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Fauske and Associates (FAI) has announced that it has developed the Modular Accident Analysis Program 5 (MAAP5) code.

MAAP5 is designed to provide a wide range of plant evaluations in support of probabilistic risk assessment (PRA), design basis evaluations and plant evaluation for all operating needs.

MAAP5’s predecessor, MAAP4, has supported the nuclear industry for the past 15 years.

The MAAP5 features: a new PWR RCS model; a generalised containment model (GCM); new MAAP5-GRAAPH representation for PWRs and BWRs; the MAAP5-DOSE; and the 1-D neutronics model.

Code documentation for MAAP has been delivered to the Electric Power Research Institute (EPRI) and is available to MAAP5 sponsors through the EPRI.

FAI developed the MAAP code in 1981, following the partial core meltdown at Three Mile Island, under the sponsorship of the EPRI and the MAAP Users Group (MUG).

The accident led the nuclear-powerplant industry to develop the MAAP computer code as part of the industry-degraded core rule-making (IDCOR) programme.

Upon the dissolution of IDCOR, ownership of the modular code transferred to the EPRI and a period of enhancements began.

Since that time, FAI has maintained and continued to improve MAAP.

Dr Robert Henry, senior vice-president at FAI, said: ‘MAAP5 code builds on the MAAP4 code severe-accident knowledge base and has substantial modelling enhancements that extend the representation of plant-specific features that are considered in the state-of-the-art models for PRAs/PSAs, SAMGs, EOPs and full-scope control-room simulators.’

Fauske and Associates

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