NAUTILUS: A Project for the Development of Experimental Methods for Investigating Innovative Approaches to Nuclear Waste Management and to Nuclear Safety
Research output: Contribution to book/Conference proceedings/Anthology/Report › Conference contribution › Contributed › peer-review
Contributors
Abstract
Molten salt reactors (MSRs) are considered to be one option for tackling the problem of the ever-growing amount of spent fuel of light water reactors (LWRs). This paper gives an overview of the NAUTILUS project, which aims at contributing to the nuclear data base relevant for chloride based MSRs and at preserving and developing key competences in experimental reactor physics and physics of MSRs in Germany. The paper also highlights first results of the p roject. The ultimate goal of the project, which is the determination of nuclear cross sections of chlorine-35 at the TU Dresden Research and Educational Reactor AKR-2 and the application of the data in MSRs simulations (i.e. simulations of burning spent LWR fuel), depends on three main pillars: The determination of the neutron spectrum of the AKR-2, the development of experimental setups to determine nuclear cross sections at AKR-2, and the development of a validated simulation toolbox complementing the measurements. A major aspect of the project is the collaboration with the University of Liverpool for exchanging of expertise and mutual granting of access to research facilities. Being funded by the German government for 5 years and providing 5 full positions (four researchers, one technician), the project tackles the fields o f E xperimental r eactor p hysics, R eactor s afety, a nd N uclear waste management, while combining experiment and simulation. It is, thus, a substantial contribution to the future nuclear expertise in Germany.
Details
Original language | English |
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Title of host publication | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 |
Publisher | American Nuclear Society |
Pages | 316-325 |
Number of pages | 10 |
ISBN (electronic) | 9780894487972 |
Publication status | Published - 2024 |
Peer-reviewed | Yes |
Publication series
Series | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024 |
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Conference
Title | 2024 International Conference on Physics of Reactors, PHYSOR 2024 |
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Duration | 21 - 24 April 2024 |
City | San Francisco |
Country | United States of America |
Keywords
ASJC Scopus subject areas
Keywords
- cross section determination, molten salt reactor (MSR), neutron spectrum measurement, nuclear waste management, validation