengthen the system and/or practice of the overall radiation protection (game changers) in radioecology with regard to their integration into the global vision of European research in radiation protection. An additional aim of this paper is to encourage contribution from research communities, end users, decision makers and other stakeholders in the evaluation, further advancement and accomplishment of the identified priorities.

Opening Fukushima floodgates: Modelling 137Cs impact in marine biota.

A numerical model was applied to simulate the transport of 137Cs released with the waters which were used to cool Fukushima reactors. These stored waters will be released to the Pacific Ocean according to Japanese government plans. The radionuclide transport model is Lagrangian and includes radionuclide interactions with sediments and an integrated dynamic foodweb model for biota uptake. Calculations made from a conservative approach indicate that expected concentrations in sediments and marine fish would be orders of magnitude below those detected after Fukushima accident and also lower than those resulting from global fallout background.

Transport and dispersion of tritium from the radioactive water of the Fukushima Daiichi nuclear plant.

Japan recently announced plans to discharge over 1.2 million tons of radioactive water from the Fukushima Daiichi Nuclear Power Plant (FDNPP) into the Pacific Ocean. The contaminated water can poses a threat to marine ecosystems and human health. To estimate the impact of the plan, here, we developed a three-dimensional global model to track the transport and dispersion of tritium released from the radioactive water of the FDNPP. The pollution scenarios for four release durations (1 month, 1 year, 5 years, and 10 years) were simulated. The simulation results showed that for the release in short-duration scenarios (1 month and 1 year), the peak plume with high tritium concentration shifted with the currents and finally reached the northeastern Pacific. For the long-duration scenarios (5 years and 10 years), the peak plume of the contaminated water was confined to coastal regions east of Japan.

Development of an Assessment Method for Building Materials Under Euratom Scope.

In 2013, the European Commission published its basic safety standards for protection against the dangers arising from exposure to ionizing radiation (Council Directive 2013/59/Euratom)-also known as EU-BSS. As a result, the use of raw materials with potentially elevated activity concentrations such as fly ash, phosphogypsum, and slags will now fall under EU-BSS scope when applied in building materials. In light of this new policy, a variety of tools are available to assess compliance with the 1-mSv y reference level for building materials. At the heart of these tools is a gamma-spectrometric determination of the naturally occurring radionuclides Ra, Th, and K in the material of concern. As a large number of construction products contain a certain amount of the raw material that falls under the scope of the EU regulation, this policy will lead to substantial measurement of building materials that pose little radiation risk. For this reason, a method is developed to enable assessment against the 1-mSv value not on the basis of gamma-spectrometric analysis but rather based on the product's material composition. The proposed method prescribes a maximum permitted content of raw materials with potentially elevated activity concentrations in terms of a weight percentage of the end product, where the raw materials of concern are defined as those listed in Annex XIII of the EU-BSS. The permitted content is a function of the product's surface density. Therefore, a product with a low surface density of up to 25 kg m can consist of nearly 100% raw materials with potentially elevated activity concentrations, and this percentage drops to around 15% for products with a surface density of around 500 kg m. Building materials that comply with these requirements on product composition are exempt from testing, while products that do not comply must perform regular gamma-spectrometric analysis. A full validation and testing of the method is provided. In addition, the paper discusses issues relevant for regulatory implementation.