Skip navigation.

  ASMEDL.ORG »  Journals »  J. Fluids Eng. »  Volume 131 »  pp. 121401
Adjust text size: Decrease font size Increase font size

Journal of Fluids Engineering
Volume: Page/CID:

Previous Article
Unsteady Velocity Profiles in Laminar and Turbulent Water Hammer Flows
The behavior of unsteady velocity profiles in laminar and turbulent water hammer flows is numerically investigated. In this way, the governing equations for the quasitwo-dimensional equations of trans...
Next Article
Improving the Spatial Resolution and Stability by Optimizing Compact Finite Differencing Templates
Parameter optimization is an excellent path for easily raising the resolution efficiency of compact finite differencing schemes. Their low-resolution errors are attractive for resolving the fine-scale...

Application of Fractional Scaling Analysis to Loss of Coolant Accidents: Component Level Scaling for Peak Clad Temperature

J. Fluids Eng.  -- December 2009 --  Volume 131,  Issue 12, 121401 (8 pages)
doi:10.1115/1.4000370

You are not logged into the ASME Digital Library.
Log in

Author(s):
Ivan Catton
UCLA–MAE, P.O. Box 951597, 48-121 Engineering IV, Los Angeles, CA 90195-1597

Wolfgang Wulff
11 Hamilton Road, Setauket, NY 11733

Novak Zuber
703 New Mark Esplanade, Rockville, MD 20850

Upendra Rohatgi
Brookhaven National Laboratory, Building 475B, Upton, NY 11973 USA
Fractional scaling analysis (FSA) is demonstrated here at the component level for depressurization of nuclear reactor primary systems undergoing a large-break loss of coolant accident. This paper is the third of a three-part sequence. The first paper by Zuber et al. (2005, “Application of Fractional Scaling Analysis (FSA) to Loss of Coolant Accidents (LOCA), Part 1. Methodology Development,” Nucl. Eng. Des., 237, pp. 1593–1607) introduces the FSA method; the second by Wulff et al. (2005, “Application of Fractional Scaling Methodology (FSM) to Loss of Coolant Accidents (LOCA), Part 2. System Level Scaling for System Depressurization,” ASME J. Fluid Eng., to be published) demonstrates FSA at the system level. This paper demonstrates that a single experiment or trustworthy computer simulation, when properly scaled, suffices for large break loss of coolant accident (LBOCAs) in the primary system of a pressurized water reactor and of all related test facilities. FSA, when applied at the system, component, and process levels, serves to synthesize the world-wide wealth of results from analyses and experiments into compact form for efficient storage, transfer, and retrieval of information. This is demonstrated at the component level. It is shown that during LBOCAs, the fuel rod stored energy is the dominant agent of change and that FSA can rank processes quantitatively and thereby objectively in the order of their importance. FSA readily identifies scale distortions. FSA is shown to supercede use of the subjectively implemented phenomena identification and ranking table and to minimize the number of experiments, analyses and computational effort by reducing the evaluation of peak clad temperature (PCT) to a single parameter problem, thus, greatly simplifying uncertainty analysis.

©2009 American Society of Mechanical Engineers

History: Received 28 May 2009; revised 8 September 2009; published 19 November 2009
doi: http://dx.doi.org/10.1115/1.4000370

KEYWORDS and PACS

Keywords
PACS
  • 28.41.Te
    Fission reactor protection systems, safety, radiation monitoring, accidents, and dismantling
  • 28.41.Fr
    Fission reactor coolants, reactor cooling, and heat recovery
  • 28.41.Ak
    Theory, design, and computerized simulation of fission reactors
  • YEAR: 2009

RELATED DATABASES


To view database links for this article,
you need to log in.
To view database links for this article,
you need to log in.

PUBLICATION DATA

Coden:
JFEGA4
ISSN:
0098-2202 (print)   1528-901X (online)
Publisher:
AIP is a member of CrossRef ASME

REFERENCES (4)

For access to fully linked references, you need to log in. For access to fully linked references, you need to Log in.

CITING ARTICLES

For access to citing articles, you need to log in.
For access to citing articles, you need to Log in.