Available Plant Models
The following types of PCTRAN models for light water reactor plants are available.
- BWR View screen | Download
- Boiling Water Reactors such as General Electric BWR-2 to BWR-6 with Mark I to III containments, ABWR or ABB BWRs.
- PWR/UTSG View screen | Download
- Pressurized Water Reactors of inverted U-tube steam generators, e.g. 2, 3 or 4 loop plants of Westinghouse, Framatome or KWU designs; or 2x4 (2 hot legs and 4 cold legs) C-E designs.
- PWR/OTSG View screen | Download
- PWRs of once-through steam generators of B&W or ABB design.
- AP1000 View screen | Download
- Westinghouse designed advanced PWR with passive safety systems.
- VVER 1000 View description
- Russian VVER440 and 1000 PWR with horizontal steam generators
Each one is available in four versions with progressive capabilities. (See next section.)
Available Versions for Each Plant
Standard Version
The standard versions of anyone of the above plant models
are available in the form of "out-of-the-shelf" object
codes. The executable program will accommodate differences in
the plant specific features such as geometric size, mega-watt
rating, number of coolant loops, primary and secondary flow characteristics,
ECCS capacity and set points, etc. by entries of the input data
sets. A standard data set in ASCII format for a typical plant
of that type will be provided. The user can alter the data entries
according to the provided manual instructions so that they will
represent the plant of concern. In order for users' comprehension
of the theoretical basis and modeling approach, a complete theory
manual will be provided.
Plant Specific Version
The source code will be modified to accommodate your plant
specifics in detail. The scope of the simulator will be individually
defined according to the client's need. It could range from a
simple one for NSSS simulation only to the most extensive model
encompassing core-melt, RMS and source term. The simulator's
performance will be verified against the plant Final Safety Analysis
Report (FSAR) and other plant operation data and documented in
a verification report. The source code may be included in the
deliverable package if it is desired and specified in the sales
contract.
Once top of the core is exposed, calculation will continue to allow melt and relocation. See detail in the Severe Accident Model description.
Area dose assessment is included following a severe accident release for either PWR or BWR. If you simply want to examine the dispersion model, a stand-alone version PUFF is provided in the download list. For commercial product version it can be used as a "dirty bomb" simulator. Isotope release source term is input to this software and area dose assessment is the output.
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