A Steady-State Thermal-Hydraulic Analysis Method for Prismatic High-Temperature Gas-Cooled Reactors
Author:
Affiliation:
1. Georgia Institute of Technology, George W. Woodruff School of Mechanical Engineering, Atlanta, Georgia 30332-0425
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT15-14
Reference11 articles.
1. “RELAP5-3D Code Manuals Revision 4.0.3,” Idaho National Laboratory (2012).
2. R. O. Gauntt et al. “MELCOR Computer Code Manuals,” NUREG/CR-6119, vol. 3, Rev. 0, SAND2001-0929P, Sandia National Laboratories (2001).
3. A. S. Shenoy and D. W. McEachern, “HTGR Core Thermal Design Methods and Analysis,” GA-A12985, General Atomics (1974).
4. C. H. Lee et al. “Status of Reactor Physics Activities on Cross Section Generation and Functionalization for the Prismatic Very High Temperature Reactor, and Development of Spatially-Heterogeneous Codes,” ANL-GenIV-075, Argonne National Laboratory (2006).
5. “Gas Turbine-Modular Helium Reactor (GT-MHR) Conceptual Design Description Report,” Report No. 910720, General Atomics (1996).
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