Scaling analysis for the OSU AP600 test facility (APEX)

Author:

Reyes Jose N.,Hochreiter Lawrence

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference31 articles.

1. American National Standard for Decay Heat Power in Light Water Reactors, 1979. American Nuclear Society, LaGrange, IL, ANSI/ANS-5.1.24.

2. Boucher, T.J., Ortiz, M.G., Palmrose, D.E., Modro, S.M., 1994. Scaling and design of LSTF modifications for AP600 testing. Idaho National Engineering Laboratory, INEL-94/0200, NUREG/CR-6066, November 1994.

3. Briggs, J., Peat, F.D., 1989. Turbulent Mirror. Harper and Row Publishers, New York.

4. Burtt, J.D., Fletcher, C.D., Wilson, G.E., Davis, C.B., et al., 1996. Phenomena Identification and Ranking Tables for Westinghouse AP600 Small Break Loss-of-Coolant Accident, Main Steam Line Break, and Steam Generator Tube Rupture Scenarios. Idaho National Engineering Laboratory, INEL-94/0061, Revision 2, November 1996.

5. Davis, C.B., Bayless, P.D., Fisher, J.E., Roth, P.A., 1996. Evaluation and assessment of RELAP5/MOD3 version 3.2.1.2 for simulating the long-term phase of small break loss-of-coolant accidents in the AP600. Idaho National Engineering Laboratory, INEL-96/0395, October 1996.

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