Nuclear Safety Consulting
Fauske & Associates' Nuclear Services Group is recognized for comprehensive plant evaluations to help clients enhance the availability and reliability of their operating plants while maintaining regulatory compliance, extending plant life, and reducing operation and maintenance costs in commercial nuclear power plants in the United States and overseas.
FAI has a robust quality assurance system to meet stringent requirements required in the Nuclear industry, and have the following certifications:
- ISO 9001
- 10CFR 50 Appendix B
- ISO/IEC 17025
- TickIT
Consulting Experience
Thermal Hydraulic Analysis
Thermal hydraulic analysis including detection and mitigation of water hammer events and resonance issues through simulation tools and sub-scale testing: FAI has decades of experience using RELAP5, a key industry recognized thermal hydraulic transient analysis software. Our experimental facilities are designed to conduct thermal hydraulic tests, including non-condensable gas-water or steam-water water hammer experiments.
Equipment Qualification (EQ) Testing
FAI brings Design Basis Accident (DBA) testing, including Loss of Coolant Accident (LOCA) and High Energy Line Break (HELB) testing capabilities to a variety of applications for equipment qualifications.
Probabilistic Risk Assessment (PRA)
FAI utilizes Probabilistic Risk Assessments (PRA) to gauge the probability of risk by using calculations to determine the potential, probability and possible severity of unwanted phenomena occurring in a nuclear power plant. FAI has developed extensive capabilities and experience in performance of NRC classified Level II risk analysis specifically focused on the potential for accidents that could release radioactivity from the facility. MAAP can simulate Loss-Of- Coolant Accident (LOCA) and non-LOCA transients for PRA applications.
Environmental Qualification (EQ)
This is the process of establishing the ability of an equipment to perform its intended function under prescribed operating conditions. This can be established through a combination of tests performed in a laboratory along with calculations.
Commonly performed tests for EQ are:
- Baseline functional test
- Radiation aging
- Post-radiation aging functional test
- Thermal aging
- Post-thermal aging functional test
- Cycle aging
- Post-cycle aging functional test
- Seismic test
- Post-seismic functional test
- High Energy Line Break (HELB) test
- Post-HELB functional test and visual inspection
- Water ingress
Equipment Survivability (ES)
Assessments are performed to evaluate the availability of the equipment and instrumentation during a severe accident.
Severe Accident Analysis
Fauske and Associates (FAI) experience in severe accident analysis goes back to the original experiments and computer modeling that led to initial development of the EPRI-owned MAAP code. FAI later was the principal author of the original Severe Accident Management (SAM) Technical Basis Report (TBR) also known as EPRI TR-101869). This report provided the technical bases for development of generic severe accident management guidance (SAMG).
In the aftermath of the Fukushima accident, EPRI commissioned an update to the original TBR, and FAI again was a principal author in this update.
In the aftermath of the Fukushima accident, EPRI commissioned an update to the original TBR, and FAI again was a principal author in this update.
Decommissioning and Decontamination
Fauske & Associates (FAI) provides technical expertise and program guidance for the storage, processing and disposal of nuclear, chemical and defense waste and for process and safety analysis to support Decontamination & Decommissioning (D&D) of nuclear and hazardous material facilities. Our three product areas for waste technology and D&D are (1) Process and safety models and analyses (2) Experimental facilities for hazard quantification and (3) The FAI developed and maintained FATE™ software. FATE™ is used for process design and safety evaluations related to waste technology, process engineering and safety and decommissioning and dismantling. It can consider engineering process components as well as facility design.
Laboratories and Testing Capability
FAI has several fully staffed laboratories with equipment such as a LOCA chamber, a thermal aging autoclave, and a thermal hydraulic loop supporting environmental qualifications, condition assessment, full-scale thermal/hydraulics experiments, and basic physical sciences.
Accident Investigation
FAI was founded on expertise in the modeling, evaluation and mitigation of severe accidents at commercial nuclear power plants, and has been intimately involved in the international response to the TMI-2, Chernobyl and Fukushima Daiichi accidents.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.