Transcript Overview of Conventional 2

Overview of Conventional 2-loop PWR
Simulator
PCTRAN
Dr. Li-Chi Cliff Po
Micro-Simulation Technology
10 Navajo Court
Montville, New Jersey
http://www.microsimtech.com
[email protected]
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Introduction
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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.
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Background
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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.
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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.
PCTAN 2-loop PWR
Transient Simulations
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Normal operation control - startup, shutdown, power ramp
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Loss-of-coolant-accident (LOCA) or steamline break
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Loss of flow, single or two-phase natural circulation
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Turbine trip with or with bypass, station blackout
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Steam generator tube rupture (PWR)
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Feedwater transients
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Anticipated transient without scram (ATWS)
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Damage to containment or spent fuel storage facility (for
example, caused by airplane crash)
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Intentional sabotage by terrorist group to cause a reactivity
event, fire or loss of diesel
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Any combination of above
Severe Accident
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Use 6-node vertical core Model with decay heat properly distributed.
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Two extra nodes for bottom of vessel metal and melted debris make
total 8 nodes in the core.
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Metal-water interaction and generation of hydrogen will be accounted
for in each node.
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Hydrogen may be detonated if concentration reaches the ignition
condition.
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Containment failure may be resulted by heat, pressure or combination
of both.
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Melting in each node may take place if calculated temperature exceeds
the melting point.
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Corium-Concrete Interaction in the reactor cavity. Generate
Radiological release source term for offsite dispersion
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Core-melt with Cavity Flooding to prevent Vessel Failure
Conclusions
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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.
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