Combustible Dust Testing

Laboratory testing to quantify dust explosion & reactivity hazards

Flammable Gas & Vapor Testing

Laboratory testing to quantify explosion hazards for vapor and gas mixtures

Chemical Reactivity Testing

Laboratory testing to quantify reactive chemical hazards, including the possibility of material incompatibility, instability, and runaway chemical reactions

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 safety handle the effluent discharge from an overpressure event

Thermal Stability

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

UN-DOT

Classification of hazardous materials subject to shipping and storage regulations

Safety Data Sheets

Develop critical safety data for inclusion in SDS documents

Biological

Model transport of airborne virus aerosols to guide safe operations and ventilation upgrades

Radioactive

Model transport of contamination for source term and leak path factor analysis

Fire Analysis

Model transport of heat and smoke for fire analysis

Flammable or Toxic Gas

transport of flammable or toxic gas during a process upset

OSS consulting, adiabatic & reaction calorimetry and consulting

Onsite safety studies can help identify explosibility and chemical reaction hazards so that appropriate testing, simulations, or calculations are identified to support safe scale up

Mechanical, Piping, and Electrical

Engineering and testing to support safe plant operations and develop solutions to problems in heat transfer, fluid flow, electric power systems

Battery Safety

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

Hydrogen Safety

Testing and consulting on the explosion risks associated with devices and processes which use or produce hydrogen

Spent Fuel

Safety analysis for packaging, transport, and storage of spent nuclear fuel

Decommissioning, Decontamination and Remediation (DD&R)

Safety analysis to underpin decommissioning process at facilities which have produced or used radioactive nuclear materials

Laboratory Testing & Software Capabilities

Bespoke testing and modeling services to validate analysis of DD&R processes

Nuclear Overview

Our Nuclear Services Group is recognized for comprehensive evaluations to help commercial nuclear power plants operate efficiently and stay compliant.

Severe Accident Analysis and Risk Assessment

Expert analysis of possible risk and consequences from nuclear plant accidents

Thermal Hydraulics

Testing and analysis to ensure that critical equipment will operate under adverse environmental conditions

Environmental Qualification (EQ) and Equipment Survivability (ES)

Testing and analysis to ensure that critical equipment will operate under adverse environmental conditions

Laboratory Testing & Software Capabilities

Testing and modeling services to support resolution of emergent safety issues at a power plant

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 (DSC/ARC supplies, CPA, C80, Super Stirrer)

Products and equipment for the process safety or process development laboratory

FERST

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

FATE

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

Blog

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.

Resources

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

Recent Posts

Severe Accident Post Fukushima Engineering /MAAP5 Advanced Capabilities

Posted by The Fauske Team on 12.07.18

 

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

Topics: severe accident, MAAP, nuclear

cta-bg.jpg

Is My Dust Combustible?

A Flowchart To Help You Decide
Download Now