ICECON: a computer program used to calculate containment back pressure for LOCA analysis (including ice condenser plants). [PWR]

Technical Report · Thu Jul 01 00:00:00 EDT 1976

OSTI ID:7252054

The ICECON computer code provides a method for conservatively calculating the long term back pressure transient in the containment resulting from a hypothetical Loss-of-Coolant Accident (LOCA) for PWR plants including ice condenser containment systems. The ICECON computer code was developed from the CONTEMPT/LT-022 code. A brief discussion of the salient features of a typical ice condenser containment is presented. Details of the ice condenser models are explained. The corrections and improvements made to CONTEMPT/LT-022 are included. The organization of the code, including the calculational procedure, is outlined. The user's manual, to be used in conjunction with the CONTEMPT/LT-022 user's manual, a sample problem, a time-step study (solution convergence) and a comparison of ICECON results with the results of the NSSS vendor are presented. In general, containment pressure calculated with the ICECON code agree with those calculated by the NSSS vendor using the same mass and energy release rates to the containment.

• Research Organization: Exxon Nuclear Co., Inc., Richland, Wash. (USA)
• OSTI ID: 7252054
• Report Number(s): XN-CC-39; TRN: 77-000171
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
I CODES
CONTAINMENT SYSTEMS
PRESSURE GRADIENTS
LOSS OF COOLANT
MATHEMATICAL MODELS
PWR TYPE REACTORS
REACTOR SAFETY
ECCS
ACCIDENTS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled