An SAS3D Analysis of Unprotected Loss-of-Flow Transients for 1200-MW(electric) Liquid-Metal Fast Breeder Reactor Homogeneous and Heterogeneous Core Designs

Author:

Shih T. A.1,Temme M. I.1

Affiliation:

1. General Electric Company Advanced Reactor Systems Department, 310 DeGuigne Drive, P.O. Box 5020, Sunnyvale, California 94086

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference6 articles.

1. J.L. McELROY et al. “Clinch River Breeder Reactor Plant,” CRBRP-GEFR-00103, Topical Report, General Electric Company (1978).

2. F. E. DUNN et al. “The SAS2A LMFBR Accident Analysis Computer Code,” ANL-8138, Argonne National Laboratory (1974).

3. D. H. CHO, R. O. IVINS, and R. W. WRIGHT, “A Rate-Limited Model of Molten-Fuel/Coolant Interactions: Model Development and Preliminary Calculation,” ANL-7919, Argonne National Laboratory (1972).

4. D. A. CANTLEY, G. R. HALL, and C. N. CRAIG, “Axial Expansion of Mixed-Oxide Fuel Measured In-Pile,” GEAP-10403, General Electric Company (1971).

5. R. E. KAISER and S. G. CARPENTER, “Small-Sample Predictions of Radial and Axial Expansion Effects in ZPPR Assembly 5,” ANL-RDP-42, Argonne National Laboratory (1975).

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