Published April 2019 | Version v1
Journal article

Comparison of water, helium, and carbon dioxide as coolants for next generation power plants using TRACE

  • 1. The Pennsylvania State University, Department of Mechanical and Nuclear Engineering (United States)
  • 2. Nuclear Engineering Program, Materials Science and Engineering, University of Florida (United States)

Description

Highlights: • Added additional text to the introduction section to address the EOS and TRACE validation. • Changed all figure formats to PDF to improve resolution. • The number of significant figures in the tables is now consistent. • References were fixed. - Abstract: The purpose of this study is to compare the use of water, helium, and carbon dioxide as coolants for Generation IV and fusion power plants. In this study, the United States Nuclear Regulatory Commission's (NRC's) thermal hydraulics and neutronics coupled code TRAC/Relap Advanced Computational Engine (TRACE) was used to build and simulate a 600 MWth fusion Field Reversed Configuration (FRC) system that was cooled by either water, helium, or carbon dioxide. The results from the simulations, along with certain design criteria, were used to determine that water was the best coolant for the system of this study. For the operating conditions used in this research, water was able to keep the temperature of certain materials below their maximum temperatures much easier than the helium and carbon dioxide cooled systems. Specifically, beryllium was used as a material in the system and was determined to have a maximum temperature of 800 °C for its applications in this study (Mitteau et al., 2017). Additionally, this temperature limit restricts the efficiency and capabilities of the helium and carbon dioxide cooled systems. There is also uncertainty associated with the turbine efficiencies used in this study. This introduces uncertainty into the overall efficiency of the system for each coolant. So, the overall efficiency is not as important of a parameter in determining the best coolant for the system in this study as other parameters.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2018.11.016

Additional details

Identifiers

DOI
10.1016/j.anucene.2018.11.016;
PII
S0306454918306157;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
126
Journal Page Range
p. 292-302
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Notes
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