Benchmarking and Qualification of Retran-03 for BWR Stability Analysis by Comparison with Frequency-Domain Stability Analysis Code

Author:

Mori Michitsugu1

Affiliation:

1. Tokyo Electric Power Company, Inc. Nuclear Power Research and Development Center 4-1 Egasaki-cho, Tsurumi-ku, Yokohama 230, Japan

Publisher

Informa UK Limited

Subject

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

Reference10 articles.

1. S. J. PENG et al. “NUFREQ-NP: A Digital Computer Code for Linear Stability Analysis of Boiling Water Nuclear Reactors,” NUREG/CR-4116, U.S. Nuclear Regulatory Commission (July 1985).

2. J. M. SORENSEN et al. “The Reactor Analysis Support Package (RASP), Vol. 9: BWR Stability Analysis,” EPRI-NP-4498, Electric Power Research Institute (Mar. 1988).

3. K. HORNYIK and J. A. NASER, “RETRAN Analysis of the Turbine Trip Tests at Peach Bottom Atomic Power Station Unit 2 at the End of Cycle 2,” EPRI NP-1076-SR, Electric Power Research Institute (Apr. 1979).

4. N. N. LARSEN et al. “Core Design and Operating Data for Cycle 1 and 2 of Peach Bottom 2,” EPRI NP-563, Electric Power Research Institute (June 1978).

5. L. A. CARMICHAEL and R. O. NIEMI, “Transient and Stability Tests at Peach Bottom Atomic Power Station Unit 2 at End of Cycle 2,” EPRI NP-564, Electric Power Research Institute (June 1978).

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