PCTRAN is the most successful desktop simulator for all types of light water nuclear reactors. It is specifically designed for many different plant types, including PWR, BWR, advanced AREVA EPR, Westinghouse AP1000, GE ABWR, and ESBWR. PCTRAN's simulation scope extends to severe accidents and dose dispersion. Since its first introduction in 1985 by Micro-Simulation Technology, PCTRAN has been selected by the IAEA as the training platform for its annual Advanced Reactor Simulation workshop. Plant-specific models have been installed at nuclear power plants and institutions all over the world for practical application in training, analysis, probabilistic safety assessment, and emergency exercises.
Recent (2011) Licensees
- The Center of Nuclear Technology Education Consortium (NTEC) in UK at University of Manchester has acquired our AP1000 and EPR modules. The consortium is formed by 12 UK universities for education in support for transition the British nuclear power generation from GCR into G3 PWR era. The software will be used in its dedicated "reactor codes and simulator suite" laboratory to run the simulator courses. These universities grants Master and PhD degrees in addition to technical training in various fields.
- Nanking University of Aeronautics and Astronautics (NUAA) has acquired AP1000 module for its education and research.
- Fukui University of Technology in Japan has got the latest versions of PCTRAN of PWR and BWR. It expands the capability to cold startup in normal operation and Fukushima-type severe accidents.
- Tsinghua University in Beijing, China has obtained AP-1000 for its human factor study.
- Tsinghua University in Taiwan has obtained the high-temperature gas reactor model for its joint project between Taiwan and US on Generation 4 reactor development.
- Stevens Institute of Technology in New Jersey got both PWR and BWR for its new nuclear engineering program.
IAEA Award of a VVER-1000 Simulator for Vietnam
The United Nations agency has awarded a contract to MST to prepare a PC-based simulator of the Russian-designed NPP for Vietnam Agency for Radiation and Nuclear Safety (VARANS). It was delivered and a training class was conducted in Hanoi in March of 2011.
The August 23 earthquake at the North Anna Nuclear Plant site at Mineral, Virginia in USA was measured Scale 5.8 – “uncomfortably close” to its design limit of 6.2. There are 2 units of Westinghouse 3-loop PWR of 900 MW electric output each. Four diesel generators started as expected after the grid loss and reactor shutdown. But one failed shortly after and the remaining three were able to provide heat removal. The grid was later recovered so that no damage has occurred. Should more diesels fail or the grid power not resumed for as little as 5 hours, our analysis shows that the consequence could be serious.
North Anna is basically the same as the Spanish Vandellos II and Taiwanese Maanshan (Horse Saddle Mountain) plants. MST has delivered its PCTRAN plant specific models to both sites since early 90’s and thus is familiar with their transient and accident behavior. For an earthquake-induced loss of offsite power (LOOP) event the FSAR has analyzed both with and without onsite diesel generator events. Without onsite AC it is called station blackout (SBO). Lack of core, containment and spent fuel pool cooling the plant will enter into a severe accident. The link is our study of the plant condition till late stage with failed core and dose release. (New)
Unit 1 analysis was first completed within one week after the earthquake. Article was published in Nuclear Engineering International magazine July of 2011 issue. The "atomic forensics" was cited by New York Times on April 3, 2011.
Unit 3 study
Unit 4 spent fuel pool fire analysis is now available.
Stress Test for NPP (New)
The European Union and many parts of the world have ordered "stress test" at their plants against earthquakes as well as from disruptions of cooling systems. The integrity of operational systems, back-up systems and overall design will be challenged in the event of power or emergency water supply cuts. The result of the test will justify whether continued operation, modification or early retirement.
To conduct dynamic tests for a full spectrum of initial and boundary conditions using any traditional accident analysis method is a time-consuming and labor-intensive task. A single run could take weeks to reach meaningful results. It happens that we did a very similar work for the Ginna plant of Constellation Energy during its extended power upgrade (from 1560 MW to 1775 MW thermal) in 2005. The success criterion was the core degradation frequency (CDF) would not be significantly increased as a result of the upgrade. By using PCTRAN/PWR for the Westinghouse 2-loop plant, we have done numerous loss-of-power, loss-of-coolant inventory, delayed operator action, etc. cases and submitted the report. It was independently reviewed and endorsed by the vendor and approved by USNRC. The plant also won a 20-year life extension in 2006.
Based on this success, Constellation Energy ordered plant specific model for its other C-E designed plant Calvert Cliffs in 2009. An extensive set of PRA Success Criteria Determination was conducted that is essentially equivalent to the post-Fukushima Stress Test. The report was completed in 2010.
Three Colleges in Texas
Wharton County Junior, Brazosport, and Victoria College - have received multiple federal and state grants to establish training programs for licensed and non-licensed workers of nuclear power plants. These three colleges used a portion of their grant money to acquire PCTRAN as the backbone of their simulation laboratory. A number of Texas institutions and utilitities have formed the Nuclear Power Institute whose goal is to establish INPO-accredited training programs. South Texas Project operates two PWR units and is also building two units of ABWR by Toshiba.
Selection of Plant Type for New Construction
In consideration of new plant construction, we all know that:
- ABWR has the longest operating record among the G3 types.
- AP1000 and ESBWR have all passive emergency core and containment cooling systems.
- EPR has the most elaborated four independent trains of ECCS, double containment and debris collecting system.
- VVER has large thermal margin in its horizontal SG design.
- Japanese APWR and Korean APR have advanced fluidic device in saving ECCS water consumption and some G3 concept application.
- Revised CPR-1000 (3-loop PWR) has proven safety record, fit to regional power grid and shortened contruction time.
If it is hard to select one from the above, why don't you have them all? You can use all of our PTRAN simulator products to compare the respective dynamc performance and safety margin during normal and accidental conditions. Train your technical staff, show to the manegerial and political leaders to make a point, etc. Two national agencies of Mexico and Pakistan have done exactly that. Huge discount applies for a package deal.
The Mexican Institute of National Nuclear Investigation has selected PCTRAN for its LaGuna Verde (GE BWR5) severe accident analysis. The package delivered also contains G3 models of AP1000, EPR, ESBWR, ABWR, and TRIGA models.
The Pakistan Nuclear Regulatory Authority has selected PCTRAN for its Chasma (PWR 2-loop 300 MW) severe accident analysis. The package also contains G3 models of PWR 3-loop, EPR, AP1000, and off-site dispersion projection.
Works completed in 2009
MST has successfully developed a prototype simulator for a High Temperature Gas-Cooled Reactor ((HTGR). The purpose of this project was to create a platform for the development of simulators for all types of helium-cooled reactors. The prototype is 600 MW and generates helium gas at 850C. But the reactor size, power level, gas temperature, and energy conversion system can all be scaled or re-designed for any specific design.
For Generation II and III plants, we provide a complete line for power plant safe operation and radiation protection. It covers:
The PCTRAN simulator package is positioned as a crucial tool for existing industry companies and emerging institutions considering the nuclear option. Installed in hundreds of installations all over the world, it has a proven track record of effectiveness in training, engineering analysis, probabilistic safety assessment, and emergency preparedness.
Oak Ridge National Laboratory has acquired a PCTRAN new reactor model
MST has delivered a new reactor PCTRAN model to the national lab's Advanced Reactor Systems and Safety Group. ARSS provides a wide range of support for analyzing, modeling, and controlling reactor power systems. The lab is commissioned by the US NRC to review all vendors' new reactor design submissions. With their expertise and resources, PCTRAN will evolve into a major analytical and simulation tool in the development of advanced reactor systems.
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