RESUMEN
The European as low as reasonably achievable(ALARA) network regularly organises workshops on topical issues in radiation protection (RP). The topic of the 20th workshop was: 'ALARA for interventional radiology (IR) and nuclear medicine (NM)'. The objective was to examine the challenges faced when applying the optimisation principle (ALARA) in IR and NM and to consider how ALARA could be better implemented for patient and staff exposures. This memorandum provides a synthesis of the workshop sessions, and recommendations coming from the working groups discussion. Parallels are drawn with the recommendations arising from the 13th EAN workshop on 'ALARA and the medical sector (2011)' to consider how the optimisation challenges in IR and NM have evolved over the past decade. Current levels of exposure are presented along with operational practice and the challenges and opportunities for improvement, both in monitoring and practice. Whilst RP challenges remain, the application of ALARA appears more established in IR compared with experiences reported in 2011. The application of ALARA to emerging technologies in the NM setting is in need of further development to ensure that RP is considered at all stages in the development process of new radiopharmaceuticals. Besides the obvious technical and operational aspects, the importance of education and training, human factors and broadly the RP 'culture' were deemed fundamental to the success of the application of ALARA and where further emphasis is needed. All concerned parties, medical physics experts (MPEs), radiation protection experts, clinical staff, manufacturers and regulators have a role to play in the application of ALARA and this is discussed in the memorandum. Many of the recommendations from the 13th EAN workshop remain applicable today and overlap with the recommendations arising from the 20th workshop. This should prompt attention given that the use of IR and the development of novel radiopharmaceuticals for NM is only anticipated to increase with time.
Asunto(s)
Medicina Nuclear , Protección Radiológica , Radiología Intervencionista , Humanos , Europa (Continente) , Exposición Profesional/prevención & controlRESUMEN
In September 2022, the International Commission on Radiological Protection (ICRP) organised a workshop in Estoril, Portugal, on the 'Review and Revision of the System of Radiological Protection: A Focus on Research Priorities'. The workshop, which was a side event of the European Radiation Protection Week, offered an opportunity to comment on a recent paper published by ICRP on areas of research to support the System of Radiological Protection. Altogether, about 150 individuals participated in the workshop. After the workshop, 16 of the 30 organisations in formal relations with ICRP provided written feedback. All participants and organisations followed ICRP's view that further research in various areas will offer additional support in improving the System in the short, medium, and long term. In general, it was emphasised that any research should be outcome-focused in that it should improve protection of people or the environment. Many research topics mentioned by the participants were in line with those already identified by ICRP in the paper noted above. In addition, further ideas were expressed such as, for example, that lessons learned during the COVID-19 pandemic with regards to the non-radiological social, economic and environment impacts, should be analysed for their usefulness to enhance radiological protection, and that current protection strategies and application of current radiological protection principles may need to be adapted to military scenarios like those observed recently during the military conflict in the Ukraine or the detonation of a nuclear weapon. On a broader perspective, it was discussed how radiation research and radiological protection can contribute towards the Sustainable Development Goals announced by the United Nations in 2015. This paper summarises the views expressed during the workshop and the major take home messages identified by ICRP.
RESUMEN
The Council Directive 2013/59/Euratom has introduced binding requirements for the management of radon in the workplace in Member States of the European Union. How does it work in practice? In 2021, the European ALARA Network created a working group on ALARA for Radon at Work with the objective of collecting and sharing experiences from the field. A survey was developed to detail each step of the national regulations for the control of radon and to describe case studies showing implementation. This article presents a qualitative analysis of the answers received from seven countries. There are no two similar national regulations and, at each step, different provisions, protocols, techniques etc are applicable or recommended. This diversity contributes to the richness of the results and can inform about interesting and good practices, where 'good' is defined by what is appropriate in the nationally and locally prevailing circumstances. All national regulations follow a graded approach, which is a key component for the implementation of the optimisation (ALARA) principle, yet several potential weak points that may be challenging to ALARA have been identified and are discussed, namely the radon risk assessment, the focus on numerical values, uncertainties in the measurement, how to obtain economically efficient remediation, and the interface with other regulations. Strengthening collaboration between risk prevention and radiation protection actors could help to provide and build expertise on radon management in the workplace, especially when exposure is managed as a planned exposure situation.
Asunto(s)
Protección Radiológica , Radón , Radón/análisis , Retroalimentación , Lugar de Trabajo , Unión EuropeaRESUMEN
The European ALARA Network regularly organises workshops on topical issues in radiation protection. The topic of the 18th workshop was 'ALARA for Decommissioning and Site Remediation'. The workshop was jointly organised with the ISOE Working Group on Decommissioning (ISOE WG-DECOM) and the French Atomic Alternatives Energy and Atomic Energy Commission (CEA). The main objective was to examine the conceptual and practical aspects of the implementation of the optimisation principle (or ALARA principle) in the 'nuclear' and 'non-nuclear' sectors and also for legacy sites. This memorandum presents a synthesis of the presentations and working groups discussion that took place. It also summaries the conclusions from former EAN workshops on the same topic (1997, 2006) to highlight the commonalities and the new topics. The theoretical scheme for applying the ALARA principle is illustrated by the various presentations of decommissioning and remediation (D&R) projects given at the workshop. The theoretical scheme includes, a starting point, the planning and implementation of the D&R strategy (including ALARA analysis) and the definition of an end-state. To lay down the foundations of ALARA, the initial characterisation should be comprehensive; considering not only radiation protection but other risks and circumstances both on site and off site. Decision-making is not trivial because many factors influence the D&R strategy and they can be addressed together using an holistic approach. A general methodology for such an approach in D&R was drafted by the participants. Techniques are apparently industrially mature and dosimetric data suggest that good control has been achieved, however experience shows that the D&R strategy will go through multiple adaptations along the way. The management of wastes remains a challenge in many cases as well as the decision on the end-state leading to question of what is a 'sustainable ALARA end-state?'.
RESUMEN
The European ALARA Network regularly organises workshops on topical issues in radiation protection. In light of the Fukushima accident, the most recent workshop questioned the application of the ALARA principle in emergency exposure situations. This memorandum presents the conclusions and recommendations of this workshop. One of the outcomes is that the process of optimisation in emergency exposure situations should be flexible enough to be able to modify or refine decisions over the course of an accident. In the urgent phase, decisions must be made in a very time-constrained environment, based on scarce, uncertain and sometimes unreliable information. In this phase, optimisation and protection strategies are therefore developed and applied on the basis of conservative assumptions or 'reasonably foreseeable worst-case scenario' which could lead to an overestimation of the consequences. In the intermediate phase, knowledge of the situation improves, and more time is available to make the decision. This is reflected by adopting a less conservative approach, and transitioning to a more appropriate optimisation adapted as effectively as possible to the various exposure situations. When the situation is eventually stabilized (transition phase), there is time to shape the measures taken previously to reflect local conditions in the affected territories. In every phase, consideration should be given to the stakeholders, so that their needs and requirements can be incorporated as effectively as possible.
Asunto(s)
Protección Radiológica , Urgencias Médicas , Europa (Continente) , Humanos , Exposición a la RadiaciónRESUMEN
The optimisation of the radiation protection for the workers in nuclear industry is an important part of the safety culture. The application of the ALARA concept (to keep exposures as low as reasonably achievable) is not always straightforward as it is influenced by the site geometry, source distribution and work organisation. A good ALARA pre-job study must therefore be performed and should contain predicted doses for the different suggested work scenarios and provide a quantitative basis to select between various alternative work scenarios for a specific operation. In order to handle this information, SCK-CEN developed the VISIPLAN 3D ALARA planning tool. The tool makes it possible to evaluate the dose due to external gamma exposure based on the simulation of work scenarios taking into account worker positions and subsequent geometry and source distribution changes in a three-dimensional environment.
Asunto(s)
Imagenología Tridimensional/métodos , Exposición Profesional/análisis , Monitoreo de Radiación/métodos , Protección Radiológica/métodos , Medición de Riesgo/métodos , Programas Informáticos , Interfaz Usuario-Computador , Arquitectura y Construcción de Instituciones de Salud/métodos , Rayos gamma , Factores de RiesgoRESUMEN
An assessment of the neutron field near the VENUS reactor is made in order to evaluate the neutron dose to the operators, particularly in an area near the reactor shielding and in the control room. Therefore, a full MCNPX model of the shielding geometry was developed. The source term used in the simulation is derived from a criticality calculation done beforehand. Calculations are compared to routine neutron dose rate measurements and show good agreement. The MCNPX model developed easily allows core adaptations in order to evaluate the effect of future core configuration on the neutron dose to the operators.