Introduction

1. Overview of Conventional 2-loop PWR SimulatorPCTRANDr. Li-Chi Cliff PoMicro-Simulation Technology 10 Navajo CourtMontville, New Jerseyhttp://www.microsimtech.cominfo@microsimtech.com

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.