Materials Map

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The Materials Map is an open tool for improving networking and interdisciplinary exchange within materials research. It enables cross-database search for cooperation and network partners and discovering of the research landscape.

The dashboard provides detailed information about the selected scientist, e.g. publications. The dashboard can be filtered and shows the relationship to co-authors in different diagrams. In addition, a link is provided to find contact information.

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The Materials Map is still under development. In its current state, it is only based on one single data source and, thus, incomplete and contains duplicates. We are working on incorporating new open data sources like ORCID to improve the quality and the timeliness of our data. We will update Materials Map as soon as possible and kindly ask for your patience.

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in Cooperation with on an Cooperation-Score of 37%

Topics

Publications (2/2 displayed)

  • 2012Safety Approaches In Gen-IV Research Reactors: Myrrha In-Vessel Fuel Manipulationcitations
  • 2012A Bifurcate System Analysis Approach to Safe Machine Design for Advanced Lead-Cooled Reactors: MYRRHA In-Vessel Fuel Manipulationcitations

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Chart of shared publication
Gesseneck, Josip Jezic Von
2 / 2 shared
Vanderborght, Bram
2 / 19 shared
Overmeire, Marc Van
2 / 2 shared
Lefeber, Dirk
2 / 4 shared
Caers, Ben
2 / 4 shared
Chart of publication period
2012

Co-Authors (by relevance)

  • Gesseneck, Josip Jezic Von
  • Vanderborght, Bram
  • Overmeire, Marc Van
  • Lefeber, Dirk
  • Caers, Ben
OrganizationsLocationPeople

document

Safety Approaches In Gen-IV Research Reactors: Myrrha In-Vessel Fuel Manipulation

  • Gesseneck, Josip Jezic Von
  • Vanderborght, Bram
  • Naidoo, Diana
  • Overmeire, Marc Van
  • Lefeber, Dirk
  • Caers, Ben
Abstract

One of the main concerns of nuclear energy is the treatment of the nuclear waste and thus technology that decreases waste output and waste half-life is consequently very interesting. This is one of the principal aims of the MYRRHA (Multi-purpose, hYbrid Research Reactor for High-tech Applications) GEN-IV reactor project. As a subcritical reactor driven externally by a high-powered accelerator, MYRRHA will be one of the earliest global demonstrations of accelerator-driven systems (ADS). A major advantage of the ADS, besides its subcriticality, is its transmutation of minor actinide waste. Lead-Bismuth Eutectic (LBE) was chosen as the spallation target and coolant for its high spallation efficiency, having a good heat capacity and reduced impact on the speed of the neutrons. Two in-vessel fuel manipulators (IVFM) operating from under the core with 4 degrees of freedom (DOF) must move the fuel assemblies between the core, storage and ex-vessel fuel transfer positions. The IVFM is thus a critical component of the MYRRHA reactor - it is essential to demonstrate its safe operation in proving the feasibility of the reactor by 2014. The LBE environment presents many technological challenges to fuel manipulation: temperatures of 200°C to 300°C, zero visibility, hydrodynamic forces, corrosion, fast neutron irradiation, and the fatigue of long operating periods. This collaborative doctoral project between the SCK* CEN and the VUB, funded by the AVN, supports the development of the IVFM from a safety approach, with the objectives to form the acceptance criteria for safe fuel operation, the design and operation methods to reach these, and adequate tests to validate these methods. Within the framework of the national legislation and international guidelines, we identify the safety functions of the IVFM and evaluate the adequacy of the design and fault response measures in minimizing the related risks to a tolerable level.We approach the safety analysis of the IVFM by both a deductive bottom-up Failure Mode and Effects (FMEA) and inductive top-down Fault Tree Analysis (FTA).A low-resolution FMEA at the component level allows us to organize the testing, warns us about expected failure modes, and prioritizes component and design adjustments based on predicted effects.The complementary FTA maps out the interesting failure paths leading to the most important top failure events of the IVFM in criticality, heat, and radiation. The fault trees are updated from, and feed back into the tests and design with failure modes (qualitative) and occurrences (quantitative), in an iterative process.

Topics
  • impedance spectroscopy
  • corrosion
  • fatigue
  • heat capacity
  • Bismuth
  • Actinide