Progress of the MYRRHA ADS Project in Belgium
- 1. Belgian Nuclear Research Centre - SCK.CEN (Belgium)
Description
The MYRRHA Project was started in 1998 by SCK-CEN in collaboration with Ion Beam Applications (IBA, Louvain-la-Neuve), as an upgrade of the ADONIS Project. MYRRHA is designed as a multi-purpose irradiation facility in order to support research programmes on fission and fusion reactor structural materials and nuclear fuel development. Applications of these are found in accelerator-driven systems (ADS) and in present generation as well as in next generation critical reactors. The first objective of MYRRHA, however, will be to demonstrate on one hand the ADS concept at reasonable power level and on the other hand the technological feasibility of the transmutation of minor actinides (MA) and long-lived fission products (LLFP) arising from the reprocessing of radioactive waste. MYRRHA will also help the development of the Pb-alloys technology needed for the LFR (lead fast reactor) Generation-IV concept. The transmutation of minor actinides can be completed in an efficient way in fast neutron spectrum facilities. Both critical reactors and subcritical ADS are potential candidates as dedicated transmutation systems. However, critical reactors, heavily loaded with fuel containing large amounts of MA, pose reactivity control problems, hence safety problems, caused by unfavourable reactivity coefficients and small delayed neutron fraction. A subcritical ADS operates in a flexible and safe manner even with a core loading containing a high amount of MA, leading to a high transmutation rate. Thus, subcriticality is not a virtue but rather a necessity for an efficient and economical burning of the MA. Besides these reactor and core physics considerations, there are other parameters to consider when deciding on the most appropriate technology suitable for the large scale deployment of partitioning and transmutation (P and T) technology for the reduction of the HLW burden. The implementation of P and T needs the demonstration of the feasibility of several installations at an 'engineering' level. The respective research and development activities could be arranged in four so-called 'building blocks' aiming to: - demonstrate the capability to process a 'sizable' amount of spent fuel from commercial power plants (i.e. LWR) in order to separate Pu and MA; - demonstrate the capability to fabricate at semi-industrial level the dedicated fuel needed to load a dedicated transmuter; - make available one or more dedicated transmuters; - provide an installation for the processing of the fuel unloaded from the transmuter which can be of a different type from the one used to process initially the original spent fuel unloaded from the commercial power plants (i.e. LWR). This paper summarises the progress of the MYRRHA Project and its perspective of implementation in Belgium. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Twelfth Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
- Imprint Pagination
- 329 p.
- Journal Page Range
- p. 158-168
- Report number
- NEA-NSC-DOC--2013-3
Conference
- Title
- 12. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
- Dates
- 24-27 Sep 2012
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 44100549
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATOR DRIVEN TRANSMUTATION; ACTINIDES; BELGIUM; FAST REACTORS; FEASIBILITY STUDIES; FISSION PRODUCTS; FUEL CYCLE; ISOTOPE PRODUCTION; LEAD ALLOYS; MATERIALS TESTING REACTORS; NEA; NUCLEAR FUELS; PARTITION; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; REACTIVITY; REACTOR CORES; REACTOR KINETICS; REACTOR SAFETY; REPROCESSING; TECHNOLOGY ASSESSMENT
- Descriptors DEC
- ALLOYS; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; EUROPE; FUELS; INTERNATIONAL ORGANIZATIONS; IRRADIATION REACTORS; ISOTOPES; KINETICS; MANAGEMENT; MATERIALS; METALS; OECD; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; SEPARATION PROCESSES; TRANSMUTATION; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; WESTERN EUROPE