A Study of Materials Used in High Temperature Nuclear Applications

1. A Study of Materials Used in High Temperature Nuclear Applications Catherine Bartholomae MANE6980 - Engineering Project Advisor: Sudhangshu Bose 9/30/10

2. Abstract • Very High-Temperature Reactors (VHTR) are being designed to provide new energy options for the future. • The heat exchanger sees temperatures around 1300 K . • Material selection is one of the main challenges in the new concept because of : • Creep Behaviour • Fatigue Properties • Structural Stabillity • Corrosion Resistance • Important factors besides just material properties: • It is also important to consider fabricability and component behavior: • Workability • Weldability • Non-destructive Testing • And more..

3. Introduction • The concept for the VHTR is a graphite-moderated core with a once through uranium fuel cycle. It is expected to have outlet temperatures of ~1000 oC.

4. Introduction continued… • This project will focus on the heat exchanger of the VHTR and materials being researched for its high temperature application as well as the highly corrosive coolant that passes through it. • Helium serves as a primary coolant and can contain traces of reactive impurities such as hydrogen, methane, carbon monoxide and water vapor.

5. Problem Description and Expected Outcomes • To perform a critical review of literature regarding materials expected to be used in the VHTR heat exchanger. • The expected outcome for the project is to gather a detailed analysis of materials found and compile them into one technical paper detailing their pros and cons for use in industry.

6. Materials for Further Research • Suggested material from research done thus far include: • Ceramic Materials • Specifically SiC Ceramics • Nickel Based Alloys • Specifically Inconel 617 and Incoloy 800HT

7. Suggested Material Inconel 617 Exhibits high level of creep strength Nickle-based alloys have high creep rupture strength Incoloy 800H High creep strength as well however not as susceptible as high of temperatures as Inconel 617. SiC (Ceramics)

8. Suggested Material cont’d… • Hastelloy X?? • New research shows this has properties in between Inconel 617 and Incoloy 800H however more research is necessary.

9. Milestones • Submit Draft Proposal 9/23/10 • Submit Proposal and Brief Presentation 9/30/10 • Begin research and obtain 12 technical papers 9/30/10 • Attend The Cole Library in Hartford 10/7/10 • Based on prior research continue research of papers found in Hartford 10/14/10 • Submit 1st Progress Report 10/21/10 • Compile all pros and cons thus far for each technical paper 10/28/10 • Begin writing final report and continue research 11/4/10 • Submit 2nd Progress Report and Presentation 11/11/10 • Continue writing report between 11/11/10 and 12/2/10 • Submit Final Draft 12/2/10 • Finalize paper between 12/2/10 and 12/16/10 • Submit Final Report and Presentation 12/16/10

10. References • Aquaro, D., and M. Pieve. "High Temperature Heat Exchangers for Power Plants: Performance of Advanced Metallic Recuperators." Applied Thermal Engineering (2007): 389-400. ELSEVIER. 4 Oct. 2006. Web. 27 Sept. 2010. <www.elsevier.com/locate/apthermeng>. • Yvon, P., and F. Carre. "Structural Material Challenges for Advanced Reactor Systems." Journal of Nuclear Materials (2008): 217-222. ELSEVIER. Web. 23 Sept. 2010. <www.elsevier.com/locate/jnucmat>. • Zhu, S., M. Mizuno, Y. Kagawa, J. Cao, Y. Nagano, and H. Kaya. "Creep and Fatigue Behavior of SiC Fiber Reinforced SiC Composite at High Temperatures." Materials Science & Engineering (1997): 69-77. Print. • “Generation IV Reactor.” Wikipeda, the Free Encyclopedia. 28 Sept. 2010. Web, <http://en.wikipedia.org/wiki/Generation_IV_reactor>. • "Very High Temperature Reactor." Wikipedia, the Free Encyclopedia. 20 Sept. 2010. Web. 30 Sept. 2010. <http://en.wikipedia.org/wiki/Very_high_temperature_reactor>.