skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Advancement of Supercritical Carbon Dioxide Technology through Round Robin Testing and Fundamental Modeling

Technical Report ·
DOI:https://doi.org/10.2172/1506970· OSTI ID:1506970
 [1];  [1];  [2];  [3];  [4];  [5];  [6];  [7]
  1. Oregon State Univ., Corvallis, OR (United States)
  2. Univ. of Wisconsin, Madison, WI (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. National Energy Technology Lab. (NETL), Albany, OR (United States)
  5. Carleton Univ., Ottawa, ON (Canada)
  6. Korea Advanced Inst. Science and Technology (KAIST), Daejeon (Korea, Republic of)
  7. Electric Power Research Inst. (EPRI), Palo Alto, CA (United States)
+ Show Author Affiliations

Growing interest in supercritical carbon dioxide (sCO2) cycles for advanced reactors is driving the need for corrosion data on candidate plant materials. The sCO2 Brayton cycle is being considered for power conversion systems for a number of nuclear reactor concepts including the sodium fast reactor, fluoride salt-cooled high temperature reactor, high temperature gas reactor, and several types of small modular reactors. Multiple organizations have developed test facilities to address the corrosion data knowledge gap in high temperature, high pressure sCO2 environments but, to date, there has been no formal test program among these organizations to validate the consistency of the data they produce. A demonstration of comparable and reproducible results enables a coordinated effort to explore the sCO2 parameter space relevant to advanced reactor technology. This proposal establishes a round robin test plan for sCO2 corrosion testing and the organization of a sCO2 Materials Group to guide future materials testing directions. Furthermore, this proposal outlines efforts to elucidate the mechanisms of sCO2 corrosion by performing identical tests in supercritical steam, testing model alloys with various composition and environmental conditions, accompanied by modeling efforts to study rate controlling mechanisms of corrosion and to help understanding the effects of impurities.

Research Organization:
Oregon State Univ., Corvallis, OR (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
NE0008424
OSTI ID:
1506970
Report Number(s):
CFA-15-8495; 15-8495
Country of Publication:
United States
Language:
English

Similar Records

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS