NSUF 24-4973: Nanoindentation Creep Testing and Characterization of High Temperature Irradiated HT-9 Cladding

HT-9 is a ferritic/martensitic steel alloy that is a candidate material for use in cladding in various advanced nuclear reactor designs including the Versatile Test Reactor. Although, there have been many successful experiments and studies surrounding the mechanical behavior of HT-9 under irradiation conditions with results from such studies being successfully incorporated into the BISON framework to model creep and simulate strain, there still exists significant inaccuracies to those models in scenarios of elevated temperatures (>600°C) and extended irradiation durations. Such inaccuracies are largely due to parameters from fresh HT-9 being used in the model which do not take into account the remarkable microstructural changes that occur under irradiation in the harsh in-core environment. Thus, it is the objective of this work to provide experimental data and measure such mechanical properties as elasticity from an HT-9 sample that has been previously irradiated in the Fast Flux Test Facility to 25 DPA at 635°C from which such experimental data can be incorporated into the BISON framework to more accurately model creep and simulate strain. Such work will be accomplished through the use of nanoindentation based experiments both in terms of constant strain rate loading as well as constant load creep experiments. Those experiments will be performed at multiple temperatures up to 500°C to obtain clear information of mechanical behavior at such elevated temperatures. The microstructure within the indented regions will be further characterized in TEM to further identify further phenomena contributing to mechanical behavior of heavily irradiated HT-9 cladding. It is expected that such work can be performed over the course of ten days. With such experimental measurements and knowledge, not only will detailed insight be gained into mechanical behavior, but the models can be updated to improve accuracy and provide a further, confident means of material qualification for advanced nuclear reactors.

추가 정보

필드	값
Award Announced Date	2024-05-28T17:12:22.17
Awarded Institution	Idaho National Laboratory
Facility Tech Lead	Alina Montrose
Irradiation Facility
PI	Joshua Rittenhouse
PI Email	[email protected]
Project Type	RTE
RTE Number	None