Periodic Reporting for period 1 - ANSELMUS (Advanced Nuclear Safety Evaluation of Liquid Metal Using Systems)
Période du rapport: 2022-09-01 au 2024-02-29
The central objective of the ANSELMUS project is to support the development and deployment of heavy metal cooled advanced nuclear systems in Europe with a focus on MYRRHA and ALFRED. The project is split into five technical work packages, each with their own objectives. Firstly, we work on a safety evaluation of the two systems via a PIRT (phenomena identification and ranking table). In addition, we do a numerical and experimental assessment of the safety of the fuel bundle, a validation of the safety performance of essential system components and work on the development of a non-destructive test-based reactors safety monitoring and vessel inspection. Next to the pure technical work, the project will also assess the social impact of heavy liquid metal systems by looking at the integration into a low-carbon energy systems and by addressing social and ethical considerations regarding the safety of advanced nuclear technologies. Finally, ANSELMUS will also work on education and training of nuclear scientists.
During the first 18 months of the project, months, the partners defined the reference technologies and scenarios for the PIRT analysis in WP1 together with the methodologies to be used specifying figures of merit, ranking methodology and list of physical phenomena of interest. The PIRT was also carried out for the first time by the partners, the result of which will be discussed in a series of dedicated in-person and on-line meetings. In parallel, numerical analyses were started in support the PIRT, that study some physical phenomena considered critical for the reference transients in more detail.
The second work package addresses safety aspects for both grid-spaced and wire-spaced fuel bundle designs. For the former, we decided to move the experiment on the deformed bundle to the NACIE loop at ENEA to avoid risks associated with the transfer of the power source although it caused small but manageable delays. This experiment has been supported by feasibility simulations and a pre-test benchmark is in progress. The wire-wrapped fuel assembly are being designed as well. Here, the required pre-test simulations have been identified and will be executed in the upcoming months. Finally, we also collected an extensive database of wire-wrapped fuel assembly experiments available from open literature suitable for CFD validation.
Significant progress was also made in the preparation of all experimental activities in devoted to the tests of key safety components. A detailed design of a new test section that is representative of the MYRRHA safety rod and will be used in the COMPLOT loop at SCK CEN was completed. At RATEN, we made the design, and started the construction a new facility for testing gas transport in liquid metals (figure 1). Furthermore, the NACIE loop was refurbished for tests with an oxygen control system while a cold trap system for oxygen removal has been installed in the MEXICO facility. Finally, numerical simulations were done, on the one hand to provide pre-test support to the experiments, and on the other hand to yield relevant background information for the design of failed-fuel-pin detection system.
In the work programme on the development of non-destructive testing for safety monitoring, initially three main lines were followed. Firstly, we investigated the existing normative/standard framework as applied to light water reactors (LWR) to understand to what extent it can be used for a heavy liquid metal -cooled reactor, and to identify potential gaps. Secondly, we enlarged the scope of the survey for the supply of possible high-temperature Ultrasound (US) sensors was enlarged, following limited success with the initial contacts. Developers have been also added to the list of new contacts. Finally, the design of the new experimental facility meant for testing US sensors at high temperatures above 350°C has started, leveraging the experience of analogous experiments made in the PASCAL project, albeit at lower temperatures.
In the fifth work package on the social impact of heavy liquid metal systems we investigated the possible balance of plant configurations for integrating a molten salts thermal storage system and cogeneration of hydrogen system for ALFRED demonstrator, with the main objective of identifying the key aspects of each technological solution. Two technologies, a molten salts thermal storage system and a High Temperature Steam Electrolysis hydrogen production system, were assessed. The heat and mass balance calculations for the water-steam cycle of ALFRED plant and its integration with the two technologies assessed were obtained. Several designs were analyzed, adapted for different degrees of electric and thermal energy outputs assessing the main performance parameters. The sizing parameters of the main equipment for each configuration was also performed. On the basis of this work, we identified the main input parameter needed to start the economic analysis foreseen in the remainder of the project.
In our efforts addressing social and ethical considerations regarding the safety of advanced nuclear technologies, three activities were completed to foster sociotechnical integration at SCK CEN in Belgium and at RATEN in Romania: an individual reflection exercise, the Socio-Technical Integration (STIR) and a workshop (figure 2). Researchers from the ANSELMUS technical teams have done an individual reflection exercise on Responsible Research and Innovation (RRI) and have filled the survey to make the results available to social scientists. Secondly, they participated in a STIR exercise, and reflected upon societal and ethical aspects in their work by creating regular interaction between them and social scientists. For the workshops, Belgian and Romanian technical researchers were moderated by the social scientists, to explore critical facets on RRI using the “Imagine RRI” card game and to obtain input for the preparation of the World Café events that are planned for the next period.
Finally in the work package on education, dissemination, exploitation and data management, the procedures for the latter three during the ANSELMUS project have been defined. The project website (www.anselmus.eu) is now live and populated with the project's information. The first newsletter of the project has been published and the first educational event, i.e. the heavy metal summer school (figure3) has taken place at SCK CEN.
The second work package addresses safety aspects for both grid-spaced and wire-spaced fuel bundle designs. For the former, we decided to move the experiment on the deformed bundle to the NACIE loop at ENEA to avoid risks associated with the transfer of the power source although it caused small but manageable delays. This experiment has been supported by feasibility simulations and a pre-test benchmark is in progress. The wire-wrapped fuel assembly are being designed as well. Here, the required pre-test simulations have been identified and will be executed in the upcoming months. Finally, we also collected an extensive database of wire-wrapped fuel assembly experiments available from open literature suitable for CFD validation.
Significant progress was also made in the preparation of all experimental activities in devoted to the tests of key safety components. A detailed design of a new test section that is representative of the MYRRHA safety rod and will be used in the COMPLOT loop at SCK CEN was completed. At RATEN, we made the design, and started the construction a new facility for testing gas transport in liquid metals (figure 1). Furthermore, the NACIE loop was refurbished for tests with an oxygen control system while a cold trap system for oxygen removal has been installed in the MEXICO facility. Finally, numerical simulations were done, on the one hand to provide pre-test support to the experiments, and on the other hand to yield relevant background information for the design of failed-fuel-pin detection system.
In the work programme on the development of non-destructive testing for safety monitoring, initially three main lines were followed. Firstly, we investigated the existing normative/standard framework as applied to light water reactors (LWR) to understand to what extent it can be used for a heavy liquid metal -cooled reactor, and to identify potential gaps. Secondly, we enlarged the scope of the survey for the supply of possible high-temperature Ultrasound (US) sensors was enlarged, following limited success with the initial contacts. Developers have been also added to the list of new contacts. Finally, the design of the new experimental facility meant for testing US sensors at high temperatures above 350°C has started, leveraging the experience of analogous experiments made in the PASCAL project, albeit at lower temperatures.
In the fifth work package on the social impact of heavy liquid metal systems we investigated the possible balance of plant configurations for integrating a molten salts thermal storage system and cogeneration of hydrogen system for ALFRED demonstrator, with the main objective of identifying the key aspects of each technological solution. Two technologies, a molten salts thermal storage system and a High Temperature Steam Electrolysis hydrogen production system, were assessed. The heat and mass balance calculations for the water-steam cycle of ALFRED plant and its integration with the two technologies assessed were obtained. Several designs were analyzed, adapted for different degrees of electric and thermal energy outputs assessing the main performance parameters. The sizing parameters of the main equipment for each configuration was also performed. On the basis of this work, we identified the main input parameter needed to start the economic analysis foreseen in the remainder of the project.
In our efforts addressing social and ethical considerations regarding the safety of advanced nuclear technologies, three activities were completed to foster sociotechnical integration at SCK CEN in Belgium and at RATEN in Romania: an individual reflection exercise, the Socio-Technical Integration (STIR) and a workshop (figure 2). Researchers from the ANSELMUS technical teams have done an individual reflection exercise on Responsible Research and Innovation (RRI) and have filled the survey to make the results available to social scientists. Secondly, they participated in a STIR exercise, and reflected upon societal and ethical aspects in their work by creating regular interaction between them and social scientists. For the workshops, Belgian and Romanian technical researchers were moderated by the social scientists, to explore critical facets on RRI using the “Imagine RRI” card game and to obtain input for the preparation of the World Café events that are planned for the next period.
Finally in the work package on education, dissemination, exploitation and data management, the procedures for the latter three during the ANSELMUS project have been defined. The project website (www.anselmus.eu) is now live and populated with the project's information. The first newsletter of the project has been published and the first educational event, i.e. the heavy metal summer school (figure3) has taken place at SCK CEN.
As this is the first reporting period report, the progress beyond the state of the art is limited since most of the time has been spend on preparation of experiments and analyses so the number of results is limited. Summarising we can state that the framework for the PIRT of MYRRHA and ALFRED has been defined, pre-experiment calculations for the experiments in WP2 and WP3 have been completed. In WP4, the framework for in-service inspection for heavy metal cooled nuclear systems have been defined. WP created the balance of plant to include thermal storage and hydrogen co-generation for a heavy metal cooled reactor for the first time.