Inert matrix fuel for the utilisation of plutonium

Ledergerber, G.; Degueldre, C.; Heimgartner, P.; Pouchon, Manuel A.; Kasemeyer, U.

doi:10.1016/s0149-1970(00)00122-0

Cited by 63 publications

(37 citation statements)

References 14 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In recent years, cubic yttria stabilized zirconia (YSZ) has been considered one of the most promising matrices for the immobilisation of plutonium and minor actinides (Am, Cm, Np), as a stable host phase for long-term final disposal, as well as a fuel/target material for transmutation. [1][2][3] According to Ref. [4], yttria cubic stabilized ZrO 2 is the most appropriate material in comparison with other possible alternatives, since it satisfies the criteria for an inert matrix, such as phase stability over a large temperature range and under severe irradiation; inertness with regard to transmutation products, cladding, and reactor water; small thermal neutron adsorption cross-section, etc.…”

Section: Introductionmentioning

confidence: 99%

Compressibility and sinterability of CeO2–8YSZ powders synthesized by a wet chemical method

Bukaemskiy

Barrier

Modolo

2009

Journal of the European Ceramic Society

View full text Add to dashboard Cite

Section: Introductionmentioning

confidence: 99%

Compressibility and sinterability of CeO2–8YSZ powders synthesized by a wet chemical method

Bukaemskiy

Barrier

Modolo

2009

Journal of the European Ceramic Society

View full text Add to dashboard Cite

“…[1][2][3] In fact, this material has a high leaching resistance, a high radiation stability, a small neutron capture cross section and a high melting point. 4,5 Furthermore, this system has the ability to form solid solutions, in a wide range of solubility, with compounds such as UO 2 , ThO 2 and PuO 2 .…”

Section: Introductionmentioning

confidence: 99%

Physical properties of 8mol% Ceria doped yttria stabilised zirconia powder and ceramic and their behaviour during annealing and sintering

Bukaemskiy

Barrier

Modolo

2006

Journal of the European Ceramic Society

View full text Add to dashboard Cite

“…Post-reactor requirements are that it must be able to be reprocessed to extract the minor actinides, and it must be compatible with the coolants used, and sodium as a thermal bonding agent [6,29,8,30,31].…”

Section: Sintered Pelletmentioning

confidence: 99%

Radiation Damage and Fission Product Release in Zirconium Nitride

Egeland

2005

View full text Add to dashboard Cite

Zirconium nitride is a material of interest to the AFCI program due to some of its particular properties, such as its high melting point, strength and thermal conductivity. It is to be used as an inert matrix or diluent with a nuclear fuel based on transuranics. As such, it must sustain not only high temperatures, but also continuous irradiation from fission and decay products. This study addresses the issues of irradiation damage and fission product retention in zirconium nitride through an assessment of defects that are produced, how they react, and how predictions can be made as to the overall lifespan of the complete nuclear fuel package.Ion irradiation experiments are a standard method for producing radiation damage to a surface for observation. Cryogenic irradiations are performed to produce the maximum accumulation of defects, while elevated temperature irradiations may be used to allow defects to migrate and react to form clusters and loops. Cross-sectional transmission electron microscopy and grazing-incidence x-ray diffractometry were used in evaluating the effects that irradiation has on the crystal structure and microstructure of the material. Other techniques were employed to evaluate physical effects, such as nanoindentation and helium release measurements.Results of the irradiations showed that, at cryogenic temperatures, ZrN withstood over 200 displacements per atom without amorphization. No significant change to the lattice or microstructure was observed. At elevated temperatures, the large amount of damage showed mobility, but did not anneal significantly. Defect clustering was possibly observed, yet the size was too small to evaluate, and bubble formation was not observed.Defects, specifically nitrogen vacancies, affect the mechanical behavior of ZrN dramatically. Current and previous work on dislocations shows a distinct change in slip plane, which is evidence of the bonding characteristics. The stacking-fault energy changes dramatically with lowered nitrogen stoichiometry, resulting in widely spaced partial dislocations in ZrN with high nitrogen vacancy concentration.The wide range of nitrogen stoichiometry in the phase field shows that ZrN may accept nitrogen defects readily. Explanations for this are suggested based upon the bonding structure of these cubic nitrides. This structure allows for a solid framework to remain on one sublattice, while at the same time allowing defects on the other sublattice. This allowance for defects allows significant damage from irradiation yet also decreases the drive for cluster growth. This is evidence that the structure will be acceptable for long-term use as a nuclear reactor fuel.

show abstract

Inert matrix fuel for the utilisation of plutonium

Cited by 63 publications

References 14 publications

Compressibility and sinterability of CeO2–8YSZ powders synthesized by a wet chemical method

Compressibility and sinterability of CeO2–8YSZ powders synthesized by a wet chemical method

Physical properties of 8mol% Ceria doped yttria stabilised zirconia powder and ceramic and their behaviour during annealing and sintering

Radiation Damage and Fission Product Release in Zirconium Nitride

Contact Info

Product

Resources

About