Advanced SearchSearch Tips
Theoretical Estimation of the Impact Velocity during the PWR Spent Fuel Drop in Water Condition
facebook(new window)  Pirnt(new window) E-mail(new window) Excel Download
 Title & Authors
Theoretical Estimation of the Impact Velocity during the PWR Spent Fuel Drop in Water Condition
Kwon, Oh Joon; Park, Nam Gyu; Lee, Seong Ki; Kim, Jae Ik;
  PDF(new window)
The spent fuel stored in the pool is vulnerable to external impacts, since the severe reactor conditions degrade the structural integrity of the fuel. Therefore an accident during shipping and handling should be considered. In an extreme case, the fuel assembly drop can be happened accidentally during handling the nuclear fuel in the spent fuel pool. The rod failure during such drop accident can be evaluated by calculating the impact force acting on the fuel assembly at the bottom of the spent fuel pool. The impact force can be evaluated with the impact velocity at the bottom of the spent fuel pool. Since fuel rods occupies most of weight and volume of a nuclear fuel assembly, the information of the rods are important to estimate the hydraulic resistance force. In this study, the hydraulic force acting on the short rod bundle model during the drop accident is calculated, and the result is verified by comparing the numerical simulations. The methodology suggested by this study is expected to be useful for evaluating the integrity of the spent fuel.
Spent fuel;Drop accident;Impact velocity;
 Cited by
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).

United States Nuclear Regulatory Commission, "Control of Heavy Loads at Nuclear Power Plants", U.S. NRC NUREG-0612, 2.1 (1980).

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).

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). crossref(new window)

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).

American National Standards Institute(ANSI)/Ameri-can Nuclear Society(ANS)-57.5-1996, Light Water Reactors Fuel Assembly Mechanical Design and Evaluation (2006).

R.D. Blevins , "Applied Fluid Dynamics Handbook", Krieger, Florida (2003).

I.E. Idelchik, "Handbook of Hydraulic Resistance", 3rd Edition, CRC Press, London (1994).

F. M. White, "Fluid Mechanics", 5th Edition, McGraw-Hill, New York (2002).

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). crossref(new window)

G. Hazi, "On Turbulence Models for Rod Bundle Flow Computations", Ann. Nuclear Energy, 32(7), 755-761 (2005). crossref(new window)

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). crossref(new window)

D. Chang and S. Tavoularis, "Numerical simulation of turbulent flow in a 37-rod bundle", Nucl. Eng. Des., 237(6), 575-590 (2007). crossref(new window)