TMI-2 analysis using SCDAP/RELAP5/MOD3.1

Technical Report · Tue Nov 01 04:00:00 EST 1994

DOI:https://doi.org/10.2172/28419· OSTI ID:28419

Hohorst, J K; Polkinghorne, S T; Siefken, L J; Allison, C M; Dobbe, C A

SCDAP/RELAP5/MOD3.1, an integrated thermal hydraulic analysis code developed primarily to simulate severe accidents in nuclear power plants, was used to predict the progression of core damage during the TMI-2 accident. The version of the code used for the TMI-2 analysis described in this paper includes models to predict core heatup, core geometry changes, and the relocation of molten core debris to the lower plenum of the reactor vessel. This paper describes the TMI-2 input model, initial conditions, boundary conditions, and the results from the best-estimate simulation of Phases 1 to 4 of the TMI-2 accident as well as the results from several sensitivity calculations.

• Research Organization: Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 28419
• Report Number(s): INEL--94/0157; ON: TI95008576
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
DESIGN BASIS ACCIDENTS
HYDRAULICS
MELTDOWN
NUCLEAR POWER PLANTS
S CODES
TEMPERATURE DEPENDENCE
THREE MILE ISLAND-2 REACTOR