Numerical diffusion and the tracking of solute fields in system codes: Part III. Application to a boron dilution transient analysis in the AP600

Nuclear Engineering and Design

Volumn 179, Issue 3, 1998, Pages 345-356

  Macian Juan, Rafael ^a   Ivanov, Kostadin ^a   Mahaffy, John H ^a  

^a PENNSYLVANIA STATE UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0000436162     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(97)00291-4     Document Type: Article

References (17)

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2. Bandini, B.R., 1990. A Three-Dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal-Hydraulic Computer Code. PhD thesis, Pennsylvania State University.
3. Diamond, D.J., 1990. Reactivity Accidents. A Reassessment of the Design Basis Events. Brookhaven National Laboratory, NUREG/CR-5368.
4. Edenius, M., Forssen, B., 1989. CASMO-3. A Fuel Assembly Burnup Program, User's Manual. STUDSVIK/NFA-89/3.
5. Finnemann, H., 1977. Interface current technique for multidimensional reactor calculations. Atomkernenergie 30, 123.
6. Hyvarinen, J., 1992. An Inherent Boron Dilution Mechanism in Pressurized Water Reactors. Finnish Center for Radiation and Nuclear Safety, STUK.
7. Ivanov, K., 1996. TMI MSLB analysis using TRAC-PF1 coupled with three-dimensional kinetics. Proc. ICONE-4 3, 33.
8. Jacobson, S., 1990. Reactivity transients after pump start in a boron diluted loop. ANS Trans 61, 223-224.
9. Jacobson, S., 1992. Risk Evaluation of Local Dilution Transients in Pressurized Water Reactors. PhD thesis, Linkoping University.
10. Leonard, B.P., 1991. The ULTIMATE conservative difference scheme applied to unsteady one-dimensional advection. Comput. Methods Appl. Mech. Eng. 88, 17.
11. Lime, J., 1995. Steady State and Transient Decks for SBLOCA AP600 Analysis. Los Alamos National Laboratory.
12. Macian, R., 1996. A Study of High Order Solute Tracking in System Codes. PhD thesis, Pennsylvania State University.
13. Macian, R., Mahaffy, J.H., 1998a. Numerical diffusion and the tracking of solute fields in system codes. Part I. One-dimensional flows. Nucl. Eng. Des. 179, 297-319.
14. Macian, R., Mahaffy, J.H., 1998b. Numerical diffusion and the tracking of solute fields in system codes. Part II. Multidimensional flows. Nucl. Eng. Des. 179, 321-341.
15. Macian, R., Tyler, T.N., Mahaffy, J.H., 1998. Large break loss of coolant accident analysis using TRAC-PF1 and three-dimensional kinetics. Nucl. Eng. Des. 19 (in press).
16. Smolarkievicz, P.K., 1984. A fully multidimensional positive definite advection transport algorithm with small implicit diffusion. J. Comput. Phys. 54, 325.
17. Wardman, P., 1995. AP600 SSAR Mark-ups: chap 15, section 6.2 and 6.4, DCP/WMS0809. section 15.2.7. Loss of Normal Feedwater Flow. Westinghouse Internal Report.