Effect of RELAP5/MOD3.2 user options on calculated results
- Idaho National Engineering and Environmental Lab., Rockville, MD (United States)
- Nuclear Regulatory Commission, Washington, DC (United States)
Calculations were performed for the same accident scenario in the same power plant geometry using the same version of the RELAP5/MOD3.2 computer code, but each calculation was performed using different user options in the code input deck. The accident scenario analyzed was a 1-in. cold-leg break in the new Westinghouse AP600 design. The calculations were analyzed for those key events leading to actuation of the AP600 automatic depressurization system. Three different user choices for plant system noding were used: (a) a detailed noding with a quasi-three-dimensional vessel; (b) a simplified system noding with a quasi-three-dimensional core, lower plenum, and upper plenum, but a simplified downcomer noding; and (c) a detailed system and downcomer noding, but a one-dimensional core, lower plenum, and upper plenum. Two other user options were separately exercised, i.e., shutting off the model for thermal stratification and using different initial temperatures for the core. The discussion focuses on the relative effect of these different user options on flow through the P-loop hot leg, initial reversal in flow through the pressure balance line, timing of draining of the core makeup tanks, and timing of actuation of the automatic depressurization system.
- OSTI ID:
- 531503
- Journal Information:
- Nuclear Technology, Vol. 119, Issue 3; Other Information: PBD: Sep 1997
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effects of entrainment in the upper plenum during an SBLOCA in the AP600
RELAP5/MOD3. 1 simulation of inadvertent initiation of SBWR passive safety features