1. Overview of Conventional 2-loop PWR Simulator. PCTRAN Dr
Overview of Conventional 2-loop PWR Simulator PCTRAN Dr. Li-Chi Cliff Po Micro-Simulation Technology 10 Navajo Court Montville, New Jersey

2. Introduction
Micros-Simulation Technology was founded 1985 in New Jersey USA.
Has developed the first PC-based nuclear plant simulator.
Used by US Nuclear Regulatory Commission since 1986 and hundreds of government agencies and nuclear plants all over the world.
Founding Lecturer Director and PWR courseware provider of the IAEA “Advanced NPP Simulation Workshop” since 1996.

3. Background
Has all new plant types Areva EPR, Westinghouse AP1000, Korean APR1400, Toshiba ABWR, Russian VVER1000, Mitsubishi APWR and experimental pool reactor simulators.
Using Microsoft Visual Basic and Access for Windows7 or XP environment, operate interactively with Graphic User Interface in real-time or faster speed.
All are validated and verified against FSAR and actual plant data.
Has Severe Accident and Dose Dispersion Capabilities.

4. Features
Generic two-loop PWR with inverted U-bend steam generators and dry containment system.
Rated about 1800 MWt or 600 MW electric.
One loop with the pressurizer is modeled separately from the other loop.
PWR plants like Point Beach, Kewaunee, Prairie Island and Ginna in the US, Mihama 1 in Japan, Krsko in Slovenia, Angra 1 in Brazil and ChinShan 2 in China.

5. PCTAN 2-loop PWR

6. Transient Simulations
·         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

7. Severe Accident
·       Use 6-node vertical core Model with decay heat properly distributed.
·       Two extra nodes for bottom of vessel metal and melted debris make total 8 nodes in the core.
·       Metal-water interaction and generation of hydrogen will be accounted for in each node.
·       Hydrogen may be detonated if concentration reaches the ignition condition.
·       Containment failure may be resulted by heat, pressure or combination of both.
·       Melting in each node may take place if calculated temperature exceeds the melting point.
·       Corium-Concrete Interaction in the reactor cavity. Generate Radiological release source term for offsite dispersion

8. Core-melt with Cavity Flooding to prevent Vessel Failure

9. Conclusions
Not just for future control room operators, but for the entire generation of technical staff entering into nuclear power.
User controls the data input to model different plant design and operation features such as power level, pump and valve size and characteristics, control and alarm set points, etc.
Valuable tool for training, education, technical evaluation and safety analysis.