Stress effect on the void swelling incubation period

Weiner, R.A.; Boltax, A.

doi:10.1016/0022-3115(77)90233-1

Cited by 8 publications

(2 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Residual stress (blue line) induced by welding process at the heat affected zone (HAZ) decreased with increasing dose (8,9) . Swelling increased rapidly above the threshold dose (10) . Each irradiation effect has the different dose and temperature dependence in particular; swelling occurs at higher temperature and dose side, on the other hand, the swelling caused the swelling-induced tensile stress at lower temperature side of the structures when those deformations are constrained.…”

Section: Concept Of New Evaluation Methods Of Materials Degradation Conmentioning

confidence: 97%

New Evaluation Method of Material Degradation Considering Synergistic Effects of Radiation Damage

Miwa

Kaji

Okubo

et al. 2008

JMMP

View full text Add to dashboard Cite

In core structural materials of next generation reactors such as a liquid-metal cooled fast breeding reactor and a supercritical-water cooled thermal or first reactor, materials' degradation behavior by neutron irradiation damage and thermal (cyclic) stress should be considered with fair accuracy in design process (including maintenance and repair plans), because the materials are used under higher temperature gradients and higher neutron flux fields than those in the present light water reactors. In the current experiential design rules, service lives of core structural components were determined by the materials degradation such as the increase of ductile-to-brittle transition temperature after post irradiation examination data. However, other materials degradations such as irradiation-assisted stress corrosion cracking (IASCC), which occurs by the degradation synergistically interacting with radiation hardening, local chemical composition change, swelling and radiation creep, should be considered reasonably in the design process of the next generation reactors, because of the anticipation of the beneficial effects by synergy of radiation damage. The radiation hardening and local chemical composition change at grain boundaries due to radiation-induced segregation increased with increasing dose. Above some threshold dose, swelling increased rapidly with increasing dose. Residual stress due to thermal stress and welding procedure decreased with increasing dose. To predict material failure by IASCC with reasonable accuracy, in this study, each material degradation phenomenon with different dose dependence was modeled with consideration of radiation induced stress relaxation. And then the models were integrated to simulate the failure behavior for the duration of reactor operation period. In this paper, the models obtained by ion-irradiation experiments and compared by data from neutron irradiation experiments were presented, and the concept of our new evaluation method and the programming code for the failure simulation were outlined.

show abstract