Papers by Keyword: Cladding Material

Abstract: Laser cladding has received significant attention in recent years due to its unique features and capabilities in various industries involved in metallic coating, high-value components repair, prototyping, and low-volume manufacturing. The laser cladding technology research status was reviewed. The characteristics of laser cladding technology, process methods, materials systems and current problems were summarized. The prospects and future research priorities were forecasted.

Abstract: Using B, Mo, and Fe powders as raw materials, Mo₂FeB₂ cermets-steel clad material has been prepared on steel 45 substrate by means of in-situ reaction vacuum and liquid phase sintering technology, and the influence of heat treatment on microstructure and properties has been studied. The influence of heat treatment on microstructure, and distribution of elements of the cladding-substrate bonding interface area has been investigated by SEM, EDS. Results show that there is an excellent metallurgic bonding between the cladding layer and steel substrate both before and after heat treatment, and heat treatment not only brings the cladding material grain size and microstructure refinement but also increases the thickness of the transition layer.

Abstract: Using finite element method, a quenching analysis of 7075 aluminum alloy thick plate is carried out. The effect of surface heat transfer coefficient and plate thickness on residual stress, and the effect of cladding material on residual stress are discussed. It shows that the bigger surface heat transfer coefficient or thickness is, the bigger the residual stress is, and the residual stress significantly reduces while the cladding material exists. Experiments validated the simulation results.

Abstract: The Super-Critical Water-cooled Reactor (SCWR) has been designed and investigated because of its high thermal efficiency and plant simplification. As the operating temperature of supercritical water reactor will be between 280°C and 620°C with a pressure of 25MPa, the selection of materials is difficult and important. The PNC1520 austenitic stainless steel developed by Japan Atomic Energy Agency (JAEA) as a nuclear fuel cladding material for a Na-cooled fast breeder reactor. The corrosion data of PNC1520 in supercritical water (SCW) is required but does not exist. The purpose of the present study is to research the corrosion properties for PNC1520 austenitic stainless steel in supercritical water. The supercritical water corrosion test was performed for the standard PNC1520 (1520S), the Ti-additional type of PNC1520 (1520Ti) and the Zr-additional type of PNC1520 (1520Zr) by using a supercritical water autoclave. In view of general corrosion, 1520Zr may have larger possibility than 1520S and 1520Ti to adopt a supercritical water reactor core fuel cladding.

Abstract: Thick laser coating on sealing surface of high parameter nuclear and chemical valve have been made, And the factors that will influence layer’s cracking behavior have been analyzed including laser cladding material, technology and base metal. It is approved by experiment that the greater the energy ratio is, the lower the possibility of cracking would be. But this case may cause diluting rate of the coat increasing, grains coarsening and hardness reducing. B and Si can create hard phase, reduce coating’s plasticity, and generate segregation easily in Ni-base alloy which may cause crystal crack. The rate of coating cracking will reduce when substrate has homogeneous structure, no relict stress, no defect, good plasticity, and, its rate of heat expansion is a bit higher than clad material, heat capacity is small, shape and structure is simple and heat symmetrical characteristic is good.