Reactor Core Materials Interactions at Very High Temperatures

Hofmann, P.; Hagen, S.; Schanz, G.; Skokan, A.

doi:10.13182/nt-tmi2-146

Cited by 75 publications

(23 citation statements)

References 13 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…In this way, the rate parameter b ox under wet conditions is identified with the oxidation rates measured by different authors [1,3,4]. The rate parameter a ox could be determined with the help of a test done in the thermo-balance in dry atmosphere under a temperature ramp going up to 800°C [8].…”

Section: High Density Materialsmentioning

confidence: 99%

“…In case of an accident different safety problems arise with these absorber rods. In first instance there occur eutectic reactions between existing materials like stainless steel cladding and B 4 C and also stainless steel and Zircaloy above about 950°C [1,2]. When the steam has free access to the surface of B 4 C a distinct exothermic oxidation ensues with formation of highly volatile boric acids.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Modeling of boron carbide oxidation in steam

Steiner¹

2005

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: High Density Materialsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Modeling of boron carbide oxidation in steam

Steiner¹

2005

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…The binary phase diagrams Zr-N [21] and Zr-O [22,23] are comparable, at least at the Zr side. For the pure metal a phase transition takes place from hcp a-phase to bcc b-Zr at 863°C; this transition temperature is reduced to around 800°C for the pseudo-binary system Zircaloy-4-oxygen [24,25].…”

Section: Analysis and Discussion Of Experimental Resultsmentioning

confidence: 99%

High-Temperature Oxidation of Zircaloy-4 in Oxygen–Nitrogen Mixtures

Steinbrück

Schaffer

2015

Oxid Met

View full text Add to dashboard Cite

Isothermal oxidation experiments with cladding tube segments of Zircaloy-4 (Zr-1.3%Sn) in oxygen-nitrogen model mixtures were performed at 800, 1000, and 1200°C for 6, 1 h, and 15 min, respectively. The gas compositions varied between 0 and 100 vol% nitrogen including 1 and 99 vol%. A strong accelerating effect of nitrogen on the oxidation kinetics was seen for a wide range of boundary conditions. At 800°C, oxidation in all mixtures with 1-99 % nitrogen resulted in higher reaction rates compared to the pure gases, especially after transition from protective to non-protective oxide scales. At 1000 and 1200°C, only starvation of oxygen in mixtures with low oxygen contents resulted in lower rates compared to pure oxygen. The oxide scales formed in the mixtures were very porous due to the formation of zirconium nitride at the metal-oxide interface and its oxidation during continuing reaction. The extension of the oxide-nitride zone increased with temperature and with nitrogen content in the gas mixture. Nitrogen seems also to affect the pre-transition reaction kinetics. The mechanism of the faster oxidation kinetics of zirconium alloys in atmospheres containing nitrogen will be discussed in this paper.

show abstract

“…2. Depending on the accident sequence, the important physico-chemical material behaviour in pressurized water reactors include [41,47]:…”

Section: Degraded Core Accident Phenomenamentioning

confidence: 99%

“…These experiments have principally focused on high temperature core melt progression and fission product release behaviour. Specifically, the experiments were designed to investigate: (i) how the core loses its original geometry as a result of interactions between core materials and fuel liquefaction; (ii) the relocation behaviour of the core with melt formation leading to partial core blockage, fuel debris beds and molten pools; (iii) how much hydrogen is produced by the steam oxidation of core materials with relocation; (iv) the influence of core degradation on the release, transport and deposition of fission products and aerosols; and (v) the fragmentation of the degraded core with cool down and/or quenching [40][41][42][43][44][45][46][47][48][49].…”

Section: Introductionmentioning

confidence: 99%