Simulating the corrosion of zirconium alloys in the water coolant of VVER reactors

Kritskii, V. G.; Berezina, I. G.; Motkova, E. A.

doi:10.1134/s0040601513070057

Cited by 5 publications

(2 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…But strong peaks show that there are still a lot of t-ZrO 2 and Zr matrices on the surface. It is consistent with the results of Kritskii et al (Kritskii et al, 2013). After 300 days of the test, strong m-ZrO 2 peaks can be found in both XRD spectrums.…”

Section: Resultssupporting

confidence: 93%

Influence of Ammonia on the Corrosion Behavior of a Zr–Sn–Nb Alloy in High Temperature Water

et al. 2022

View full text Add to dashboard Cite

Corrosion behaviors, microstructures of oxide films, and hydrogen absorptions of a Chinese domestic Zr alloy in 6.7 × 10−3 mol/L ammonia solution and 2.9 × 10−4 mol/L LiOH+9.3 × 10−2 mol/L H3BO3 solution at 360 °C, 18.6 MPa were studied. Weight gains, oxide film thicknesses, and hydrogen absorptions showed that the corrosion rate in the ammonia solution is a little higher than that in the boron–lithium solution. There is no significant difference in the microstructure and crystalline structure between the oxide films formed in the two types of solutions. The element distributions along the depth direction of the oxide films showed the existence of nitrogen in the oxide film formed in ammonia solution. Moreover, nitrogen was found to be segregated in local areas in a range of about 2 μm from the oxide/metal interface. The corrosion behavior of the Chinese domestic Zr alloy in 360 °C aqueous solution shows no difference with other Zr alloys.

show abstract

Section: Resultssupporting

confidence: 93%

Influence of Ammonia on the Corrosion Behavior of a Zr–Sn–Nb Alloy in High Temperature Water

et al. 2022

View full text Add to dashboard Cite

show abstract

“…Zirconium has good properties to be used in nuclear reactors, especially as cladding. Nuclear power consumes 90% of metal zirconium industry due to its excellent corrosion resistance, high thermal conductivity, suitable mechanical behavior and low neutron absorption cross‐section in the low and the thermal energy range 19‐23 . The basic idea of using Zr rods as water displacer inside the fuel assembly is to displace a part of the water in order to decrease the moderator‐to‐fuel ratio and the moderation process and thereafter the reactor reactivity 24 .…”

Section: Introductionmentioning

confidence: 99%

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

2021

View full text Add to dashboard Cite

Summary The control of the reactor energy increases the reactor fuel cycle time. In this work, a new method has been investigated to control the reactor energy instead of traditional methods. SERPENT2 version 2.1.30 was used to investigate the possibility of using Zirconium rods as an energy regulator in the VVER‐1000. Zirconium rods were used as water displacers. The effect of different Zr rod diameter on the infinite multiplication factor (k∞) of the reactor and the fuel concentration at different fuel burnup steps has been analyzed. Larger fuel pitches have been investigated to increase the Zr rod diameter. The main safety parameters such as the void volume reactivity coefficients, the Doppler reactivity coefficients and the Moderator temperature coefficient have been studied at different fuel pitch and different Zr rod diameter. A comparison between the effect of Zr rods and boric acid on the reactor reactivity proved the efficiency of using Zr rods as reactivity regulation.

show abstract

Effects of Atomic Oxygen Exposure on Tribological Property of Zirconium Alloy

Liu

Yang

et al. 2017

Astrophysics and Space Science Proceedings

View full text Add to dashboard Cite

Simulating the corrosion of zirconium alloys in the water coolant of VVER reactors

Cited by 5 publications

References 2 publications

Influence of Ammonia on the Corrosion Behavior of a Zr–Sn–Nb Alloy in High Temperature Water

Influence of Ammonia on the Corrosion Behavior of a Zr–Sn–Nb Alloy in High Temperature Water

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

Effects of Atomic Oxygen Exposure on Tribological Property of Zirconium Alloy

Contact Info

Product

Resources

About