Investigation of processing routes, microstructures and mechanical properties of reduced activation ferritic/martensitic steels for nuclear fusion applications

Research output: ThesisDoctoral thesis

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Institutes & Expert groups

  • UGent - Universiteit Gent

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Abstract

Ferritic/martensitic (F/M) steels have been proposed as fuel assembly materials at the time of the fast reactor programmes in the 1970s-1980s because, by swelling significantly less than austenitic steels under irradiation, they would allow the fuel to be kept for longer time in the reactor, thereby increasing the burnup[1]. Burnup increase has a number of quite obvious advantages: more efficient use of the fuel (more energy produced from the same fuel pins), consumption of not only uranium and plutonium, but also minor actinides, with subsequently reduced amount of waste (in a closed fuel cycle scenario …), etc. In addition to superior resistance to irradiation, F/M steels have also better thermal properties, in particular higher thermal conductivity than austenitic, thereby offering better guarantees in the case of thermal transient, especially an accidental one.

The current goals of increasing both thermodynamic efficiency and safety in GenIV reactors require that fuel assembly materials should have good elevated-temperature mechanical properties (so, good creep resistance), while stably offering good fracture toughness at all temperatures, including under irradiation. Fusion reactors have in this respect very similar requirements, in addition to the stringent limitation of reduced activation. The loss of creep resistance above 550°C in existing F/M steels, used or usable in nuclear energy, is one factor that limits the operating temperature of fast reactors. Austenitic steels, at least 316L, allow in this respect somewhat higher temperature[2], even though the difference is not spectacular. Thus, F/M steels with superior creep resistance would certainly find application for the supporting component of the core of fast reactors, as well as for fusion applications, given that their resistance to irradiation up to high dose, swelling in particular, but also irradiation creep, is higher. Already now, standard F/M steels such as EM10 are planned to be used for in-core supporting components of the future French sodium fast reactor, ASTRID, such as wrappers.
In order to increase the creep resistance and therefore increase the operating temperature, oxide dispersion strengthening (ODS) of F/M steels is currently being considered. However, ODS steels can currently only be produced from powder technology by mechanical alloying followed by extrusion. This limits the industrial scalability of their production. Moreover, to date it remains challenging to guarantee the uniform distribution of nanometric dispersoids that would ideally be required, as well as to remove the anisotropy of the properties of these alloys. It is also difficult to guarantee reasonable uniformity of properties from heat to heat. Finally, fracture toughness remains quite severely penalized even at high temperature: it is therefore unlikely that these alloys will ever be usable for any other reactor component except cladding. Thus, ODS steels remain a possible alternative as nuclear reactor core materials, but projected far in the future as a long-term perspective, and most likely their use will not be considered for structural components.

In recent times an intermediate solution between current F/M steels and ODS steels has been considered, which would remove the problems of fabricability. The idea is to push up the upper operating temperature limit of conventionally produced F/M steels, by improving their thermal creep-resistance, while keeping their composition compatible with the requirement of nuclear energy, including as much as possible low activation. This research line has been pursued in the US by R. Klueh and co-workers at ORNL, is being studied at CEA in France, where a few PhD theses are devoted to this route, and has been included as one of the priorities of the current European fusion roadmap. In no case, however, for the moment, has any steel-maker been involved in such type of research. Commercial creep-resistant steels of superior capability in terms of creep-resistance and therefore with higher operation temperature limits do exist, in fact (so called 4th Generation creep-resistant steels), for example P92, HCM12A, and more recently NF12 and SAVE12. However, the composition of these steels is clearly incompatible with their use in nuclear energy, because of activation and in general neutronic reasons (e.g. the use of boron or cobalt), but also because of the presence of elements that lead to pernicious radiation effects in terms of embrittlement (nickel, copper, …).

Details

Original languageEnglish
QualificationDoctor of Science
Awarding Institution
  • UGent - Universiteit Gent
Supervisors/Advisors
  • Sietsma, Jilt, Supervisor, External person
  • Petrov, Roumen, Supervisor, External person
  • Malerba, Lorenzo, SCK CEN Mentor
Award date7 Dec 2018
Publisher
  • UGent - Universiteit Gent
Print ISBNs9789463551823
Publication statusPublished - 7 Dec 2018

Keywords

  • Creep-resistant steels, Nuclear energy, Develoment

ID: 7500996