Charged particle irradiation facilities Sample Clauses

Charged particle irradiation facilities. For irreplaceable component materials, the doses expected at the end of life can be reached in existing MTRs, although in order to have exposure times much shorter than the real ones the fluxes used are much higher. While this may be a problem especially when the operating temperatures are high and the synergy between mild irradiation and thermal ageing and/or thermal creep may lead to unknown effects, MTRs available in Europe are at least usable to reach end-of-life doses, with the only caveat of the different neutron spectrum. However, for fuel and replaceable component materials, especially cladding, the doses expected in service are much higher than those accessible in thermal MTRs. The only way round this problem to reach doses up to or in excess of 100 dpa is currently the use of charged particles, despite the shortcomings and limitations associated with this type of irradiation, which can certainly not be used for full qualification purposes. Charged particle irradiation is also used to get further insight into the behaviour of materials under irradiation (see sections 2.3.2, 3.1.2 and 3.2.2) A significant number of facilities permitting charged particle irradiation, which can be exploited for the above purposes, exist in Europe at nuclear research centres and universities. Concerning fuel, if ion irradiation is used to study uranium-bearing fuel behaviour under irradiation, no charged particle irradiation facility exist for plutonium containing materials in Europe, and even in the world, except the Casimir facility at CEA Saclay (France) 86. This facility, however, is dedicated to the ion beam analysis of radioactive materials, and can only be used, with some limitations, to irradiate materials using light ions (H, He, N…). In practice, fuel pins are only qualified for a limited amount of time sufficient to license the first core. Further qualification or the qualification of alternative fuel pins are then performed in the reactor itself, when built.
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