Combustible Dust Testing

Laboratory testing to quantify dust explosion and reactivity hazards

Safety Data Sheets

Develop critical safety data for inclusion in SDS documents

Gas and Vapor

Laboratory testing to quantify explosion hazards for vapor and gas mixtures

Classification of hazardous materials subject to shipping and storage regulations
Testing and consulting on the explosion risks associated with devices and processes which use or produce hydrogen
Safety Data Sheets

Develop critical safety data for inclusion in SDS documents

Thermal Stability

Safe storage or processing requires an understanding of the possible hazards associated with sensitivity to variations in temperature

Adiabatic Calorimetry
Data demonstrate the consequences of process upsets, such as failed equipment or improper procedures, and guide mitigation strategies including Emergency Relief System (ERS) design
Reaction Calorimetry
Data yield heat and gas removal requirements to control the desired process chemistry
Battery Safety

Testing to support safe design of batteries and electrical power backup facilities particularly to satisfy UL9540a ed.4

Safety Data Sheets

Develop critical safety data for inclusion in SDS documents

Cable Testing
Evaluate electrical cables to demonstrate reliability and identify defects or degradation
Equipment Qualification (EQ)
Testing and analysis to ensure that critical equipment will operate under adverse environmental conditions
Water Hammer
Analysis and testing to identify and prevent unwanted hydraulic pressure transients in process piping
Acoustic Vibration
Identify and eliminate potential sources of unwanted vibration in piping and structural systems
Gas & Air Intrusion
Analysis and testing to identify and prevent intrusion of gas or air in piping systems
ISO/IEC 17025:2017

Fauske & Associates fulfills the requirements of ISO/IEC 17025:2017 in the field of Testing

ISO 9001:2015
Fauske & Associates fulfills the requirements of ISO 9001:2015
Dust Hazards Analysis
Evaluate your process to identify combustible dust hazards and perform dust explosion testing
On-Site Risk Management
On-site safety studies can help identify explosibility and chemical reaction hazards so that appropriate testing, simulations, or calculations are identified to support safe scale up
DIERS Methodology
Design emergency pressure relief systems to mitigate the consequences of unwanted chemical reactivity and account for two-phase flow using the right tools and methods
Deflagrations (Dust/Vapor/Gas)

Properly size pressure relief vents to protect your processes from dust, vapor, and gas explosions

Effluent Handling

Pressure relief sizing is just the first step and it is critical to safely handle the effluent discharge from an overpressure event

FATE™ & Facility Modeling

FATE (Facility Flow, Aerosol, Thermal, and Explosion) is a flexible, fast-running code developed and maintained by Fauske and Associates under an ASME NQA-1 compliant QA program.

Mechanical, Piping, and Electrical
Engineering and testing to support safe plant operations and develop solutions to problems in heat transfer, fluid, flow, and electric power systems
Hydrogen Safety
Testing and consulting on the explosion risks associated with devices and processes which use or produce hydrogen
Thermal Hydraulics
Testing and analysis to ensure that critical equipment will operate under adverse environmental conditions
Nuclear Safety
Our Nuclear Services Group is recognized for comprehensive evaluations to help commercial nuclear power plants operate efficiently and stay compliant
Radioactive Waste
Safety analysis to underpin decomissioning process at facilities which have produced or used radioactive nuclear materials
Adiabatic Safety Calorimeters (ARSST and VSP2)

Low thermal inertial adiabatic calorimeters specially designed to provide directly scalable data that are critical to safe process design

Other Lab Equipment and Parts for the DSC/ARC/ARSST/VSP2 Calorimeters

Products and equipment for the process safety or process development laboratory


Software for emergency relief system design to ensure safe processing of reactive chemicals, including consideration of two-phase flow and runaway chemical reactions


Facility modeling software mechanistically tracks transport of heat, gasses, vapors, and aerosols for safety analysis of multi-room facilities


Our highly experienced team keeps you up-to-date on the latest process safety developments.

Process Safety Newsletter

Stay informed with our quarterly Process Safety Newsletters sharing topical articles and practical advice.


With over 40 years of industry expertise, we have a wealth of process safety knowledge to share.

Published December 7, 2018

Severe Accident Post Fukushima Engineering /MAAP5 Advanced Capabilities


Fukushima severe accident management probabilistic risk assessmentBWR reactor similar to Fukushima Daiichi Unit 1 (Aerial view of Fukushima Daiichi nuclear site in the background).

SAMG Update * MAAP5 Analysis * Level II Risk Analysis * Severe Accident Phenomena * Modular Accident Response System (MARS) Code for On-Line Accident Management * PRA Support * FLEX Equipment Evaluation* Power Coping Strategies for ELAP (Extended Loss of AC Power) Events

Intimately involved in the international response to the TMI-2, Chernobyl and Fukushima Daiichi accidents, Fauske & Associates, LLC (FAI) was founded on expertise in the modeling, evaluation and mitigation of severe accidents at commercial nuclear power plants. FAI employs Probabilistic Risk Assessments, Modular Accident Analysis Programs, and other severe accident modeling techniques and tools to create comprehensive risk profiles, thereby mitigating the risk of future accidents.

FAI has collaborated with the nuclear industry in understanding and preparing for severe accidents at power reactors:

  • In 1980, FAI contributed to the development of the foundation NSAC-1 report, the first analysis of the TMI-2 accident.
  • In 1986, FAI was part of the U.S. mission to Vienna, Austria, where the Soviet Union provided their first technical briefing on the Chernobyl accident to the western European countries.
  • In 2011, FAI helped man the “War Room” in Tokyo that was monitoring Fukushima Daiichi (1F) accident progression during the event and considering strategies for accident response and mitigation.
  • In 2012, FAI joined the Japanese consortium that was tasked by government agency METI with developing technologies to understand accident progression and the subsequent end-state configuration of Units 1, 2, and 3 at the 1F site. This provided comprehension of key phenomena that are crucial to the fundamental understanding of 1F-specific progression.

“Due to its multiple reactor involvement and its occurrence within a conventional Western-style power reactor design, Fukushima Daiichi is a watershed event that has implications for the entire world-wide power reactor fleet, states James Burelbach, PhD, Director of Systems Modeling, FAI.  "FAI’s 30+ years of intensive study and accomplishment in the field has culminated in our industry-leading efforts revealing fundamental lessons from Daiichi.  These tractable, pragmatic lessons are an immediate benefit to plant Operations and Technical Support Committee (TSC) personnel, tasked with executing the Severe Accident Management Guidelines (SAMGs).  Now, they can fulfill their mission with a much advanced expectation of plant response, informed by the Daiichi experience.”

FAI utilizes Probabilistic Risk Assessments (PRAs) and accompanying engineering calculations to quantify the risk profile.  This determines the probability and potential severity of beyond-design-basis phenomena occurring in a nuclear power plant.  FAI has supported Level I and Level II PRA analyses for many plants, dating back to the original individual plant examination (IPE) studies. Also, FAI has developed or enhanced software and methodologies for evaluating severe accident progression.

MAAP probabilistic risk assessment
Engineer using MAAP graphical interface

FAI was the original developer of the Modular Accident Analysis Program (MAAP), which is now an Electric Power Research Institute (EPRI) owned and licensed computer software.  MAAP is a fast-running computer code that simulates the response of light water and heavy water moderated nuclear power plants for both current and Advanced Light Water Reactor (ALWR) designs. It can simulate Loss-Of-Coolant Accident (LOCA) and non-LOCA transients for PRA applications as well as severe accident sequences, including actions taken as part of the Severe Accident Management Guidelines (SAMGs). Originally developed by FAI as part of the Industry Degraded Core Rulemaking (IDCOR) program, there are now several parallel versions of MAAP for BWRs, PWRs, CANDU designs, FUGEN design and the Russian VVER PWR design. FAI continues to support EPRI in MAAP development, and we collaborate with users to meet their particular needs for model customization and PRA applications, including success criteria, timing of operator actions, and room heat-up, as well as SAMG development, full-scope simulators, and automated sensitivity studies.

FAI supports utilities/vendors in a collaborative way for all severe accident issues, including hydrogen, source term, equipment survivability, and atmospheric dispersion and dose.  FAI has unique experience developed in part through performance of a number of key experiments to expand the understanding of severe accidents related to:

  • Direct containment heating
  • Drywell shell thermal interaction with core debris (Liner Melt-through potential)
  • External cooling of core debris in the Reactor Pressure Vessel (RPV) lower plenum.
  • Internal (“in-vessel”) cooling of core debris in the RPV lower plenum.
  • Lower plenum penetration response to thermal attack by core debris
  • Concentric tube cooling
  • Core debris jet thermal attack on adjacent tube pairs


Stay up to date on the latest in severe accident modeling, testing and solutions, and other process safety news by subscribing to our blog below.

Subscribe Now

Sign up for our newsletter to Get all the latest information

Share this article

Find more resources articles