Testing of FBR fuel and core structural materials in a materials testing reactor
Although the HFR is a thermal reactor, fast reactor conditions can be simulated by suitable design of the irradiation devices; for example, the in-pile carriers for fuel irradiation are provided with cadmium screens in order to cut off the thermal neutrons. The fuel pins and the core structural material samples are immersed in sodium and encapsulated in double-containment sealed tubes, and placed in individually cooled experimental carriers, for placement in the reactor. Fuel irradiation conditions that can be simulated include start-up behaviour, power cycling and ramping, transient or steady-state overpower up to fuel melting and loss-of-flow. Pre-irradiated high burn-up fuel pins, having achieved end-of-life conditions in the European fast reactors PHENIX and PFR, are also to be tested. Irradiation of core structural material samples in sodium up to temperatures of around 823 K for investigation of tensile and fatigue behaviour are continuing with the martensitic steel and AISI 316L. The paper gives a description of the typical features of an irradiation device, its instrumentation, some of the available ancillary equipment, developments and some results of the experiments.
Bibliographic Reference: Paper presented: 12th International Conference on Structural Mechanics in Reactor Technology, Stuttgart (DE), August 1993
Availability: Available from (1) as Paper EN 37394 ORA
Record Number: 199310525 / Last updated on: 1994-11-29
Original language: en
Available languages: en