FAI is recognized in the nuclear industry for its expertise in modeling of severe accident phenomena and comprehensive plant evaluations.  Along with these activities, FAI is extensively involved in developing the technical basis for Severe Accident Management Guidelines (SAMGs) and training in associated areas.   For additional details on how we can support you, CLICK HERE.

In 1981, FAI was selected by the Industry Degraded Core Rulemaking (IDCOR) organization, sponsored by the Atomic Industrial Forum in the United States, to develop an engineering understanding of severe accident phenomena using mathematical models.  FAI then integrated these models into the Modular Accident Analysis Program (MAAP).  Since the beginning, FAI has been the primary code developer for MAAP as well as the maintenance contractor for EPRI.  Currently, the MAAP codes are used worldwide to evaluate the thermal-hydraulic response of the core, the Reactor Coolant System (RCS) and containment as well as the fission product release, transport and deposition during postulated severe accident conditions.

FAI has expanded the MAAP code to model the various current and advanced LWR's, CANDU reactors (in cooperation with Ontario Hydro), and Russian VVER reactors (in cooperation with Westinghouse Brussels).  In addition, FAI has worked with numerous organizations around the world to apply the MAAP codes to support plant specific Probabilistic Risk Assessments (PRA's), Individual Plant Examinations (IPE's), site specific evaluations and other related studies.

FAI was the EPRI contractor to develop the Technical Basis Report for SAMGs for all types of commercial nuclear plants in the USA. This included designs built by Westinghouse, Combustion Engienering, Babcock and Wilcox and General Electric. This report was used by the respective owners's groups to develop the SAMGs that were then implemented at each plant. MAAP has been used to confirm the guidance for a broad spectrum of accident sequences.. FAI has developed the MAAP Accident Response System (MARS), an Accident Management software package which uses actual or simulated plant data to perform a dynamic assessment of the current and future status of a nuclear plant under actual (or simulated) accident conditions.  Graphical user-interface software (MAAP-GRAAPH) and software to calculate in-plant and ex-plant radiation dose (INDOSE and MAAP4-DOSE) were also developed by FAI to assist in the understanding of severe accident phenomena for plant evaluations, training, and emergency drill planning efforts.

The FAI Nuclear Systems Group is staffed by qualified engineers and scientists who participate in all facets of nuclear safety activities, health physics, and equipment qualification  programs.

Please feel free to contact us.

Sincerely,

Robert Henry, Ph.D.
Senior Vice-President
Nuclear Group

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