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Nuclear Technology Volume 119, 1997 - Issue 3

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Technical Paper

Effect of RELAP5/MOD3.2 User Options on Calculated Results

John D. BurttIdaho National Engineering and Environmental Laboratory 11428 Rockville Pike. Suite 410, Rockville, Maryland 20852

Louis M. ShotkinU.S. Nuclear Regulatory Commission, Mail Stop T-10E37, Washington, D.C. 20555

Joseph L. StaudenmeierU.S. Nuclear Regulatory Commission, Mail Stop T-10E37, Washington, D.C. 20555

Pages 244-268 | Published online: 10 May 2017

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https://doi.org/10.13182/NT97-A35401

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AP600 Standard Safety Analysis Report, Rev. 1 (Jan. 13, 1994) and Rev. 3 (May 31, 1995).
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THE RELAP5 DEVELOPMENT TEAM, “RELAP5/MOD3 Code Manual,” NUREG/CR-5535, Idaho National Engineering and Environmental Laboratory (1995).
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M. ORTIZ et al., “Adequacy Evaluation of RELAP5/MOD3 for Simulating Small Break Loss of Coolant Accidents, Volume 2: Horizontal Integrated Analysis of the AP6001” Diameter Cold Leg Break, Appendix B: AP6001” Cold Leg Break Counterpart Calculation,” INEL-96/0380, App. B, Idaho National Engineering and Environmental Laboratory (Oct. 1996).
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