Home
Scholarly Works
Development of a CanmetMATERIALS Gen IV Materials...
Conference

Development of a CanmetMATERIALS Gen IV Materials Property Database for Materials Selection

Abstract

The Canadian GIF team has chosen to focus on the development of a Super-critical water-cooledreactor (SCWR), requiring material stability atboth higher temperatures and pressures than theolder CANDU(R) reactor designs. Preliminary concept designs peg core operating temperaturesat close to 650°C and pressures at 25 MPa. Assuch there are a number of materials challengesthat must be considered in the process of de-signing a prototype reactor. The Gen IV SCWR conceptual design requires the identification and testing of materials used in all components of the new reactor design under these conditions. While a large amount of experimental data exists on materials properties in SCW, no database was available to consolidate access and assessthis data. A dynamic web-based database forstoring materials corrosion and mechanical datarelevant to the Gen IV SCWR Canadian concept is developed. Data has been collected for, at present, 87 different alloys.

Authors

Greenwood M; Xu S; Zheng W

Publication Date

January 1, 2016

Conference proceedings

36th Annual CNS Conference and 40th CNS Cna Student Conference Nuclear in the 21st Century Global Directions and Canada S Role

Contact the Experts team