Development of a comprehensive modeling capability based on rigorous treatment of multi-physics phenomena influencing reactor core design

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04

Volumn , Issue , 2004, Pages 1353-1363

  Sofu, T ^a   Weber, D P ^a   Chun, T H ^b   Joo, H G ^b   Thomas, J W ^c   Zhong, Z ^c   Downar, T J ^c  

^a ARGONNE NATIONAL LABORATORY   (United States)

^b Korea Atomic Energy Research Institute   (South Korea)

^c PURDUE UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; COMPUTATIONAL FLUID DYNAMICS; COMPUTER SIMULATION; COOLANTS; HYDRAULICS; MATHEMATICAL MODELS; TRANSPORT PROPERTIES;

COMPUTATIONAL CELLS; FUEL ASSEMBLY; HIGH-FIDELITY CAPABILITY; PARALLEL PLATFORMS;

REACTOR CORES;

EID: 14844309428     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (14)

1. D.P. Weber, et.al., "Integrated 3-D Simulation of Neutronic, Thermal-Hydraulic and Thermo-Mechanical Phenomena," Proc. of the 10th Intl. Topical Mtg. on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003.
2. D.P. Weber, et.al., "The Numerical Nuclear Reactor for High Fidelity Integrated Simulation of Neutronic, Thermal-Hydraulic and Thermo Mechanical Phenomena," Proc. of the ANS Reactor Physics Topical Meeting, PHYSOR 2004, Chicago, Illinois, April 25-29, 2004.
3. J.Y. Cho, H.G. Joo, "Consistent Group Collapsing Scheme for Multi-Group MOC Calculation," Proc. of the ANS Reactor Physics Topical Meeting, PHYSOR 2002, Seoul, Korea, October 7-10, 2002.
4. R.J.J. Stamm'ler, "HELIOS Methods," Studsvik Scan-power, 2002.
5. H.G. Joo, et.al., Proc. of the ANS Reactor Physics Topical Meeting, PHYSOR 2004, Chicago, Illinois, April 25-29, 2004.
6. J.D. Hooper and D.H. Wood, "Fully Developed Rod Bundle Row over a Large Range of Reynolds Numbers," Nucl. Eng. and Des., 83, pp. 31-46, 1984.
7. V. Vonka, "Measurement of Secondary Flow Vortices in a Rod Bundle," Nucl. Eng. and Des., 106, pp. 191-207, 1988.
8. W. K. In, C. H. Shin, D. S. Oh, T. H. Chun, "CFD Simulation of the Turbulent Flow and Heat Transfer in a Bare Rod Bundle," Proc. ICAPP'04 Pittsburgh, PA, June 13-17, 2004.
9. Krauss and Mayer, "Experimental investigation of turbulent transport of momentum and energy in a heated rod bundle," Nucl. Eng. and Des., 180, 185-206, 1998.
10. J. Thomas, et.al., "The Coupling of the STAR-CD Software to a Whole-Core Neutron Transport Code DeCART for PWR Applications," Proc. of Intl. Conf. on Supercomputing in Nuclear Applications, SNA'03, Paris, France, September 22-24, 2003.
11. STAR-CD, Version 3.150A, CD-adapco Group, Melville, NY.
12. J. Thomas, et.al., "Methodology for Coupling Computational Fluid Dynamics with Integral Transport Neutronics," Proc. of the ANS Reactor Physics Topical Meeting, PHYSOR 2004, Chicago, Illinois, April 25-29, 2004.
13. D.P. Weber, et.al., "Coupled Calculations using the Numerical Nuclear Reactor for Integrated Simulation of Neutronic and Thermal-Hydraulic Phenomena," Proc. of the ANS Reactor Physics Topical Meeting, PHYSOR 2004, Chicago, Illinois, April 25-29, 2004.
14. T. Takeda, K. Ohya, E. Saji, "Doppler Reactivity Calculation for Thermal Reactor Cells by Space-Dependent Multiband Method," J. Nucl. Sci. Technol, 33, 604, 1996.