PCTRAN is nuclear power plant simulation software specifically designed for beyond - design-basis accidents including severe accidents and intentional sabotage . Core melt, containment and spent fuel pool failures are within its scope.

The sixth generation of PCTRAN extends NPP simulation to offsite dose projection. All operational and radiological release data are accessible by onsite and remote technical support or corporate personnel. During a training or exercise session, a client may even conduct its own projections and feedback to the server end instructor or emergency control director.

Given increased concern in intentional or complicated events, PCTRAN prepares a nuclear power plant's personnel with realistic training and exercise. The web-based simulator extends to severe accidents, generates radiological release source terms and makes area dose projection according to live meteorological conditions . Its speed can be either real-time or many times faster. Operation is user-friendly in its graphical-user-interface (GUI). All graphics, text messages and data are transmitted seamlessly back and forth via existing IE Explorer.

In the plant mimic, there are icons showing simultaneous containment failure, reactor coolant boundary leak and fuel pool damage. The combined radiological releases contribute to dose distribution in EPZ. This can aid EAL determination as well as protective shielding or evacuation recommendation.

Transient Simulations

Selection of a transient is menu-driven that includes all possible disturbances to a plant such as:

•  Normal operation control - startup, shutdown, power ramp
•  Loss-of-coolant-accident (LOCA) or steamline break
•  Loss of flow, single or two-phase natural circulation
•  Turbine trip with or with bypass, station blackout
•  Steam generator tube rupture (PWR)
•  Feedwater transients
•  Anticipated transient without scram (ATWS)
•  Damage to containment or spent fuel storage facility (for example, caused by airplane crash)
•  Intentional sabotage by terrorist group to cause a reactivity event, fire or loss of diesel
•  Any combination of above

Severe Accident Model

The core is modeled into six vertical nodes. Each one will generate a portion of the decay heat. When the boundary heat removal rate is less than the core heat, the core node is heated up to the point of melting. Molten fuel may collapse into the bottom of the vessel. The vessel lower head may then heat up to the melting point, too. The molten debris may drop into the containment cavity floor. During the fuel damage process, first the fission gas in the clad may leak out. Later if the fuel and cladding continue their degradation, fuel isotopes will release also. In addition to iodine and noble gases, there are alkali metals, tellurium, barium, cerium, lanthanides, etc. The elevated concentration of these radioactive isotopes would find their ways through the vessel break, relief valves, and containment leakage into the environment.

PCTRAN is most powerful in its versatile and interactive control. The user can at any time manually trip the reactor or the pumps, open or close a relief valve, override the ECCS or change the set points for a number of the control systems. All transient parameters are available for trending during execution or printed after the run. The data can be saved in Access or Excel files for later usage. The restart capability can virtually extend a transient simulation to indefinite time period.

RMS Source Term & Area Dose Projection

Available as an option, the extended simulation model keeps track of fission product transport along the major release pathways. Normal and accident condition readings of major area, effluent, and process radiation monitors throughout the plant are displayed in a separate mimic. Iodine, noble gases and other fission products based on Regulatory Guide 1.183 Revised Source Terms are calculated periodically. Plume or puff release is then projected for variable wind speed and stability factors in the Emergency Planning Zone.

Available Plant Models

MST has completed the following models in Windows:

•  GE BWR 2 (Oyster Creek), 4 (Peach Bottom), 5 ( La Salle ), 6 (River Bend) and ABWR (Lungmen) with Mark I, II, III or advanced containment
•  Westinghouse 2-loop ( Point Beach ), 3-loop (Turkey Point) and 4-loop ( Salem ) PWR dry containment or ice condenser containment (Sequoyah)
•  Westinghouse AP1000
•  C-E PWR's of 2x4 hot/cold loops (St Lucie and Fort Calhoun ), System 80+, Korean Advanced PWR
•  B&W (now Areva) PWR's of once through steam generators (TMI)
•  Framatome PWR's ( Guangdong ) or Areva EPR 1600
•  ABB BWR's (TVO)
•  Russian VVER-440 and 1000 of horizontal steam generators


Westinghouse AP1000 Passive Containment Cooling System

Computer Configuration  

Any Pentium or compatible PC with SVGA graphic monitor and color printer is required. The operating system should be Windows 2000, XP or NT with MS Office Suite installed. Simulation speed is adjustable from real-time to fast time. For a 1.4 GHz processor, the maximum speed is about 16 times faster than real-time.

Free CDROM  

A full capability demonstration package is available upon request. Alternatively, a number of plant types' can be downloaded from MST's website http://www.microsimtech.com


Training – A Training Simulator for operators and engineers training in reactor theory, transient phenomena and diagnostic skills. A comprehensive training lesson plan from basic principles to symptom oriented emergency diagnosis can be developed in conjunction with the software.

Emergency Exercise – Generate emergency drill scenarios and conduct actual exercises. Data at selected time interval can be prepared and handed out to drill team for an undisclosed event. Data on core damage, radiological release and offsite dose projection support a comprehensive exercise.

Application Analysis – Parametric/Scoping Study
For system modifications and licensing support, development of emergency procedures, responding to regulatory inquiries such as system performance, equipment sizing, operator actions, etc., repetitive runs can be conducted with immediate turnaround for answering “what if” type of questions.

Probabilistic Risk Assessment (PRA) – To predict consequences of selected event branches leading to core melt and/or containment failure, and their contributions to overall plant risk.

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