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PCTRAN Component Models

PCTRAN is a simulation program that incorporates knowledge of reactor physics, thermal hydraulics, control system, etc. into solution techniques with the assistance of modern computer graphics that enable interactive operation on a PC. The source code is in FORTRAN. It is a product of twelve years of development that has included extensive verification conducted against Final Safety Analysis Reports and validated with respect to real plant data and other computer analyses such as RETRAN, RELAP5, TRAC, MAAP, SAFE, etc.. These verification analyses have been documented by over a dozen published papers in professional journals. Reprints are available upon request.

PCTRAN is under a continuous upgrading and enhancement program so that new features will be incorporated into the package periodically. Currently it has the following component models:

Thermal Hydraulics Model
Lumped-loop approach with two-phase critical flow discharge, non-equilibrium pressurizer for PWR and drift flux model for BWR
Core Kinetics Model
Point kinetics model with rod control and reactivity feedback from moderator temperature, Doppler, and voids
Control System
PWR's rod, pressurizer pressure and level, steam generator feedwater, turbine header pressure, and steam dump control modelled to operate either in "AUTO" or "MANUAL" mode following the unit load demand; BWR's rod, recirculation flow, and feedwater system are controlled to reach the same goal
Containment Model
Containment's structure, cooler, spray, vent, etc. modelled to keep track of post-LOCA conditions
Severe Accident Model
For an exposed core, the fuel clad may be overheated, and fission products may be released into the reactor coolant and containment. They may be further released into the ambient atmosphere depending upon the open pathways. Radioactive isotope types and their release pattern are generated as source terms for an off-site dose estimate. For clad temperature beyond 1000âC, metal-water reactions will generate hydrogen. The containment hydrogen concentration will be calculated, and its combustibility will be checked throughout the transient.

Upon a client's specific order for the most extensive severe accident simulator, MST can prepare one that includes simulation of the plant's radiation monitoring system (RMS). This could be used as a tool for the plant's Severe Accident Management program. Normal and accident readings for all area, effluent, and process monitors throughout the plant will be calculated, and source terms for off-site release will be projected. These results could be used as input to the plant's dose dispersion model for off-site dose distribution estimate. The system could then be an integral part of the plant's emergency response plan.


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