The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview

Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Volumn , Issue , 2004, Pages 13-20

  Weber, D P ^a   Sofu, T ^a   Pfeiffer, P A ^a   Yang, W S ^a   Taiwo, T A ^a   Joo, H G ^b   Cho, J Y ^b   Kim, K S ^b   Chun, T H ^b   Downar, T J ^c   Thomas, J W ^c   Zhong, Z ^c   Kim, C H ^d   Han, B S ^d  

^a ARGONNE NATIONAL LABORATORY   (United States)

^b Korea Atomic Energy Research Institute   (South Korea)

^c PURDUE UNIVERSITY   (United States)

^d Seoul National University   (South Korea)

Author keywords

CFD; Computational fluid dynamics; Core analysis; Coupled codes; High performance computing; Integral transport theory; Neutronics; Numerical reactor; Parallel computers; Reactor physics; Thermal hydraulics

Indexed keywords

COUPLED CODES; HIGH PERFORMANCE COMPUTING; INTEGRAL TRANSPORT THEORY; NEUTRONICS; NUMERICAL REACTORS; PARALLEL COMPUTERS; REACTOR PHYSICS; THERMAL-HYDRAULICS;

CHEMICAL VAPOR DEPOSITION; COMPUTATIONAL METHODS; COMPUTER SIMULATION; CORE ANALYSIS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; NEUTRONS; PROJECT MANAGEMENT;

NUCLEAR REACTORS;

EID: 22344449428     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (13)

1. th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10) Seoul, Korea, October 5-9, 2003.
2. H.G Joo, et.al., 2002, Dynamic Implementation of the Equivalence Theory in the Heterogeneous Whole Core Transport Calculation, Proceedings of PHYSOR 2002 ANS International Topical Meeting on the New Frontiers of Nuclear Technology, Seoul, Korea, October 7-10, 2002.
3. J.Y Cho et al., 2002, Three-Dimensional Heterogeneous Whole-Core Transport Calculation Employing Planar MOC Solution, Trans. Amer. Nucl. Soc., 87, 234.
4. H. J. Shim, B. S. Han and C. H. Kim, "Numerical Experiment on Variance Biases and Monte Carlo Neutronics Analysis with Thermal Hydraulic Feedback," International Conference on Supercomputing in Nuclear Application, SNA03, Paris, France, Sept. 22-24, 2003, Paper 103, CDROM (2003).
5. STAR-CD, Version 3.150A, CD-adapco Group, Melville, NY.
6. CFX-4.4, AEA Technology, Oxfordshire, UK.
7. C. P. Tzanos, 2002, Heat Transfer Predictions of k-ε , Turbulence Models, Trans. Amer. Nucl. Soc., 87, 184.
8. W. K. In, 2002, Numerical Prediction of Flow in a Nuclear Fuel Bundle with Various Turbulence Models, Intl. ASME/JSME/KSME Symposium on CFD, Canada, 2002.W.K. In,
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. R. F. Kulak and C. Fiala, "NEPTUNE: A System of Finite Element Programs for Three-Dimensional Nonlinear Analysis," Nuclear Engineering and Design, 106 (1988) 47-68.
11. J.W. Thomas, H.C. Lee, T. J. Downar, Purdue University, T. Sofu, D. P. Weber, Argonne National Laboratory, H. G. Joo, J. Y. Cho, Korean Atomic Energy Research Institute, 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.
12. D. Barber, R.M. Miller, H. Joo, T. Downar (Purdue University), W. Wang (SCINTECH, Inc.), V. Mousseau, D. Ebert (USNRC), "Coupled 3D Reactor Kinetics and Thermal-Hydraulic Code Development Activities at the U.S. Nuclear Regulatory Commission," M&C'99 in Madrid, Spain, Sept. 27-30, 1999.
13. T. Kozlowski, R. Miller, T. Downar, D. Ebert, "Analysis of the OECD MSLB Benchmark with the Coupled Neutronic and Thermal-Hydraulics Code RELAP5/PARCS," PHYSOR-2000, Pittsburgh, 2000.