1 |
United States Nuclear Regulatory Commission, "Control of Heavy Loads at Nuclear Power Plants", U.S. NRC NUREG-0612, 2.1 (1980).
|
2 |
United States Nuclear Regulatory Commission, "Assumptions Used For Evaluating The Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors", U.S. NRC Regulatory Guides 1.25 (1972).
|
3 |
H.J. Wu, C.C. Tseng, and S.C. Cheng, "A Numerical Analysis for a BWR Fuel Assembly Drop Event", J. Nucl. Sci. Technol., 43(9), 1068-1073 (2006).
DOI
|
4 |
W. Zhao, J. Liu, W. Stilwell, B. Hempy, and Z. Karoutas, "Modeling Nuclear Fuel Rod Drop with LS-DYNA", 13th International LS-DYNA Users Conference, Detroit (2014).
|
5 |
American National Standards Institute(ANSI)/Ameri-can Nuclear Society(ANS)-57.5-1996, Light Water Reactors Fuel Assembly Mechanical Design and Evaluation (2006).
|
6 |
R.D. Blevins , "Applied Fluid Dynamics Handbook", Krieger, Florida (2003).
|
7 |
I.E. Idelchik, "Handbook of Hydraulic Resistance", 3rd Edition, CRC Press, London (1994).
|
8 |
F. M. White, "Fluid Mechanics", 5th Edition, McGraw-Hill, New York (2002).
|
9 |
C.C. Liu, Y.M. Ferng, and C.K. Shih, "CFD Evaluation of Turbulence Models for Flow Simulation of the Fuel Rod Bundle with a Spacer Assembly", Appl. Therm. Eng., 40, 389-396 (2012).
DOI
|
10 |
G. Hazi, "On Turbulence Models for Rod Bundle Flow Computations", Ann. Nuclear Energy, 32(7), 755-761 (2005).
DOI
|
11 |
M.E. Conner, E. Baglietto, and A.M. Elmahdi, "CFD methodology and validation for single-phase flow in PWR fuel assembly", Nucl. Eng. Des., 240(9), 2088-2095 (2010).
DOI
|
12 |
D. Chang and S. Tavoularis, "Numerical simulation of turbulent flow in a 37-rod bundle", Nucl. Eng. Des., 237(6), 575-590 (2007).
DOI
|
13 |
United States Nuclear Regulatory Commission, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants", U.S. NRC NUREG-0800, 15.7.4 (1981).
|