An Instrumentation and Control for Loop Test 21-24 Aug. 2012 S.H. Ahn, J.T. Hong, C.Y. Joung, S.J. Park Neutron Utilization Technology Division 0
Contents 1 Introduction Click to of add HANARO Title 2 Pressurized Click to Water add Loop Title 13 Instrumentation Click to add and Title Control System 24 Test Rig Click & In-Pile to add Instrumentation Title 15 Conclusions Click to add Title 1
Characteristics of HANARO Type Power Coolant Reflector Open-tank-in-pool 30 MW th Light Water Heavy water Fuel Materials U 3 Si, 19.75% enriched Absorber Hafnium Reactor Building Confinement Max Thermal Flux 5x10 14 n/cm 2 s Typical flux at port nose 2x10 14 n/cm 2 s 7 horizontal ports & 36 vertical holes Vertical hole for cold neutron source Operation Cycle 24 days@5 weeks 2
HANARO Cold Neutron Beam Radiography Fuel Test Loop Material Irradiation Neutron Activation Analysis NTD Neutron Beam Research Neutron Irradiation Research Operation & Development RI Production & Utilization Reactor Operation Experimental Facility Operation Public Welfare Industrial Application 3
Pressurized Water Loop Pressurized water loop Simulates the steady-state operation condition of PWR Irradiation Hole : IR1 Accommodate up to 3 pins of test fuel 4
Schematic Diagram of Loop 5
Main Design Parameter of Loop Parameters PWR test mode Design Pressure, MPa 17.5 Design Temperature, 350 Operating Pressure, MPa 15.2 Operating Temperature (IPS Inlet), Operating Temperature (IPS outlet), 300.3 312.0 Operating Flow, kg/s 1.65 6
Instrumentation and Control (I&C) System Safety Classification System Panels/System Composition Functions Design Nuclear Safety Related Reactor Shutdown System Loop Shutdown System - Loop Protection Panels (3 Channels) - Loop Safety Control Panels (2 trains) - Loop Safety Indicator Panel Reactor Shutdown Loop Isolation - IEEE std-603-2/3 Logic - Interconnection with Existing RPS (Reactor Protection System) Non- Nuclear Safety Related Process Control System Data Acquisition System Loop Control System Data Acquisition System Control for Non-Safety Related Process System Data Acquisition, Storage, Display and Analysis for Irradiation Test - Normal Operation at HANARO Control Room - Redundancy of Control and Communication Network - HCS (Hybrid Control System) - AI/AO - DI/DO - Interface with SPND, T/C, LVDT 7
Composition of I&C System Reactor Control Room : Normal Operation Loop Control Room : Start-up, Maintenance DAS Station Engineering Station Operator Station Operator Station Data Acquisition System Loop Control System Loop Protection PNL -1/2/3 Loop Safety Indicator PNL Loop Safety Control PNL-1/2 Reactor Protection System PNL-1/2/3 Loop Control Room Reactor Control Room Measurement Signals from Test Rig Electrical System Process System 8
Signal Flow of Safety Related Control System Trip Signals from HANARO Trip Signals from FTL FTL Protection Panels Reactor Protection Panels Loop Safety Control Panels Reactor Shutdown Signal FTL Isolation Signal Loop Safety Indicator Panel Loop Control Room Reactor Control Room 9
Safety Related Control Panels Design Quality Class : Q Seismic Category : I IEEE std-603 - Single failure criterion/ Redundancy/ Independence/ Diversity/Fail-Safe/ Manual Initiation/ Channel Bypass/ Identification of Protective Action/ Interface with Non-Safety Related System/Equipment Qualification. etc. Loop Protection Panels Manufacturing Qualification - Environmental Qualification : IEEE std-323 - Seismic Qualification : IEEE std-344 Loop Safety Control Panels & Loop Safety Indicator Panel 10
Non-Safety Related I&C System Loop Control System HCS (Hybrid Control System) Redundancy of Control and Communication Network Normal Operation at Reactor Control Room Data Acquisition System Data Acquisition, Storage, Display from In-pile Instruments Communication with Loop Control System 11
Remote Date Acquisition Web based remote data acquisition Data Acquisition System : Web Server PC : Remote Area : Web Client Independent Network Real time data acquisition at remote PC 12
IPS Including In-pile Instruments Test Fuel Fission gas pressure Fuel centerline temp. Coolant temp. Neutron flux 13
In-Pile Instrumentation Installation at Rods Parameters (Instruments) Rod 1 Rod 2 Rod 3 Upper Part Fuel Rod Pressure (LVDT) Centerline Temperature (C-Type T/C) Centerline Temperature (C-Type T/C) Lower Part - Upper Part Centerline Temperature (C-Type T/C) Lower Part - Installation at Rig Position Neutron Flux (SPND) Upper/Middle/Lower Coolant Temperature (K-Type T/C) Upper/Middle/Lower (3 번핵연료는 2 번핵연료와동일 ) Rod 1 Rod 2&3 14
Manufacturing Procedure for Test Rig Parts Manufacture & Instruments Purchase Insulation Resistance Test Parts Manufacture (ASME Certificate of Authorization) Welding Inspection Inspection & Measurement of Parts and Instruments Assembling and Welding of Fuel Rod for Test Test and Inspection of Fuel Rod (for Test) after Welding Macrography Dimension Inspection Fuel Rod Assembling to Test Rig Instrument Cable Assembling to Test Rig Parts Assembling Insulation Resistance Test Dimension Inspection Hole Drilling of Test Fuels, Inspection/Cleansing Tensile Test Brazing (ASME IV, Brazing Procedure) Hydraulic Test Assembling and Welding of Fuel Rods Organization Check Inspection (ASME III, Authorized Inspection) Test and Inspection of Fuel Rods after Welding Helium Leakage Test Test and Inspection of Test Rig after Assembling Helium Leakage Test Manufacturing of Fuel Rods Manufacturing of Test Rig 15
Manufacturing of Test Rig Manufacturing of Fuel Rods Manufacturing of Test Rig Manufacturing of Test Rig Test and Inspection of Test Rig after Assembling 16
Technology Development (1) Sealing of instrumentation cable feed-through (Brazing method, Mechanical sealing method) Instrumentation cables Brazing Sealing Part Mechanical Sealing Brazing 17
Technology Development (2) Rig with removable typed fuel rod for intermediate examination Mechanical Joint Part Instrumented Fuel Rod Non-Instrumented Fuel Rod Welding technology for fuel rod and rig fabrication (TIG, Laser, etc.) 18
Technology Development (3) In-pile Instrumentation Technology Drilling of pellet Fuel centerline temp. measurement Fission gas pressure measurement Neutron flux measurement Coolant temp. Coolant flow Fuel elongation measurement Cladding swelling measurement Connection of MI cable etc. 19
Conclusions Instrumentation and Control for Pressurized Water Loop Safety Related Control System Non-safety Related Control System - Loop Control System - Data Acquisition System : connected with in-pile instruments Technology Development in KAERI Rig design and Fabrication In-pile Instrumentation 20
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