- Process Safety Newsletter - Winter 2012 Edition
- Dust & Flammability Safety Training Courses – Spring 2012
- FAI User's Group Forum – Spring 2012
- Relief System Design Course – Spring 2012
- FAI Announces ISO 17025 Accreditation!
- OSHA & NFPA 654 Testing Services
- ChemiSens Reaction Calorimeter
- Press Release - PrEVent
- Press Release -Dust Explosion Testing
- Press Release - MAAP5 Code Development
- Press Release- 18 Years Without Lost-Time Injury
- Press Release- FAI Announces New Lab Capabilities
MAAP* - Modular Accident Analysis Program
The Modular Accident Analysis Program (MAAP) Version 4 is a computer code that simulates the response of light water and heavy water moderated nuclear power plants, both current designs and Advanced Light Water Reactors (ALWRs), during severe accident sequences, including actions taken as part of the Severe Accident Management Guidelines (SAMGs). There are several parallel versions of MAAP4*, one each for BWRs, PWRs, CANDUs, the FUGEN design and the Russian VVER PWR design.
MAAP4* also includes a graphical interface, MAAP4*-GRAAPH, to increase the analytical capability as well as enhancing the review function. Specifically, the user can interactively interface with the code during execution to modify the status of on-site power, pumps, valves, etc., as well as, to directly observe the results.
MAAP* was originally developed by Fauske & Associates, LLC as part of the Industry Degraded Core Rulemaking (IDCOR) program. The previous major revision, MAAP*-3B, was developed by EPRI to support the plant-specific Individual Plant Examinations (IPEs). Since the beginning, FAI has developed and maintained the code under the sponsorship of the Electric Power Research Institute (EPRI) and the MAAP Users Group (MUG).
MAAP4* is the latest version of MAAP* and has completed final acceptance testing at EPRI for release to the MAAP4* sponsors. The MAAP4* code builds on the substantial modeling enhancements over MAAP4* to assess the approach to, and progression of, severe accidents in the BWRs and PWRs operated in the western hemisphere and extends these to the plant specific features that are presently represented in the state-of-the-art models for PRAs/PSAs, SAM
Gs, EOPs, and full scope control room simulators. These substantial enhancements include PWR RCS model improvement, containment model improvements which can perform Design Basis Accidents analyses with either a single node or multi-node containment model, coupled Dose calculation, 1-D neutronic and a point kinetic models, and many other improvements.
The MAAP4* PWR RCS model includes increased nodalization of RCS to individually represent each steam generator in the design, the two-phase flow regime is modeled in each node using the EPRI drift flux model to provide the mixture density in the node and the appropriate flow regime. This increased nodalization also enables each cold leg and hot leg to be represented including those designs with 4 cold legs and 2 hot legs. This also enables the model to evaluate the operating state with one or more of the RCPs shut down. The MAAP4* code can calculate the single phase and two-phase natural circulation flows for the reactor core and each of the steam generators that has the capability to participate in the natural circulation flow.
*-MAAP is owned by EPRI (Electric Power Research Institute, Inc.) EPRI Website
For more information, please contact us.