Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

Minato, Kazuo; Ogawa, Teiichiro; Sawa, Kôichiro; Ishikawa, Akiyoshi; Tomita, T.; Iida, Shozo; Sekino, Hajime

doi:10.13182/nt00-a3093

Cited by 77 publications

(39 citation statements)

References 18 publications

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“…[1][2][3] However, due to its strong covalent bonding nature and low self-diffusion coefficient, ZrC shows very poor sinterability, which limits its applications. It has been widely realized that smaller particles can lower the sintering temperature and facilitate densication processes due to the larger surface area and higher reactivity of the smaller particles.…”

Section: Introductionmentioning

confidence: 99%

Synthesis of nanocrystallized zirconium carbide based on an aqueous solution-derived precursor

Wang

Dong

et al. 2017

RSC Adv.

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Nanocrystallized zirconium carbide (ZrC) powder was synthesized by an aqueous solution-based process using zirconium acetate and sucrose as starting reagents. Polyvinyl pyrrolidone (PVP) was used to combine the reactants to form a suitable precursor for ZrC. Through such a novel aqueous solutionbased process, fine-scale mixing of the reactants is achieved in an environmentally friendly manner. The formed precursor can be converted to ZrC by carbothermal reduction reaction at 1600-1650 C. Thanks to a limited amount of residual free carbon, the as-synthesized ZrC powder had an ultra-fine particle size (50-100 nm) and a low oxygen content less than 1.0 wt%. The conversion mechanisms from assynthesized pre-ceramic precursor to ZrC powder were investigated systematically and revealed by means of FTIR, TG-DSC, XRD, Raman, SEM and TEM.

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Section: Introductionmentioning

confidence: 99%

Synthesis of nanocrystallized zirconium carbide based on an aqueous solution-derived precursor

Wang

Dong

et al. 2017

RSC Adv.

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“…Particularly, the structural swelling after neutron irradiation at room temperature saturates around 1 vol.% at a few dpa's [2]. Zirconium carbide has shown a better behaviour than silicon carbide for the barrier layer of the Triso particles, higher stability at high temperature and better fission products retention [3]. Neutron irradiations of different ZrC x compounds have been performed in order to study the stability in a large stoichiometry range [4].…”

Section: Introductionmentioning

confidence: 99%

Structural evolution of zirconium carbide under ion irradiation

Gosset

Dollé

Siméone

et al. 2008

Journal of Nuclear Materials

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“…These materials are highly refractory, 3 have a good thermal conductivity, 4 a low neutron absorption and a small absorption cross sections, a weak damage sensitivity under irradiation. 5,6 Unfortunately, they are characterized by brittle mechanical behaviour. 7 Over last years, nanosized grain materials have shown increasing interests due to new properties, which arise for example from the absence of extended defects in these particles.…”

Section: Introductionmentioning

confidence: 99%