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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 assistance of modern computer graphics to operate interactively on a PC. The source code is in FORTRAN. It is a product of twelve years of development. Extensive verification had been 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.. They were 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 are 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. are 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 offsite 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 will prepare one that could include 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 offsite release will be projected. These could be used as input to the plant's dose dispersion model for offsite dose distribution estimate. The system will then be an integral part for the plant's emergency response plan.



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