Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Improvements to MAAP 3. 0B for IPE (individual plant evaluations) analyses

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:5488775
; ; ;  [1]
  1. Fauske Associates, Inc., Burr Ridge, IL (USA)
The MAAP 3.0B code is a coupled thermal-hydraulics and fission product release and transport code for prediction of boiling water reactor and pressurized water reactor (PWR) responses to severe reactor accidents. MAAP 3.0B is maintained by the Electric Power Research Institute to assist in utility performance of IPEs (individual plant evaluations) and other source term calculations. Significant improvements have been made to MAAP 3.0B during 1989, including methods of interest for other code developers. Three improvements are selected for this discussion: (1) a model for flammability and combustion of possible gas mixtures, (2) a model for natural circulation intercompartmental flow including countercurrent flows, and (3) integration diagnostics and control.
OSTI ID:
5488775
Report Number(s):
CONF-891103--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
Country of Publication:
United States
Language:
English

Similar Records

Individual plant evaluation uses of MAAP (modular accident analysis program) 3. 0B
Conference · Sat Dec 31 23:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA) · OSTI ID:6923095

A long-term MAAP 3. 0B analysis of a severe anticipated transient without scram accident in a boiling water reactor
Journal Article · Thu Oct 01 00:00:00 EDT 1992 · Nuclear Technology; (United States) · OSTI ID:6933322

Simulation of loss-of-decay heat removal with MAAP 3. 0B
Conference · Sat Dec 31 23:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA) · OSTI ID:6528899